ML20203J199
| ML20203J199 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Haddam Neck, 05000000 |
| Issue date: | 08/09/1985 |
| From: | NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML20203J178 | List: |
| References | |
| NUDOCS 8604300139 | |
| Download: ML20203J199 (100) | |
Text
y. - .- ,- m, - , ,, -- - -.;.-- m -
7 . =-mm p . . -
l.
r.
ABSTRACT NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM (NUQAP)- <
TOPICAL REPORT Northeast Utilities (NU) has developed and is implementing a.compre-hensive Quality Assurance Program to assure conformance with established !
- regulatory requirements, set 'forth by the. Nuclear Regulatory Commission'.
(NRC), and accepted industry standards.- . The participants in the NU -
- ' Quality Assurance Program assure that'the design, procurement,.construc-tion, testing, operation, maintenance, repair- and modification of nuclear. ,
power plants are performed in a safe and effective manner.
The NU Quality Assurance Program.(NUQAP) Topical Report complies.with the requirements set forth in Appendix B, of 10 CFR Part 50,;along with applicable sections of the Safety Analysis Report-(SAR) for each license application, and is responsive to the United States -NRC Regulatory Guide 1.70, which describes the information required to be presented in the j Quality Assurance Section of the SAR's for nuclear power plants.
This NUQAP is also established, maintained and executed with regard to Radioactive Material Transport Packages as allowed by-10 CFR 71.101(f). .l Quality Assurance provisions for Fire Protection activities are detailed in the Northeast Utilities Fire Protection. Program.
The NUQAP is committed to utilize the guidance.obtained from'the Regula--
O tory documents and their endorsed Standards'.as referenced in Appendix D-of the Topical Report.
I QAP . Abstract ;
Rev.: '7-
" Datei AUG 0.R M 5604300139 86 . 3
- 1 ADOCK 0 PDR Page.1 of'1 ,
- s P J
, - . , - . -.w. ~ . . _ , > . , ,.c -
, . . g.., ., . ._ ~ms. , .,- -
UNITED STATES
~
/g* E8hg%,
NUCLEAR REGULATORY COMMISSION
, [ ReCION l
[\ re
- est PanM AVENUC
1
-l AUG 0 91985 Docket Nos. '50-213 ~
t 50-245
) 50-336 i
50-423 Northeast Nuclear Energy Company -
ATTN: Mr. J. F. Opeka Senior Vice President - Nuclear Engineering and Operations Group Post Office Box 270 4
Hartford, Connecticut 06141-0270 Gentlemen:
-t
Subject:
10 CFR 50.54(a)/50.55(f) Quality Assurance Program Description Review - Northeast Utilities Quality Assurance Program Topical i
t Report (Revision 7) for Haddam Neck Plant, Millstone Nuclear _
Power Station, Unit Nos.1 and 2 (Operation) and Millstone Nuclear
{ Power Station, Unit No. 3 (Construction)
Reference:
J. F. Opeka Letter to Dr. T. E. Murley, dated June 5, 1985 i We have received the above referenced letter, submitted per the . requirements I of 10 CFR 50.54 a Assurance progra(m)/50.55(f), which documents twenty-two changes to your. Qual i j Topical Report. The Region'I staff has reviewed these changes and found them to be acceptable, as they did not reduce your commitments in the 7 Quality Assurance Program previously accepted by the NRC. U
-1 Additionally, as documented in the NRC letter dated July 3,1985, the Office !
of Inspection and Enforcement staff reviewed the proposed revision for Millstone- 1 i
- Unit 3 operations phase and found it to be acceptable.
The effectiveness of your QA Program implementation will continue to 'be the
! subject of routine regional inspections.
i f21[)33y,3have any questions concerning the above please' contact Madan Dev at. -
l l'
j Sincerely,
_,4. N -
- Stewart D. Ebneter, Director .
Division of. Reactor Safety .
i i
- --.rr ,.- ,---.,e, , , , . . _ . - . _ . , . . , , .,m-, , , . , . , - _ ., , . . _ , ,,y-- ,,.- ,, ,_, a -,e ,
, . . . ~ . . , - - _,,.,-p. . -
, ~ Northeast Nuclear Energy Company 2 cc:
R. Graves, Plant Superintendent E. J. Mroc:ka, Vice President, Nuclear Operations W. D. Romberg, Station Superintendent D. O. Nordquist, Manager of Quality Assurance V. Papadopoli, Construction Quality Assurance Supervisor R. T. Laudenat, Manager, Generation Facilities Licensing Gerald Garfiel($ Esquire IE/QUA8 Public Document Room (POR) .
Local Public Document Room (LPOR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of Connecticut 1
I 0
(
h
- w .,; g --; ~ y eg- m ~=
- , .
n m .xrm<
seio.n sir..t. s.ri'a coan.ct' cut Q NOkTHEAST UTILITIES o.a.r.i On.c.
'b I )v'.CC$$[sIiNc'EU a + .co. .o . c"""
P O. BOX 270 HARTFORD. CONNECTICUT 06141-0270 L t ; y,((' *[" "j '""",
(203) 665-s000 June 5,1985 Docket Nos. 50-213 50-245 30-336 50-423
- F0574A Dr. Thomas E. Murley Regional Administrator R.egion !
l U.S. Nuclear Regulatory Commission l 631 Park Avenue
! King of Prussia, PA 19406
References:
- 1. W. G. Counsil letter to T. E. Murley, A03039, dated June 8, 1984.
! 2. W. G. Counsil letter to B. 3. Youngblood, " Millstone Nuclear (oC) Power Station, Unit No. 3, Transmittal of Amendment 3,"
dated August 29, 1983.
- 3. W. G. Counsil letter to B. 3. Youngblood," Millstone Nuclear Power Station, Unit No. 3, Response to SER Confirmatory item 70," dated March 1,1985.
Dear Dr. Murley:
Haddam Neck Plant Millstone Nuclear Power Station, Unit Nos.1,2 and 3 Annual Reporting of Changes to the Quality Assurance Program j 1
Proposed Revision 7 to the Northeast Utilities Quality Assurance Program Topical Report 1
in accordance with 10CFR50.54(a)(3) and 30.55(f)(3), transmitted herewith are three (3) copies of proposed Revision 7 of the Northeast Utilities Quality Assurance Program (NUQAP) Topical Report (Attachment II) submitted for your review and approval. Proposed changes to the Topical Report are indicated by a vertical line in the right-hand margin. The reason and basis for each change t.e detailed in Attachment I which is arranged in a sequence which coincides with the Topical Report sections. Attachment I does not include minor editorial changes in accordance with 50.54(a)(3)(li) and 50.55(f)(3)(ii).
I n Several of the changes to the Topical Report are the result of commitments
( ) made in response to the NRC's Requests for Additional Information for the
'V Millstone Nuclear Power Station, Unit No. 3 (References 2 and 3). Changes which are related to specific NRC questions are detailed in Attachment I and are followed by the question number (i.e., Q260.XX).
ywpwww. w.:ma n :- 7 : .< mmmmw .
- n-n. . .- ..
L l
'p .
, k All changes included in proposed Revision 7 of the NUQAP Topical Report have -
the effect of upgrading our quality assurance program which continues to meet-the criteria of 10CFR50 Appendix B.
.Please note that the draft NUQAP Topical Report is shown as Revision 7 without i a date. This draf t will be issued as Revision 7 and dated the same as your effective date of approval when we receive it, or sixty (60) days following this -
submittal as prescribed in 50.54(aX3)(iv) and 50.55(fX3Xiv).
l if you have any questions regarding this submittal, please contact Mr. Donald O.
Nordquist at (203) 665-5447.
Very truly yours, NORTHEAST UTILITIES SERVICE COMPANY l
d* .D '
- 3. F. Opeka Senior Vice President O
h By: C. F. Sears Vice President i
cc: U.S. NRC Document Control Desk (15 copies)
NRC Region IV Vendor Program Branch (1 copy)
- 3. Shediosky - NRC Senior Resident inspector - Millstone Station (1 copy)
T. Rebelowski - NRC Senior Resident inspector - Millstone Unit No.
3-(1 copy)
P. Swetland - NRC Senior Resident inspector - Haddam Neck (1 copy)
D. Lipinski - NRC Resident inspector - Millstone Station (1 copy) 9
, - .- n. A m w ~ ., r .2 .- z .m m m
\ ) -
'# Attachment i Summary of Changes to NUQAP Topical Report Proposed Revision 7 _
ABSTRACT o Deleted the :eference to the revision level of Regulatory Guide 1.70.
Applicable evisions are detailed in Appendix D.-
o Changd to correct the reference to 10CFR Part 71 due to the
- r. organization and renumbering of Part 71. ,
QAP 1.0 ORGANIZATION o Paragraphs 1.2.2 and 1.5.1 - Title change for the System Director -
Purchasing and Materials Management.
o Paragraphs 1.2.2, 1.5.2.1, 1.5.2.2, 1.5.2.3.b.4, and 1.5.2.4 - Detail reorganization, changes in title and responsibility within-the.Information Resources Group. This includes the addition of a Director - Informaticn Resources Administration.
o Paragraphs 1.4.2, 1.4.2.1.d and 1.4.2.1.e - Revised to reflect the A reorganization of the Nuclear Operations Analysis Branch into the Nuclear V Materials and Chemistry Branch and the Nuclear Safety Engineering Branch.
o Paragraph 1.4.2.1.c - Deleted reference to sections and, units within t.he Reliability Engineering Branch for consistency with other organizations described in QAP 1.0.
o Paragraph 1.4.2.2 -
Added details of the organizations within the Environmental Programs Department for consistency with other organizations described in QAP 1.0.
o Figure 1.2 - Details System Director -
Purchasing and Materials Management title change.
o Figure 1.4 - Changed to reflect the reorganization of the Nuclear Operations Analysis Branch into the Nuclear Materials and Chemistry Branch and the Nuclear Safety Engineering Branch.
o Figure 1.7 - Changed due to the reorganization of the Information '
Resources Group.
QAP 2.0 QUALITY ASSURANCE PROGRAM o Paragraphs 2.1 and 2.2.3 - Clarification of the applicability of the QA program was made to correct the disagreement between these paragraphs and the first paragraph of Appendix A.
(Qv l
M M.. ,. . .;
-, ,:s.m + .n. .v... wu w y a m ;. W m +-- + --
-p QAP 4.0 PROCUREMENT DOCUMENT CONTROL o Paragraph 4.2.1 - Revised to ' clarify that the Llatest Quality Assurance program and procedural requirements are applied to the procurement of spare or replacement parts (Q260.33).
QAP 6.0 DOCUMENT CONTROL o Paragraph 6.2.2 - Revised to clarify that controlled document acknowledgement of receipt forms are completed and returned (Q260.30).
QAP 10.0 INSPECTION .
o Paragraphs 10.2.2 and 10.2.4 - Added provisions to include accuracy -
requirements for intpection measuring and test equipment in job packages, inspection procedures, plans, or checklists (Q260.36 and Q260.38).
o Paragraph 10.2.6 - Revised to clarify that an inspection result evaluation can be performed by qualified personnel outside of the NUSCO/NUPOC ,
QA/QC organizations. This will allow Reactor Engineer evaluation of fuel inspection results and Reliability Engineering evaluation of ISI results.
QAP 12.0 CONTROL OF MEASURING AND TEST EQUIPMENT o Paragraph 12.2.1 - Revised to include instruments under the heading of Measuring and Test Equipment.
o Paragraph 12.2.2 - Revised to remove the distinction between measuring and test equipment and measuring and test instruments.
QAP 16.0 CORRECTIVE ACTION o Paragraph 16.2.1 - Revised the responsibility for review and concurrence of corrective action procedures ~ to agree with the. procedure review responsibilities of paragraphs 2.2.2 and 5.2. .
APPENDIX A CATEGORY I SYSTEMS, STRUCTURES AND COMPONENTS o Clarification of the applicability of the QA program was made to correct the disagreement between Appendix A and ' paragraphs 2.1 and 2.2.3 of QAP 2.0.
APPENDIX C LIST OF TYPICAL QUALITY ASSURANCE RELATED -
PROCEDURES o The appendix was updated to reflect current procedures issued by various organizations within NU.
APPENDIX D REGULATORY GUIDE AND ANSI STANDARD COMMITMENTS o The commitment to ' Regulatory Guide 1.70 was updated to detail .the applicable revision for each generating f acility.
, _ , 9e, ','. ':.':Lg u .%;y i>-c :+.n.;;r;,.i.. nice:.7ge,w;w 6:a m=~ ?
> 7:a >vs s ::::.
=- R. , - -
t-
.l 3.. ;
-t APPENDIX E GLOSSARY OF QUALITY ASSURANCE TERMS
. -i o - Revised the. definition of .' Measuring and Test. Equipment . to include i fixtures, reference ^ and transfer standards .and nondestructive test ,
equipment. j i
[
t e
' i 4
t i
4 1
b 5
1 f'
- r. s y y g m .T- , ciP.- - ,
.e f. . g-- ,
.v- -
I !
TABLE OF CONTENTS -
'> NORTifEAST UTILITIES _ GUAI.ITY ASSURANCE. PROGRAM ,(NUQAP)
TOPICAL. REPORT Rev. Pages Abstract 7 1 Table of Contents 7 1 Policy Statement 7 1 Introduction , 7 1 l
Quality Assurance Program QAP 1.0 Organization 7 1-16 Organizational Charts 7 Figs. 1.1-1.7 QAP 2.0 Quality Assurance Program 7 1-7 QAP 3.0 Design Control 7 1-6 l QAP 4.0 Procurement Document Control 7 1-4 l
QAP 5.0 Procedures, Instructions and Drawings 7 1-3 QAP 6.0 Document Control 7 1-4 QAP 7.0 Control of Purchased Haterial, Equip- 7 1-4 l ment and Services QAP 8.0 Identification and Control of 7 1-2 1
7-~3 Materials, Parts and Components
! (/;
QAP 9.0 Control of Special Processes 7 1-3 -
QAP 10.0 Inspection 7 1-4 QAP 11.0 Test Control. 7 1-3 QAP 12.0 Control of Measuring and Test Equip- 7 1-3 ment QAP 13.0 Handling, Storage, and Shipping 7 1-2 QAP 14.0 Inspection, Test and Operating Status 7 1-2 QAP 15.0 Nonconforming Materials, Parts, 7 1-3 Components, or Services QAP 16.0 Corrective Action 7 1-2 QAP 17.0 Quality Assurance Records 7 1-2 QAP 18.0 Audits 7 1-4 Appendices A. Category I Systems, Structures and Com- 7 1-3 ponents B. Qualification and Experience Requirements 7 1 NUSCO Manager, Quality Assurance C. List of Typical Quality Assurance Related .
Procedures 7 1-35 D. Regulatory Guide and ANSI Standard 7 1-2 Commitments E. Glossary of Quality Assurance Terms 7 1-7 F. Program Exceptions 7 1-2
(%
\ !
\/
QAP' Table of Contents Rev.: 7 Date:AUG 0 91985 Page 1 of I
- - .;.;c . .
- , y - n- .,- ;v y? . a - m . rn, ,;s.pm - a?s r
.( .
POLICY STATEMENT NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM ,
TOPICAL REPORT The policies, requirements and tasks contained in this Northeast Utili-ties QualJty Assurance Program description have been developed to achieve a recognized need for quality assurance during the design, procurement, construction and operation of our nuclear facilities. i Northeast Utilities procedures which implement this program are described in various manuals which are referenced herein. '
The program has been established to , comply with the requirements of Title 10, Code of Federal Regulations, Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants." It is also responsive to selected NRC Regulatory Guides as well as ANSI N45.2.
The development and overall responsibility for this Quality . Assurance Program lies with the NUSCO Executive Vice President - Engineering and.
Operations. Corporate authority is delegated to the NUSCO Manager, Quality Assurance for the preparation and administration of the Quality Assurance Program. Individual group Vice Presidents are responsible for the implementation of their portion of the Northeast Utilities Quality Assurance Program. Revisions, additions to, and audits of this program O are the responsibility of the NUSCO Manager, Quality Assurance. Any revisions or additions shall be approved by affected Departments prior to the incorporation of such changes into the program.
or s W. F. Fee Executive Vice President - Enaineering and Operations Northeast Utilities t
I i
1 j
QAP -' Policy Statement-i Rev.: 7
' Date:I. . ..
Page'l of l
. .si5
n- ;
, . , _-- , ; .; m, , . . _
r._..,
, ,~, . . ,
q (U \ -
INTRODUCTION NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT This Northeast Utilities Quality Assurance Program (NUQAP) Topical Report contains the quality assurance requirements which are relative to the safety of the nuclear power plant. The Topical Report consists of the following three parts:
- 1. Introduction, which delineates the purpose of the Topical Program, and summarizes its scope and applicability. -
- 2. Quality Assurance Program (QAP), which summarizes the quality assurance approach, through eighteen criteria, to activities related to Category I material, parts, components, systems and services.
- 3. Appendices, which provide supporting statements and tabulations.
This NIQAP Topical Report has been prepared to document that a meaningful '
quality assurance program has been established and implemented to ensure that adequate quality requirements are being complied with to safeguard NU e.nployees, contracted personnel and the general public, from the conceptual phase through the operations phase of nuclear power plant Iffe.
V) s The NUQAP establishes controls which are applicable to systems, struc-tures, components, material, parts and services identified as safety related and listed for each nucleat power plant and supplemented, if applicable, for plant betterment projects. The controls which implement the actions identified in the NUQAP Topical Report are departmental pro-cedures and instructions which delineate actions and steps necessary to accomplish safety related quality requirements. Procedures and instruc-tions are written by company groups, divisions, departments, branches, or sections, which hive the responsibility for implementing actions assigned to them as delineated by the NUQAP. Quality related procedures and revisions thereto are reviewed by and concurred with by the applicable NUSCO/NUPOC Quality Assurance Organization, in accordance with QAP 2.0 and QAP 5.0.
The NUQAP is responsive to applicable codes, Nuclear Regulatory Commis-sion regulatory requirements, accepted industrial standards and revisions thereto. Provisions are established to update the NUQAP Topical Report in accordance with revisions to codes, standards and regulatory require- '
ments, and to inform cognizant personnel to implement appropriate action to assure the highest standard of quality is achieved for safety related systems, structures, components and services for nuclear power plants.
GL b U Donald O. Nordquist NUSCO Manager, Quality Assurance (nV)
QAP - Introduction
;lF - ns Page 1 of 1
GyCWne;n Q2 _ ' myWW% v 2% es m-%Mme
. -c
. , r L4 d I. 0' ORGANIZATION 4
1.1 INTRODUCTION
Northeast Utilities (NU) is a holding company-which owns all of'the.
[- common stock in several companies as illustrated by Figure l'.1.
The Connecticut Light and-Power Company (CL&P) and Western
! Massachusetts ElectriU Company,(WMECO) are the sole owners of-Millstone Units Number One and Two_with'81% and.19% ownership respectively. They are the principal owners in Millstone _ Unit Number Three with 65% ownership and, by contract have the authority to make all of the decisions affecting the design, procurement,
' construction and operation of that unit. This decision making authority would be similar for any future units. -
The NU Companies jointly own 44% of The Connecticut Yankee Atomic Power Company (CYAPCO). By contract, NU and _ Northeast Utilities :
Service Company (NUSCO) have been delegated operational control of CYAPCO. NUSCO provides technical support for the operation of that'
- plant. This is also illustrated in Figure 1.1.
Northeast Nuclear Energy Company (NNECO) and CYAPC0;are the-operating companies established to operate their respective
, facilities. NNECO is delegated the responsibility for operating the Millstone Units by the owners. NNECO in turn has contracted for the services of NUSCO for the design and construction. management- of all' of the units at Millstone and may solicit technical support'during' plant operations. NNECO and CYAPCO comprise the. Nuclear Plant-Operating Companies (NUPOC) as illustrated in Figure 1.1.
NUSCO, parts of which are organized as shown in Figures' 1.2, 1. 3,1 1.4 and 1.5 provides services such as engineering, quality assurance, accounting, planning and procurement:for the NU systeu operating companies where these services can be more efficiently and economically performed on a system-wide basis.
The NUPOC and NUSCO interrelationship shown in Figure'1.6, for quality related activities, indicates how conflicts are resolved.-
As indicated, the Senior Vice President-Nuclear: Engineering and Opeiations - NUSCO is also the Senior Vice President-Nuclear -
Engineering and Operations - NUPOC. He resolves disputes arising from a dif ference of opinion between Quality Assurance. personnel and s other department personnel.
1 1.2 CENERAL (Refer to Figure 1.2) 1.2.1 The President aj Chief Operating Of ficer of NU is also the President and Chief Operating Officer of NUSCO and directs specified nuclear related activities within NU' -
lie has the ultimate responsibility for the establishment" QAP 1.0
. Rev.: 7-o L'' t '
Date:f p ..
y y' ' **:
t
',n Q W wecv.g v u PWC/KMenver.$ R m M @ wugewm:Twmpyyi*#rres6
.p , ,
q
, J ?3^~~ ,
?,v2 - I l r
- > i ,
t _
. E . . . .. . .
('
r
'. uni fxci ut ion .ol Llu Nil Quality. Annurant e l' rop, ram .(NtHJAP) .
1 . Reporting to the President and Chief: Operating Officer.is
-the Executive Vice President-Engineering'and Operations,'
f.
the Senior Vice President-Administrative Services, and. the Vice President' .Information' Resources Grosp. Authority,
~
for,the establishment and execution of the NUQAP is delegated to the NUSCO Executive Vice- - _
[ ,
President-Engineering and Operations-(see Para.'1.2.3).
1.2.2 The NUSCO S'eniorz Vice! President-Administrative Services is.
responsible for procurement activities within NU. The.
System Director-Purchasing. and Materials Manaaement ];
reports to the Senior Vice President-Administrativei-
- - Services and is responsible to ensure that. procurement .-
- f. .
- requirements of the NUQAP are carried out within his-division (see Para. 1. 5.1) .-
The Vice President - Information Resources: Group ~1s:
I responsible for all'information storage, handling and" delivery systems at NU. The following Director s/-
Manager report to the ,Vicc President-Information -
Resources Group-t
- a. Director-Engineering Computer Systems and Technical Support (see paragraph 1.5.2.1).
- b. Director-Busine'ss Computer Applications and Data )
Center Operations (see paragraph 1'.5.2.2). ' I
- c. Director-Information Resources Administration (see.
paragraph 1.5.2.4), -
~'
- d. Manager-Information Resources PlanningLand Control (see paragraph 1.5.2.3).
! 1.2.3 The NUSCO Executive Vice President-Ensincerina and-Operations is also the Executive Vice>
President-Engineering and' Operations for NUPOC.- lie is responsible for engineering, ' construction, operation, maintenance, modification and-quality' assurance-within NU.
Specific. nuclear related responsibilities rest with the following individuais who -are responsible for ' ens.uring ...
that the requirements of the NUQAP!are carried out within-their respective groups. '
- a. Senior Vice President-Nuclear Engineering and: Opera-tions (see Para. 1.2.4).
- h. Vice President - Transmission and Distribution Engineering and.Operatio'ns=(see Para, 1.5.3)..
\ .
g 4 f QAP 1.0 1' -
Rev.: 7 Date:
Page 2 o f :16 '
A$9 0-M ,
4 ,
r .
, g -- ,
_ _ _ _ . _ . . - _ _ _ - . - - - - - - - -----------'--A------ ' - - - - - - - - - - - - - - ^ ^ ' ^ ^ ^ ^ ^ ^ ^ ^ ^ ' ^ " ' ^ ' ' ' ^ - ^ ~ ^ ~ ~ ^ ~ ~ ~ ^ ~ ~ ^ ~ ^ ^ ^ ~ ' ' ^ ^ ' ^ ^ ' ~ ~ ~ ~ ^ ' ^ ~ ~ ^ ^ ^ ' ^ ~ ~ ' ' ' ~ ~ ~
' ' ~ ^
N,Nen%;W Pew ms Wew ## nv . -. -e is mW=k O 4
L
,y t
A_,) > 1.2.4 The NUSCO Senior Vice President-Nuclear Engineering and - -
Operations is also the Senior-Vice President-Nuclear Engineering and Operations for NUPOC. He is responrible for nuclear engineering, construction, operation, mainte -
nance, modification and quality assurance.
1.2.4.1 The responsibilities _of the Senior Vice President - Nuclear Engineering and Operations relating to the _ Quality Assurance Program are described in the Nuclear Engineering and-Operations Policies and Procedures Manual. He has contact with quality assurance _ activities through the receipt of various documents such as: Weekly progress reports, Nuclear Review Board Meeting Notes and other reports, and audits related to NUP0C nuclear plant operations activities.
[ 1.2.4.2 The Senior Vice President-Nuclear Engineering and Operations is responsible to assess the scope, status, implementation and effectiveness -
l of the NUQAP. To meet this responsibility, he appoints a qualified team of individuals to perform an annual Management Quality Assurance Review,
- b(s,/ This Management Quality Assurance Review is
l
- a. A systematic evaluation;
- b. Preplanned toward_the objective of deter-mining the adequacy of the ffDQAP and its compliance with Appendix B t'o 10 CFR-Part 50 and other regulatory requirements; l c. Capable of identifying, communicating and I tracking any required corrective action.
The team is made up of_ individuals knowledgable in Quality Assurance, Quality Related Activities, Auditing, Management-Responsibilities, and the NUQAP Topical Report.
1.2.4.3 The following division Vice Presidents report to the Senior Vice- President-Nuclear Engineering l
and Operations:
- a. Vice President-Generation Engineering and Construction (see Para, 1.4.1) -
- b. Vice President-Nuclear and Environmental
'(j Engineering (see~ Para. 1.4.2)
LJ QAP 1.0
. Rev.: 7
! ? .,
l Date:/,',,'lf Page 3 o {6 i
e L. _
%@EiW RMk W MW'-&NMM MM% - Y W qr W M M
- N W W W P" s
- ^ i /,
Ip lg c. Vice President-Nuclear Operations (see.-
. Para. 1.4.3)
" 'l.3ORESPONSIBILITIES '(Refer'to Figure 1.6)'
l.3.1 Overall responsibility for the,NUQAP is assigned to'the NUSCO Manager-Quality Assurance who reports:to the Vice-President-Nuclear and Environmental Engineering through~
the Director-Nuclear; Engineering'and Operations Services'.
These responsibilities include: direction of~th'e Quality; Assurance program;-implementation of policies, plans,1 requirements, procedures, and audits;'verificatior.ito 4-assure compliance-with 10 CFR 50 Appendix B and other regulatory requirements; and. verification of the-implementation of the NUQAP Topical Report ~ requirements. ,
t Overall responsibility for the implementation of the-NUQAP.
- 1.3.2 .
] Topical Report at the NUr0C Nuclear Plant is, assigned to.a~ -
NUPOC Superintendent. -Each;NUPOC Quality Assuran,ce Super .
> 4 visor, reporting to.theloppropriate-NUPOC Superintendent, {
r is responsible for verifying implementation of the requirements of th'e NUQAP Topical Report.
1.3.3 The head of each NU department or organization performing
- quality related activities is responsible..for:
- a. Administering those, activities yithin;his organiza-j tion which are quality related as defined by- the NUQAP Topical Report; _i t
'# b. Ensuring implementation' of the Quality Assurance '
- v Program. ? ,
y ,.
- c. Establishingandclearly-dffiningthedutiesand. '
responsibilities of personnel within'his_ organization.- -
' # ~
i who perform. quality.related activities;.
f
. .- 1' t / d. Planning, selecting and training personne1Lto. meet -
l' the requirements 'of the NUQAP Topical' Report;- '
. s v'
- e. Performing and coordinating quality matters within. ,
,1
- j. his department and~ interfacing with NUSCO/NUPOC
~
Quality Assurance o'n; quality.related matters. :l 1 1 I 1.3.4 Each . individual, performing -or : verifyin'g ~ activities -
i
' ' H affecting quality, is. responsible to conduct those; . .
q l' activities . in accordance with. the requirements ; of: the : q NUQAP and implementing procedures. q r i l
1 1.3.5 - The_ responsibility,'. authority,~and organizational. ,
i relationship" for . performing qualityj related activities i
i' withineachorganizationis.~establishedand'dplineated:in :i
- - -QAP,1$0.
, .R$v.:$ 7 '
iDMAUG
-Page 4:of'16 0 9 E5 7
p
- ,s -
3 y- - _ _
n T g = N,_ ,;_ y m ; m .e ~ y;:5 0e . ~;gt n ? .g ;+.qiM..y .;vy +w.n:m _e a (r~')
t A/
m the NU OrganizationallCharts, jurisdictional statements, and written job or -functional descriptions.
1.4 NU PARTICIPATING CROUPS - NUSCO NUCI. EAR' ENGINEERING AND OPERATIONt GROUP
'The Senior Vice President-Nuclear Engineering'and Operations Group is responsible for providing. and directing ' projects and for providing technical and support personnel to meet responsibilities during engineering, construction, preoperational and startup.
testing, modification, and operation of nuclears power plants.
The Nuclear Engineering and Operations Group is divided into three divisions:
a) Generation Engineering and Construction (Figure 1.3);
b) Nuclear and Environmental Engineering (Figure 1.4); and c) Nuclear Operations-(Figure 1.5).
The functions of the personnel, who perform quality related activi-ties within these divisions, are as follows: -
1.4.1 The Vice President-Generation Engineering and Construction O'
is responsible for engineering, design,;and construction-activities for new NU generating facilities and modifica-tion, backfit, and betterment projects'for existing NU generating facilities. .The following~ department. heads report to him: (See Figure 1.3) 1.4.1.1 The Director-Generation Engineering and Design Department is responsible to provide technical and support personnel to-new' generation facility projects-directed by the Generation Construction.
Department or -the Project Manager - Millstone -
Unit 3 and to provide Project Engineers and support for betterment projects in existing generating facilities directed by.the Generatica Projects Department. Technical support'is-also provided for operations.and maintenance
- activities of the existing generating facilities. The Generation Engineering and Design Department provides expertise for
. systems, specifications and procurement ofe
- equipment and material;.it provides design expertise for the preparation and maintenance of -
design documents'for generating facilities.
These Generation Engineering and Design Department activities are performed by personn'el'
~
within the following department. branches:
s .
- - \s-) ~
QAP 1.0
- Rev.: 7- .
Date: };;[, C 7/ *: [
Page $ ofE16' mehr
W$21sl&@EMhWHR$M *M*T'T9FWP&' @:M Mhki Ti% <& }M % ~ ', 3 ~ *O '
m f,
- a. Mechanical Engineering;; ,
~
- b. Electrical: Engineering; ,
Civil Edgineering;
~ c.
- d. Engineering Design.~ .
{
l.4.1.2 The Director-Generation Cons'truction~ Department ' ,
is responsible for the following areas ~in new, ,
generation _ facility projects': . 1).the: direction ^
and. coordination of processes and-assurance.of. ~
necessary resources for; construction; and ,
- 2) coordination of startup. activities with '
NUPOC. For existing generation' facility , i betterment' projects; and when assigned,_ for new ~
generation projects; the ' department is < , < ,
responsible for providing construction management andl quality control' services. The?
department consists of: >
4
- a. New Site Construction to oversee lthe i
construction and quality related activities 1 of Engineering Constructors for new -
generation: facilities; .
' ~
- b. Betterment Construction to^ overs'ee the?
cons'truction and quality related activities of construction. contractors for betterment. .; j work on existing generation facilities.
- c. NUSCO Construction l Quality ~Controb to, l perform quality control functions onfitems affectingLquality,.such as ; inspection, .
receipt control coordination'among' ,
applicable NU: departments'and outside a
organization's (see1 Figure [1.6).
1.4.1.3 The Director-Generation Projects Department is:
responsible to provide project management and - -
- coordination .of proje' cts ~ involving existing; o generation facilities performed by NUSCO:for thea ,
l]
.NU operating: companies.' Thislactivity includes m :q but is not limited to projects'. involving :l betterment- and backfit. modifications made to - . , 1 s
existing generation-facilities. .The; _. ,
j coordinating. function-includes cost and schedule- j control.of projects land=outiageiplanning and; il scheduling forlthe-' operating companies.
Sections.:offthis' Department,-which perform
~
-quality related activities',iare: . ,j
. - ' '1
'QAP?T.0T. ,
'Rev;: 7. . ., g 4Date:AUG () Bile ;
- Page 6-.ofc16 .l m - , , . ,; . ~ ;,; 3 -;
- g ; ~
- p. -l
~
o
'-~c p age;c. w <,4,;'"'*'"?xcm;p ', n - -
x ,, .. .. . , '; , ;c-x c , em e" .q,e.mW 4
L, ,
~ N. - -. a. Generation Projects-Millstone Unit,Nd -I
~ b. Generat' ion ' Projects-Millstone Unit No. 2
-c. Generation Projects-Connecticut Yankee -
- d. Cost and Schedule Control.
1.4.1.4 The Project Manager-Millstone Unit 3 is responsible to. direct and/or coordinate'the processes and assure the necessary resources, construction management,. cost and schedule-control, and quality control'for the licensing, engineering, construction, testing and startup.
of the new nuclear generating facility.
1.4.2 The Vice President-Nuclear and Environmental Engineering is responsible for Nuclear Engineering and Operations. -
Services (including: Quality Assurance, Reliability:
Engineering, Generation Facilities-Records, Nuclear Materials and Chemistry, and Nuclear Safety Engineering); .
Environmental Programs; Nuclear, Engineering'(including: ..
Radiological Assessment, Reactor Engineering, Licensing,-
and Nuclear Fuel); and Nuclear Training' for new and -
existing nuclear generation facilities. .'The following ~
department Directors. report to the Vice President-Nuclear.
and Environmental Engineering 1(see Fi,*ure.1 6):
1.4.2.1 The Director-Nuclear Engineering y d, Operations Services is responsible.to direct and. coordinate ;
the support services as required .for :new: nuclear and betterment . projects and for NUSCO/NUPOC
- Departments during;the design, construction and operation of. nuclear power plants. cHe.has reporting to him the..following' managers / supervisors:
- a. -The NUSCO Manager, Quality; Assurance is responsible for'the preparationLand issuance of.the NUQAP Topical Report, and.
verification of the.--implementation of its requirements by' applicable =NUSCO/NUPOC.
Departments; Verification issperformeo by a planned program of audits inspectionsiand.
surveillances by the quality assurance:
sections'of design &' operations, procure-ment, and construction. :He-.provides s management with objective evidence.of" thel
- performance' of. activities affecting' ,
quality, independent"of the7 individual or. 'i group' directly responsible for; performing . '
the specific. activity. ,
-QAP 150
.Rev.: 7: .
Date:f,1 5 ,^;',. %
.Page 7 of 16 ~
__- - E An..
w;..-- a ,, . .- :;. - , ;2 .
~ mn;9n ,--, n .w g .a. w ..,r.y:. g m n n. w. - ,,
\ t.
-He has the authority and organizational ~
'~ '
, freedom to assure all necessary quality.
affecting activities are performed and-is independent of undue influences and respon--
sibilities for. schedules and costs. He has the responsiblity'and authority delineated in writing, to stop unsatisfactory ' work and control further processing, delivery, or installation of nonconforming materials.
He also has the responsibility and authority to identify quality problems, to provide solutions, and to verify their
-implementation. He maintains an overview of NUP0C quality 1 assurance' activities through a planned and systematic program of audits and surveillances.
The following ' supervisors and their staffs report to the NUSCO Manager, Quality Assurance (see Figure 1.6):
- 1. Supervisor, Design and Operations Quality Assurance.
- 2. Supervisor, Construction Quality 7-s,
- Assurance.
g
'-'} .
- 3. Supervisor, Procurement Quality Assurance.
The Supervisor, Design-and Operations.
Quality Assurance assures that Quality Assurance responsibilities;~as they relate to the. design, operational phases,-and betterment projects of nuclear power plants; are being implemented.
The Supervisor, Construction Quality Assurance assures that Quality Assurance responsibilities;Las they relate;to'onnite Construction and the preoperational phase of new Nuclear power plants; are being-implemented.
-The Supervisor, Procurement Quality Assu'rance assures that. Quality Assurance.
responsibilities, as they relate to' procurement activities. for the nuclear 1 power plants, are being' implemented.
These_ supervisors'have positions which are
~
[ T f ree f rom;non-Qudlity Assurancei duties and.
\m,/.
QAP 1'.0 Rev.: 7..
Datei AUG-0 0 =1985
=Page 8'of.16 H
n-
.n.qg q w .;:. p n g-3;p n g g; ;.y ; g ,y y s.; p e w. 3;y;.p g3(.wp.ga.pnw . ?
g_ ,7 can give full a'tt'ention to assure that thel ~
~d
~ Quality Ass >2rance Program is being-effectively-implemented and have~ . ,
appropriate organizationaltresponsibilities and authority to exercise proper control-
-over.the Quality Assurance Program. LThey.
~
s have'the responsibility and authorityito identify quality problems, to provide.
solutions, and to verify their implementation. Stoptwork orders initiated' by NUSCO Quality Assurance personnel:are s delineated in writing.with.the concurrence of a NUSCO Supervisor,- Quality Assurance.; "
' and approved by lthe NUSCO Manager, Quality.
Assurance. '
The responsibilities and -duties ofI all NUSCO Quality- Assurance - personnel' are. '
described in NUSCO implementing procedures end job descriptions.
- b. Manager,-Generation Facilities Records'is responsible t'o provide _ guidance by.the' establishment of a1 corporate Nuclear Plant
~ Records Program and Manual ~for the-O effective operation of all Northeast.
Utilities Nuclear' Plant RecordsLFacilities.
to meet corporate nuclear recorus.
objectives.
- c. ' Manager,;ReliabilityfEngineering is. ~
responsible-to assure that proper:
~
reliability 1evels are' included in.the design, construction and operationLof1 nuclearf generating facilities.
- d. Manager,1 Nuclear Materials:aad Chemistry is responsible ; to ' provide . evaluations : of .-
nuclear plant; coolant chemistry :and . ,
materials and.to Jimplement controls.in- .
accordance with'the Nuclear-Plant Water Chemistry Program.
- e. Manager, Nuclear _ Safety' Engineering is: .. I responsible;to ' provide nuclearJsafety
- d engineering evaluations :of operational .
experience at:NUfand. Industry Nuclear Power; 1 Plants.
1
.- 1.4.2.2- The Director-Environmental-Programs _is respon . /l sible for-the planning, design, coordination:and supervision of all: scientific engineering ' u' ,
QAP_1.0)
J Rev. r: 7J 1--
- Date-[,yG?$y',J]';;,
Page 9;ofl16 _ 21 , ~
l
,_,: -.-_.g. , , ._--.4 .._....,mL , , , ..,;. - 4.-..,,, -.
...-w e ~ re- 4 # - + ~ - +.'
~ '
~-r;.?y % g W ..v W V ' W ~O W a M :w:Ye@%WF9W&
n.~. :yn;;a T.=
T studies of problems related to environmental impacts of NU activitieszaf f ecting proposed and '
operating' generation' facilities. He has; reporting;to him, the-following' Managers /
Supervisors:
- a. Manager, Earth Sciences is responsible'for the preparation of atmospheric dispersion calculations required to estimate-dose to the public from.both routine releases and postulated accidents. He provides criteria and studies to assure that such calculations reflect state-of-the-art-techniques and adequately support the corporate program for Nuclear Emergency .
Preparedness,
- b. Supervisor, EcologicalIAssessments provides. .
statistical support to the NU Environmental Lab to ensure state-of-the-art' statistical methods and techniques lin all areas of'the ,
ecological monitoring programs.
- c. Manager, NU Environmental Laboratory directs ecological impact assessment.
i studies:for the operating generation. .
ON - facilities.
1.4.2.3 The Director-Nuc'_ ear Engineering :is responsible to direct and coordinate the: activities of.
Radiological Assessment, Generation Facilitie's Licensing, Reactor Engineering and. Nuclear Fuel.
The following' managers report to Director-Nuclear Engineering:
a .' The Ma' nager-Radiological Assessment is:
responsible to provide technical services
- in radiological matters relating to nuclear.
plant design and operation in new nuclear and betterment projects. It. includes the studies of radiation ' exposure to plant 'per-sonnel and the general public, . liaison with --
regulatory-agencies, and responsibility for the corporate program for Nuclear Emergency Preparedness.
- b. The Manager-Generation Facilities / Licensing is . responsible for corporate liaison with' the Nuclear Regulatory; Commission.and coordination of responses to regulatory;. . I requirements for .new nuclear projects and c{
changes to operating facilities. .This;
{/
N_
} 1
-' QAP 1.0'
- Rev.: 7
'Date: AUG 0 9 BS3 u
~Page.10 oft 16~ ,
l
w:; m . r . . . - . . . . . s_c w ,, .. .,v.w.y. .-- . , ,:
E.
includes the preparation and coordination of documents for submittal to various regulatory agencies.
- c. The System Manager-Reactor Engineering is responsible to provide reactor engineering, NSSS safety analysis, probabilistic risk assessments, fuel design, and reactor core analysis and performance evaluation services for new nuclear projects, betterment projects, and operations of nuclear generation facilities. This includes services during reload of nuclear reactor cores, direction for optimal operations of reactor cores, evaluation of design and analysis of reactors, and NSSS transient evaluations.
- d. The Manag~er-Nuclear Fuel is responsible for the planning, scheduling and coordination of the nuclear fuel supply requirements for proposed and operating nuclear generation facilities. This includes contract engineering for technical administration of fuel contracts and technical support for the procurement of all elements of the O. nuclear fuel cycle, the handling of fuel removed from operating facilities, and j determination of nuclear fuel costs.
1.4.2.4 The Director-Nuclear Training is responsible for all Nuclear Training and Training Evaluation activities. The Department consists of the Connecticut Yankee, Millstone, and the Berlin Nuclear Training Organizations.
1.4.3 The Vice President-Nuclear Operations is responsible for plant modifications, refueling, maintenance and operation of operating nuclear generation facilities; and for controlling and directing the preoperational and startup test program for new nurlear projects. The division consists of a Nuclear Operations Engineering staf f and the NUPOC organizations (see Figure 1.5).
1.4.3.1 The Supervisor - Nuclear Operations is responsible for the coordination of activities between the NUSCO Engineering personnel and the NUPOC personnel. An engineer is assigned to each NUPOC operating nuclear generating facility to perform the coordination of the activities.
QAP 1.0 Rev.: 7 s
Date:9,,
Page ~'1 1 of 16
KG%:%%{5977;$CMR.5";?!{lk&K M& P% ' + %?M6? : W;%& ~JA W - n " BWh*
, ,-~~
m, I 1.4.3.2 . NUPOC - Station . Superintendents (Millstone and Connecticut Yankee,) .are responsible Lfor :the -
=
operation, maintenancei plant modifications, refueling and services of operating nuclear-generation facilities and controlling and:
directing the lpreoperational and startup test.
programs l for new nuclear projects. They provide:
operational input to the-Project ' Engineers for the design.of3new-nuclear and operating' plant-betterment projects.
- a. NUP0C. Station Services Superintendents (Millstone and Connecticut Yankee) report
~
to the:1ndividual Station Superintendents ~
and are responsible for the service depart-
~
ments of each' station such as Security, Health Physics, Chemistry, Stores,. Nuclear Records and Quality Assurance (see Figure 1.6).
- b. At the Millstone Station only, the Quality Services Supervisor reports to the Station Services Superintendent'and has responsibility _ for the areas of Stores, Records, and Quality Assurance (see.
'} Figure 1.6). -
J .
- c. The Millstone' Quality Assurance Supervisor.
reports to th'e Quality Services Supervisor..
The Connecticut Yankee Quality Assurance Supervisor reports to the_CY Station Services Superintendent (see Figure 1.6).
The Quality AssurancefSupervisors.are responsible for the verification'of the implementation of'the NUQAP requirements in n eration facilities.
the operating . nuclear ge' y and in new nuclear projects commencing _at system turnover. sThey provide nuclear-generation facility management and the NUSCO Manager, Quality Assurance with -
objective evidence of the implementation of the Quality Assurance Program within the-facility. Their duties-and organizational positions are' described in NUPOC-Procedures. -
They.have the authority, organizational -.
freedom, and are sufficiently removed from , <
undue cost'and schedule influences to perform quality assurance functions ef fec- ;
s tively including responsibilities to:
. %/
QAP 1.0 Rev.: 7 .. -
lDate: AUG 0913B5
'Page 12 of116
q&S?q:7ay:' , y x , j:5Ay;, c , % ;5 nW =
n.g.97Mgmwm , ~* w -
.o e
I~k .
.1\m ,/. (1) . Stop unsatisfactory work and control.
, further. pro 'essing, delivery or installation of nonconforming materials as delineated in writing;.
(2) Identify quality: problems; j (3) Initiate, recommend or provide solutions; and; (4) . - Verify -implementation of solu'. ions'.
The Millstone and Connecticut- ankee Quality Assurance organizations routinely attend and participate in daily plant work' schedules and status meetings to assure ~
they Lare kept' aware of day-to-day work assignments throughout the plant. 'This also assures that there is adequate Quality.
i Assurance coverage relative - to procedural, and inspection control, acceptance, criteria, and Quality Assurance stiffing and qualification of personnel to carry out Quality Assurance assignments for safety related activities.
4
[);
V 1.5 OTHER NU PAPTICIPATING GROUPS 1.5.1 ADMINISTRATIVE SERVICES The System Director-Purchasing and Materials Management ~ is? .l
- responsible to the Senior
- Vice President-Administrative Services for procurement activities within NU. Reporting to the System Dirc: tor-Purchasing and Materials'
[
+
Management, are several Purchasing Directors and Managers-responsible for:
- a. The procurement of materials and services from-qualified ' suppliers in accordance with predetermined commercial, technical, and quality requirements;
- b. Issuing Purchase Orders / Contracts 1and changes thereto;
- c. Maintaining traceability. of purchasing: records' from NUSCO/NUPOC;
- d. Processing of purchase requistions -'through to -j
~
preparation for payment for'the purchased item. ~
~ ~
The' System Director-Purchasing and Materials Management controls quality related purchasing' procedures.
]. ,
f'"% l
^%.sY l
~QAP 1.0 l Rev.: 7 '
1 Date:Pjf C It .. ,$3 Page z l3 of 16 "' -
W 'v-k- -
1,i77.gqX:%f vwS W:.YM % ?'AV , { .W : "=~ '
- *~ r >
i s
(_,) ~ 1.5.2 INFORMATION RESOURCES GROUP (See Figure'l.7)
The Vice' President - Information Resources Group is :
responsible for_ all information storage, handling anu-delivery systems at NU.
. 1.5.2.1 -The Director - Engineering Computer Systems and Technical Support is responsible for:
- a. The design,' coding and implementation of coe.puter. systems in support of engineering and scientific' functions at NU.
- b. 'The initiali supply, - life-cycle; support' and !
replacement fof NU process computer systems including the . nuclear plant computers and various special purpose systems.
- c. Mainframe Computer! System technical support, which includes all associated
~ ~
teleprocessing and distributed processing.
aetworks.
1.5.2.2 The Director - Business Computer Applications .
and Data Cen*.er Operations is responsible-for:
{s 's,,) a.
~
The design, coding and implementation of all_ compu .er systems in support of business.
related ftnctions at NU.
~
- b. The operat.on of all NU Data Centers.
1.5.2.3 The Manager -'Information Resources Planning and .
Control is responsible for:
- a. Evaluating.new and.emergingitechnologies to determine their'. applicability to NU and their. impact on strategic directions.
- b. Coordinating all<Information Resources-Group Software Quality Engineering activities including:
- 1. Development of software engineering standards; detailing policies _and '
procedures. governing the developmen; of: computer sof tware.
- 2. Identifying _ minimum documentation
~
levels for. all sof tware . requirements.
. specifications, design-descriptions,_
.d .QAP 1.0
~Rev.: .7~
Date:AljG Q 9_l?.35_ ~
"Page 14'of 16
- - . . _ _d
'sQvR+pF;:%='QW kG - = Foc , 1:
w&T
.W-+a "A D y .'@ V ' ?; : :
J
~
p);
\.,, '
verification ~ plans' and verification reports.
i
- 3. Development of computer based systems. a for automated auditability and traceability, including source code libraries,' object ' code libraries and' executable load modules.
- 4. ~ Application Jand review of. software products which_ ensure traceability and auditability of quality-related computer programs.
- 5. Development ofJsoftware system' test
- j. plans.
i 6. ' Development of training and-
. indoctrination programs in sof tware-engineering.
4
- 7. Monitoring compliance with all.
j Information Resources Group Software .
j Engineering standards.
1
("'A 8. Identifying deficiencies with existing l \_,) Information' Resources Group policies l and standards relative to,this NUQAP topical. report.
i 1.5.2.4 The Director-Information Resources Administration is' responsible for: -
- a. Ensuring that data retention and ownership requirements are;followed.
J b. Ensuring data integrity.
- c. Setting policy forc_ data standardization.
- d. Overseeing the design, construction,. tuning l and recoverability'proce'ss of physical data bases as part iof application 'dsvelopment.
1
~
- e. Administration 'of the Information Resources .
- Disaster RecoverycPrograms.
l Administration of the Information Resources f.
, Information Asset Security Progra.ms.
hv
- QAP :1.0 ;
Rev.: 7
- ~
Date: , ' , ' . l *f ' '. . "
i 'Page 15.of 16'^
a____---__--_ - - . _ _ _ - - . - - - - - - - - - . - _ _ . - _ . - _ - - - _ - - - - - . _ - - - - . - - - - . - - - L
- ,=.rm .
, . .g w. ,
- / ;
, ;1:.. ,s vn,w r:- n q1.w.m.mwz;=v;p::.w:;..;:: m: A
- f 3 h_,[ -
- g. Maintaining awareness and' understand'ng i of legislation and regulations pertaining to data security concerns.
1.5.3 SYSTEM TRANSMISSION AND DISTRIBUTION The Vice President - Transmissio'n and Distribution Engineering and Operations is responsible for quality related activities performed -by groups within his organization. The System Superintendent-Transmission and Test reports to the Vice President-Transmission and Distribution Engineering and Operations and is also respon'sible for quality related activities. _The:
Superintendent-Production Test reports to the System Superintendent-Transmission and Test-and is responsible for quality related production test activities which include:
- a. Providing electrical' testing'servicesato the Nuclear Plant Operating Companies (NUPOC).
- b. Planning and coordinating periodic and corrective maintenance of electrical equipment.
- c. Conducting acceptance tests, calibrations,
'N adjustments, functional checkout and commissioning of sm, electrical systems.
- d. Overseeing electrical'preoperational testing for new nuclear generation facilities projects and'startup testing for backfit/ betterment projects, as requested.
l-QAP'1.0. .
Rev.: 7 Date:
- Page 16 of 16'
O O O .
iv NORTHEAST UTILITIES ORGANIZATION Direct Control Operational Conirol - - - - - - - ---
NORTHEAST '$
UTILITIES [
1 ,
NORTHEAST UTILITIES : '
SERVICE COMPANY ,
(NUSCO)
J
_______________q g l
1 CONNECTICUT WESTERN HOLYOKE NORTHEAST CONNECTICUT MASSACHUSETTS WATER NUCLEAR "
LIGHT & POWER YANKEE ELECTRIC POWER ENERGY ATOMIC POWER COMPANY COMPANY COMPANY COMPANY . COMPANY .,
3 THE NUCLEAR PLANT OPERATING '
COMPANIES (NUPOC)
FIOURE 1.1 O AP 1.0 w7 ,.
. "AUG 0 91985 f
~4
______ _____ __ __ __ _ __ _ . _. _ _ _ _ _ _ _ . _ _ _ ._ _ _ _ _ _ _______._____._______1
) i a . O *:
ll
.O s '.
NORTHEAST UTILITIES
[
Organizational Relationships is.
of Personnelhaving Quality President & Chiet Related Functions o erating Officer i JQ
- 3. -
(NUSCO & NUPOC) 9 s
I i
i i i
Executive Vice President. Vice President- 4 information Resources S Senior Vice President- Engineering & Operations Group Administratsve (NUSCO & NUPOC) t ,
Services I _
l N See Figure 1.7 1 I ,
Vice President- Senior Vice President.
System Director. Transmission & Nuclear Engineering ,
Purchasing & Distnbution & Operations ,.
Engineenng Y Matenals Management (NUSCO & NUPOC)
& Operations [. .
b l l i[
s Vice President. Vice President. .
System Superintendent- Vice President- <
c .' . uon
- Engineering Nuclear & Environmental Transmission & Test & Construction Engineenng Nuclear Operations 4
1 -1 I l See Figure 1.3 See Figure 1.4 See Figure 1.5 >
Superintendent.
Production Test OAP - 1.0 Rev 7 1 Date e . . , ..s-- -
1 : , .
- L. .J . JJ FIGURE 1.2 s
.3-
'N r'N
- A 1
) \ \
a G J f NOffTHEAST UTILITIES Organizational Relationships of Personnel having Quality i Related Functions From Figure 1.2 q
+.,
Vice President- , ji II Generation Engineering
& Construction p
, 'j .
l 1
Director-Director- Director-Generation Project Manager- .j Generation Generation Minstone Unit 3 Projects Construction Engineenng
& Design ,,
C Generation Generation Projects New Site
- "" ##' Construction d Millstone Unit 1 ,4 Engineering J
n Generation Generation Projects Betterment Electrical Millstone Unit 2 Construction h Engineering j {
I 4
Generation Generation Projects Construction !
Civil Connecticut Yankee Quality Control r Engineering i 6t Ger'eration Cost & 'l Engineering Schedule Control Design FIGURE 1.3 OAP10 Rev; 7 '
m_ _ _ __.__. _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
Date:
' m :
L
.J
- p l^b
}
e
^
From Figure 12
- NORTHEAST UTILITIES OrganszarsonalRelatoonships of Personnelnaving QualstY voce Presscene-Nuclear A f
'Q Related funCloons Enverontnentat %
Eng.neereng , ' 'j l lfs g
i i i I
. D. rector-Direcio,. Detecto
Enveronmentag Nuclear Engeneering & -
Director '
- Nucsyar Traaning Nucteer Eng+neermg Progsams Operates Services
.?.
.W
.F.
9,i
- Nuceear Tra.n.ng -
Reecas ,
. (Sethn6 Earth Sciences - Quahty Assurance . - _ j Assessments .
' .k, h%
b NucHrar Tra.n.ng Ecologeat ija Rehabehty . Generasson Faciht es-Connectecut Yankee) -
Assessment Engineenne Lcenseng Q r<
r Tk
.,'i,
- ~
.ns >
y , o os "N <
j,
\' ;.
_ Nuclear Safety ~
Nuclear Fuel Engmeermg s.
, < y f '
sce.ar uaier.ais t and Chemistry 'N OAP 10- ' 'E Rev.. 7
' ,. cure i . -
one. p 3 j g g q
9i e
fl s
O O O y I
j NORTHEAST UTILITIES Organizational Relationships p7a m pl9u7e 3,2 {g of Personnel having Quality y Related Functions Vice President Nuclear Operations
/
'I; Station Supervisor-Station Superintendent Nuclear Superintendent Operations Millstone Connecticut Yankee a
- .1 Figure 1.5 ,,
OAP 1.0 0 Rev 7 Date p,;g c ,
.\
p -
l t t
\_Y \ <
s-
,h a
ca s
P NOftTHEAST UTILITIES Organizational Relationship Bet *een Sensor Vece Pressdent.
Nuclear Engineering l NUSCO & NUPOC Personn H Haven 0 ~____- Nuclear Review Boards Quately Related Functions & Operahons (NUSCO & NUPOC)
N I
I vece President- Y e
v.s. e e-vece Presedent- rahon Engemnng 3 e es. a Nuclear C,;.sations & Construchon a- sas.r e t'
I I -i 1 ,
- 5'* *
- D'=se'- I sies.ea Derector - Nucleas - Pim s,se, U****"* "'*' G*a*'***" '$~
Engineering & Co*'.**'**"'
no
-- sweem ---------- "--
ernmeae massoas und 3 coneu.seien ~
cv ceaus ".ee Opershons Serveces ce,,,,,seee j
n I , :
seemea
- N"'
- une una una session '.
ser.as ***** .. -_ _ n _: ,. _
p so,e, go,e,see
)-
, . I semesoao 2 ss.nason 3
~
g umeeene e g
.- e. : i e
S e
=
- Pieae ! M __ __ _ _
0.enev 5*' ~e -
ase e te oee e eae . i ese- s.e ',
uana9er- ___________ ___
ne*** ----- ----' l ***"' cease'use ea y Qualens Assurance \, 5=e***'e**-
C1 Ceauaeesee l l y
- g tuaesene h I
\
\
- syneen l 0.ener .,
I l \g . ,,, g
- '*"88 ope,ee.ean l /** -
s ,e., s., ew.
%. =--==---==-----J ""*** *****"'
oee a P ese cease co.en %' ne**= / " '*"*""'*** ,,
j Oswe eason om on \ Ce*=.sies i
% ene.***eae h ,#
g s________________.________________s____, .
l %
assasee .
l I I *g 7
._, ceas==chen
. ne a. *
- esmeieae 3 -
cemeneas Ceneu cmea N___. Omv Cones .
Os*ea ceaan.se 04 04 om on
- and. cases On Sao Organ sahonas Elements under the Ovat.sy Ass mance Psogram f.
tene Report.n3 .
Comun cationsd Adessory Reportang F8GURE t 6 OAP10 nee 7 Date AUG 0 91985 ,
/ n i ( )
%, %j i
$6 4 N
';v
. {.1 Y
T b
mee NORTHEAST UTILITIES '
Organizational Relationships -
of PersonnelHaving Quality Related Functions From Figure 1.2 -
Vice President-Information Resources Group
..t s
Director - Engineering Director - Business .,
Director - Information Manager - Information Computer Systems and Computer Applications and Resources Administration Resources Planning Technical Support Data Center Operations and Control 5
? Figure 1.7 OAP-1.0 Rev. 7 Date 7 _ .
C __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
m-
~
w .w ,, w :n.n, m , m a- ~+ - -
m ,w -
= - '
. +
l ' '
?j 5 L
_l
.; + , . ,
N !'
.2.0 QUALITY ASSURANCE PROGRAM- -
2~. 1 IGENERAL' REQUIREMENTS 4 NortheastaUtilities-(NU) has.establishedLa' Quality Assurance ProgramL ,
(NUQAP) which complies lwith the criteria of.10 CFR.50,-Appendix-B,- ,
and follows the guidance referred to in Appendix D ofLthis: report.
The quality assurance; requirements set forth herein and-the attached Policy Statement,; supplemented by the Quality Assurance Procedures, provide the primary basis of the Program and the'NU PolicyJwith ..
regard to quality assurance. This Program is established for each ;
plant. site in 'a manner intended to accomplish the required. level of '
quality and .is carried -out throughout the life of nuclear _ power; plants. ' This includes quality related activities initiated prior to t i
! submittal of the Preliminary Safety-Analysis Report (PSAR),Jsuch as design and procurement, preparation of the PSAR, and_ safety related ~
site preparation construction' activities, it alsol includes quality ,
related activ. ties during the operation,5 maintenance and modifica-
~
tion of the in-service nuclear power plants.
The requirements of the NUQAP apply, as a minimum, to nuclear safety .
related systems, structures and components-as functionally,' identified in Appendix A, " Category I Systems, Structures-and Components",:and other items or services which are specifically identified'in each- >
FSAR/FDSA addressing Section 3.2.l'of-NRC. Regulatory Guide 1.70c
-l The requirements of the Program are. implemented;by' Northeast Utili-ties. Service Company-(NUSCO), Nuclear Plant Operating Companies ,
(NUPOC), the engineer-constructor, contractors, suppliers 1 and engineering service organizations; performing activities affect- i ing the quality of safety related systems, structures and components of nuclear power plants.
I Procedures define the~ required indoctrination'and training of:
personnel-performing activities 'af fecting quality, as necessary,- to assure that suitable proficiency is. achieved and maintained.
Training sessions are documented, the content described, who attended,' j when they attended and the results of.the tiraining sessions. j A periodic program review of. the. status and adequacy; of the:NUQAP '
- [
is accomplished by NUSCO Quality Assuracce audits,..by Nuclear ~
Review Board (NRB) Reviews, 'and 'by the independent audit: team J
described herein and'in-QAP 1.0, Section l.2.4.2. ;0rganizations; . -
l outside-NU are required to review the status and adequacy of that.
~
part of the Quality Assurance Program for which they.-have designated t responsibility. .
{
n 5 q
\
QAP 2.0: i Rev.: 7 '
Date: AUG 0 91985
-Page~1 of 17;
. ,s .
_j' *
.c - _
m- c.,m , . . -
. . _ , .m,.- .m 2.2 IMPLEMENTATION
' N) \~-
2.2.1 Goals and Objectives As stated in the Policy Statement of NU, the goals of.the'
.NUQAP are to maintain-quality. levels in an effective and:
efficient manner and to assure a high degree of functional.
integrity and reliability of nsclear safety related systems, structures and components. To meet this; goal, the following objectives.of the NUQAP have been defined:
- a. Define through documented _ procedures , the' quality activities that apply to the design, fabrication, procurement, construction, test'ing, operation, refueling, maintenance, repair and modification of nuclear power plants;
- b. Establish, assign.and document the responsibilities for the conduct-of those activities affecting quality of the safety related systems, structures and compo--
nents;-
- c. Establish confidence that (a) the design', fabrication, construction and operation of nuclear power generation facilities are performed in a manner consistent with NU Policies and (b) quality related activities are performed by responsible personnel, through a system
[/)
s of audits of those organizations with quality related responsibilities;
- d. Appraise the. Senior Vice President, Nuclear Engineering and Operations of quality related unresolved, problems and trends which could have.a significant effect on-nuclear power plant safety and;
- e. Prevent schedule delays and high cost due to poor quality.
2.2.2 Program Documentation
~
This NUQAP Topical Report defines the NU nuclear policies,.
goals and objectives, and is used as guidance for the.
development of'the various implementing divisional, .
departmental, branch, or section procedures. Revisions.to the NUQAP Topical Report will be.made as needed to reflect. ,
current requirements and descriptions of activities prior to' implementation. These revisions.will be made in accordance with a Nuclear Engineering and Operations Group Procedure.
pr~ l 5
l
\% /- -QAP 2.0:
Rev.: 7 Date:AUGt'C E;3-Page 2 of 7 q
. - - - - _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ - _ - _ - _ - _ _ _ _ _ - - _ _ - - _ - _ . .-. - - _ _ _ _ _ _ +_ _ _ _ _ - _ _ _ _ - . . _ - - . _ _ _ _ _ - _ -
, x ym anc. +~n e:~=mW -
x.w., v ~ - . . , ~ - - - - - + - mm =- ~- m-t t- t
, s %
W I
. <01 '
'. Y
- ~~ / Revisions to.the NUQAP Topical, Report,.'which reduce commit .
ments previously (accepted byithe ,NHC[ a re submitted , to; the '
NRC' for review .and approval prior , to Limplementation. ~
Revisions ~which .do . not -. reduce previously accepted ' con.altments are. periodically submitted 1to the NRC as required.by',
10CFR50.54(a)(3)-and 10CFR50.55(f)(3).
o Quality procedures are developed lar =the-departments performing quality related activities.
~ '
These procedures are reviewed;by.the'departmentsLwhich are responsible for portions of these procedures. .Theser.,
procedures are. approved by therdepar,tments'which initiate-these procedures andLare reviewed;and. concurred with-by #
the applicable NUSC0/NUPOC QualityfAssuranceL0rganization7 for' compliance with the NUQAP. Topical Report. Changes to procedures are. subjected to the same degree of control'as that utilized in: the; preparation of the original document.
Each NUSCO Department Head /NUPOC Superintendent is responsible' for implementation of the NUQAP, which includds-individual. ,
' departmental procedure requirements 1 applicable'only.to:his-respective activities. In addition,.he:is responsible for-the preparation, approval and distribution.of those .
instructions,. operating procedures, testing procedures or other instructions where further guidancelis-necessary.
2.2.3 Systems, Structures-and Components The requirements of the NUQAP Topical. Report shall apply,' l as a minimum, to nuclearcsafety ;related syt.tems , , structures . .
and components, as addressedxin ~ the Safety; Analysis .
~j Reports (SAR). Safety related systems, structures = and -- t components are functionally-identified-inzAppendix A of . !
the NUQAP Topical Report and also.as specifically identi- !
fied in each FSAR/FDSA addressing Sectionl3.2.1 of NRC.
For systems,. components, Land structures; covered by the . ' .!
ASME Code,Section III; NUSCO/NUPOC: Procedures describe the -i measures taken to' assure that ithe Quality; Assurance !
requirements, contained In' the code,': are . supplemented ;by : 0 the specific guidance of the applicable regulatory. guides listed in Appendix D of this' Topical Report.'
z The: degree of control;over activities affecting:the" {j quality of' safety related systems, structures and compon. ,' H
-ents is consistent with their:importance to_ safety. Such. ]
controls include'use of, appropriate equipment,. establish--
c ment of : suitable. environmental conditions and -assurance i that all prerequisites for a given ~ activity (have. been, l
.I
/ H QAP'2.0i s
?Rev.: 7J
-SDate:f'.'l 1 .. __ _ ,
' PageL 3 of 7 ~
m s -(.
s #
v-
' ' ' ' ' ' '^' ' ' ! '*
_g_.,._ s- - , . %. -
.-3 - . . - . - - - - - . ,-
~
i- satisfied. This~NUQAP Topical Report _provides for. controls,
!- \s / over special processes and skills.necessary to attain the
~
required quality, and the need for verification of iguality by inspection and test.
NUSCO/NUPOC Quality Assurance organizations. and applicable NUSCO/NUP0C technical organizations jointly determine and
- identify the extent Quality Assurance controls are to be.
applied to safety-related structures, systems, and components.-
designated as Category I in Appendix A and in implementing NUSCO/NUPOC Procedures. The Quality Assurance controls-are in conformance with this NUQAP Topical. Report, which complies with the-18 criteria set fo,rth in Appendix B to 10CFR:Part 50.
I 2.2.4 Participating Organizations The NU organizations with responsibilities for activities affecting quality of nuclear safety related systems, structures and components are identified in QAP 1.0, which-also briefly describes their assigned responsibilities.
NUSCO Quality Assurance is responsible for: a) the development, coordination, and control of the NUQAP including coordination of NUSCO Quality Assurance Branch Procedure review and approval; b) control and issuance of.
j the NUQAP Topical Report as a controlled document (as.
' described in QAP 6.0) and; c)' review and concurrence with quality related procedures and revisions written by other1 g departments. Procedure reviews will be performed in-accordance with QAP 5.0.
I
- NU shall require that their Engineer-Constructor, Nuclear-L Steam Supply System.(NSSS), Suppliers, Engineering ~ Service Organizations and contractors shall invoke upon their-l subcontractors,-via procurement documents,, requirements l for a quality assurance program to meet the applicable criteria of Appendix B .to .10 CFR,' Part 50, including the applicable elements of the Regulatory Guides and their.
endorsed Standards identified in' Appendix D of the Topical
- Report. However, NU retains overall responsibility.for
! the QA Program. The specific quality related activities performed by these organizations are specified in the procurement documents. NUSCO Quality Assurance reviews and approves these organization's quality assurance programs prior to initiation of contracted activities, and audits subsequent activities for compliance to their procedures.
i N
l
- QAP 2.0 Rev.: 7
! Date:
Page-4 of'7 l
--. ,. g ~. .
, c -
- ,: _ . ..-- w ; -. -
.-.x -
.i - The object of.-the review is to verify that.the engineer-- >
- \m/ : constructor, contractors , suppliers and . engineering .
service organizations have an adequate quality assurance program to meet the applicable _ requirements of. Append'x B to 10 CFR, Part 50' .,
o In addition to the initial review, the. engineer-construc-tor, contractors,Lsuppliers and. engineering service- '
organizations quality assurance programs shall be periodi :
l cal.ly audited by NUSCO/NUPOC Quality Assurance;to assure -
continued implementation of quality requirements.
Af ter system construction' by the engineer-constructor. and .
system. turnover to NUPOC, the program will fall under the.
l requirements of the NUQAP. A formal' test program is.
! prepared to provide' assurance that all systems andfequipment
! function in accordanceiwith design specifications.
i i
The formal test program is described in a'startup test manual which describes the-administrative organization and "
procedure which will be followed,~during;the: phaseout of
- design and construction, preoperational testing:and plant turnover. It demonstrates' control of quality related l
activities including management and technical interfaces among the engineer. constructor, NSSS Supplier, NUSCO, and NUPOC.
. During operation, contractors may be delegated the execu-tion of quality assurance functions by contract. These contracts are reviewed and approved in accordance with NU.
QAP requirements.
'l I
2.2.5 Indoctrination and Training' ,
I l
A program is established and maintained for Jquality -
! assurance indoctrination and training.which provides confidence that the required level of. personnel competence and skill is achieved and. maintained in the. performance of; quality related activities. Quality procedures. delineate the requirements for an indoctrination ' program. to assure that personnel responsible for performing quality activi-~
ties are instructed:in the purpose, scope and implementa .
Lion of quality related procedures and' instructions and ,
that compliance to these documents is mandatory. The NUSCO Manager, Quality Assurance is responsible for'thef ,
. indoctrination of personnel within' his department who perform quality related activities.
(
Nuclear training programs shall be developed and H implemented to provide training for all individuals attached to or associated with NU nuclear facilities.
73
\_,) .QAP 2.0 Rev.t- 7-Date:. AUG 0 0.1995
.Page 5 of.7 i -
E -
- O
wm,y -
, _ . - . , _ -- g _- .
m a-.
~ '
a ..
. . ' 1 >
9 7:
2.m "'
, - u ,-. ,
4 q '.
- w y
j t{
~ Additional .gui' dance 'is established .in NUSCO/NUPOC ;
. - Procedures. ,,
Implementing NUSC0/NUPOC_ Procedures describe the.nucl' ard training program requirements.which as's'ure that:
~
~
Documentation of formal training and qualification]
[ a.
[ _
programs-includes the' objective,:c'ntent o of the- ,j program, attendees, and. date of. attendance;.
I b' . Proficiency, of personnel performing'and; verifying' ,
, activities affecting quality,-is establishedLand j; . maintained. Personnel proficiency,is~ established. s and maintained by training,;exa'minatioc/ testing (: ,
and/or certification based upon the requirements of~
~
I ~
[ the activity. . Acceptance criteria are_ developed to: .
[ determine if~ individuals are properly trained and' !
,i qualified. ;
4 j c. Certificates or other documentation.of qualification-clearly delineate the specific functions personneli .;
F are qualified to perform and the criteria used to: ;
- qualify personnel in~each function, j t
f This program also requires.the head'of;each department" s j (including NUSCO/NUPOC Quality Assurance) to be. responsible j for a training plan which assures that'-personnel perform-'. 7
, ing quality related activities are trained in the principles: ,
and techniques of the activity being performed. ,
2.2.6 Management Participation
.~ > y, , .
NUSCO Department Heads /NUPOC Superintendents.are responsi--
ble for implementing the NUQAP Topical Report within theirt
~
g Departments / Plants.- The'NUSCO Manager,: Quality Assurance 1 j j' will assist in development,: coordination and review of the Program. -
l-
- 1 1 .. . .
s A management review of the' Program'is conducted:on'an i t ml h annual basis, by an independent' audit' group yto assess the~ ~
j scope, status, implementation,Jeffectiveness and-to assure l- compliance to NRC licensing commitments. TheiManagement'
- Review Committee'is appointed byjthe NUSCO' Senior?Vice-President - Nuclear Engineering and Operations.-- ;Hei 'i
~
l- ensures that deficiencies are tracked'and resolved,?and >= , ,
{ advises ~ upper management of the results of the, audits'. -
t
~
' Actions considered by the Management Review Commik. tee.may)'
j; include, but are not'. limited,to, the:following: 1 ,
e j: a .. Review of selected procedures andidocuments,_ '
t
[ b. Verification' of thef impleme'ntation of) selected !
y ~$
7 procedural, requirements .
., _[ g
]' QAP 2.0 ,
V -
Rev.: 7: -: -
L.,
~
[ 1Date:f"* 5: , ,
f- ..
Pagel6 of 7'.
)- ' '
w -
~ ,p '
J -
l 4N- s . . .. .
, - . . ..I _ ,_
.r
,._y __ ___3
m w.,. .-u. ; - ~. ,. . . . , - - - ;:: - -. - ,-- ,, --: m=m an.u-
,~ - - -
+
- c. Review of past audit results such'as-those conducied' g, .by: previous Management Review Committees, the NRC; 'or. -
other departments.
The-Review Committee's-findings of deficiencies and recommendations for program improvement are forwarded to the-NUSCO Senior Vice President -l Nuclear Engineering and Operations, who will ensure: appropriate corrective action is taken.
The quality assurance programs of the engineer-constructor, NUSCO contractors, suppliers .and . engineering . service organizations that perform. quality related activities are-reviewed by NUSCO Quality Assurance to assure.that their management regularly reviews the status and adequacy-of their part of.the NUQAP.
i I
f QAP.2.0 Rev.: 7 Date:
Page 7.of 7
yp. m p.z m .g ,m.:. ..ncmw- v--Ow + . - n. m. g. n -- - ~= -
- n. ,
w '
L
-3.0 DESIGN _CONTROI.
3.1'-- GENERAL REQUIREMENTS:
P . . .
The NUSC0/NUPOC is responsible.for controlling design work, administering _ design control activities-(including design; interface)~
and design mo.difications for nuclear safety related systems, .
i- structures and components defined in:the." Category I Systems, Structures and Components-List" (Appendix A).
~
I i - The NUQAP for design i.s established to assure that the applicable-1s design requirements,.such as design. bases, regulatory requirements, codes, technical standards and-quality standards are identified in
, design. documents which~-are reviewed, approved and controlled in
- accordance with established procedures. Such controls include
- review for suitability of application of materials, equipment, parts
i and processes that are essential to the safety related functions .of-
- . the systems, structures and components. . Changes to and deviations f from specified requirements are identified, documented and controlled.
NUSCO'has the ultimate responsibility for design control program-
'- implementation for plants presently under construction and for
, proposed plants. NUPOC has the responsibility for design control:
j program implementation for operating plants unless . they elect to
- appoint NUSCO to perform a modification. NUSCO and NUPOC may j delegate to other organizations the work of establishing
- and -
( executing the design control program or. any part thereof, but retain-
['
1 the ultimate responsibility,-for the program.
l' The interface controls', both internal and external, for organiza-i tions performing. design work for safety related systems,, structures
] and components are identified and. implemented'iniaccordance with .
} documented procedures. This identification includes those organi-1 '
j zations providing criteria, designs, specifications and technical j direction.
t Measures are applied to verify the adequacy of design.~ The extent- !
j of design verification is specified and. documented by the'respon- '
i sible organization. The individuals performing design verification- cj should not (1) have immediate supervisory responsibility for the. .
i - individual performing the design,=(2) have specified a-singular.
} design approach, (3) have ' ruled out certain' design considerations,. ;
j.
or (4);have established the design inputs for the,particular design- . ;
aspect being verified. sThe independent-design verification should- '
j- not dilute or replace,the responsiblity;of the supervisors for.the' 9 t
quality of work performed under their. supervision. Where changes lto. ' ?
previously verified. designs have been made, design verifications :are -
!. required for the change, including evaluation of,the" effects'of- ;
th'ose changes on the overall design. Design. verification may be' ;
f
- QAP 3.0 I
'Rev.:
7.
L Date:El lPage 1 oT 6 { E85!
' ~ ^ -
}-
i 4 >
- b'
g, . n. + ,
- - - .- :.x : -- , .x, v -
- -~ - - m h -' -g v--
, e J : arcomplisheil by testing. Testai toldemnnst rate adequacy i[nder:
asiverse des i gn ' rondi t ions . sha l l '.comgil y' wi t h t he requirements of QAP-l I .0, " Test' Con t ro l". Destkn errors and deliciencies which:ad versely affect safety related systems,: structures and componenti in the design process are-documented,-and appropriate corrective' action is taken. 'These design errors and-deficiencies'are documented in
- - ( . accordance.with design. change procedures or.as', p defined in QAP 15.0.
'.t ) -
r '3.2 IMPLEMENTATION t NUSCO/NUPOC is responsible,for'the-design,' design-review,;
engineering approval'of design-changes,1 design evaluation and design, control of. nuclear power plants. ;Theifpaction'may be~ delegated to' other organizations .to perform _theidesign activity, or any part
~
thereof, but- the responsibility - for. overall design resains with
,j NUSCO/NUPOC. In all cases,,finaliengineering decisions.and ultimatet design control of systems, structur'enfand components related to-
, nuclear power plants is the responsibility-of NuSCO/NUPOC.-
a f ~
NUSCO/NUPOC Quality Assurance p Mforms' audits /surveillances/inspec--
tions, to verify that the engineer,-constructer, contractors, '
., suppliers, engineering service organizations and NU departments are:
effectively complying with the NUQAP and procedural requirements for design control.
L 3.2.1- Design Process Design control measures are applied toidesign analyses, such as, reactor physics , stress, thermal, hydraulic, <
nuclear radiation, accident and seismic analyses;;compat-ibility of materials;- accessibility for in-service :inspec-tion, maintenance, and repair; and delineation of; accept . .
ance criteria for inspections and. tests. MeasuresLestab-
, lished to control. design documents are described in QAP
/ 6.0.
Program proceduresiand-instructions define the: method for-implementing design-control measures. These measures ~
require thatiapplicable lesign requirements, such as, design. bases, regula" uy equirements, codes and stand-ards, are transl W 4 ;t: specifications, drawings,.
Trocedures.orfiu t y'.- .. , Instructions;further require s that appropriate qually (tandards are;specified'and '
included in.designjdocuments. All' materials, equipment,'
, parts and processes',tincluding standard "off'thetshelf".; .
E commercial or previously approved; items. essential to;the '
' safetyJ related . functions', L are' selected and reviewed for ; <
i duitability of application. The basis forJselection may include industry standards; material:and prototype hard-' ,
ware-testing programs,f.and design reviews.
L snV-e 1
.QAP13'0:
.Rev.: j7 >
Date:pof:6-
- Page.2 d-p '_' '
- w. ~
n .. .
k ?
. . . . s e
. . , ' 5 ~
7; ,
< t
]
. g ., , w . .7.m y , a g ;n., x ,. , - -mm
. ,w . , n a.. m . .-: n - - - -
'/ NUSCO Procedures assure that a documented check-is k/ performed to verify.the accuracy and completeness of design drawings and specifications before, release to construction. Design drawings receive'a documented 0.eck to verify dimensional accuracy.
Design drawings ind specifications issued for plant design changes during the operations phase of.an in-service nuclear plant are reviewed for completeness and accuracy, before release to operations in accordance with NUSCO/NUPOC Procedures. Drawings are reviewed for accuracy and completeness in accordance with NUSCO/NUPOC Procedures defining Document Control.
NUSC0/NUPOC Procedures describe the provisions:to assure that design drawings and specifications are reviewed by NUSCO/NUPOC Quality Assurance to. verify that the; documents are prepared, reviewed, and approved in accordance with-
- company procedures, and that the documents contain the necessary' Quality Assurance requirements, such as inspection and test requirements, acceptance requirements, and the extent of documenting inspection and test results.
- 3.2.2 Design Change Control Procedures and instructions governing. design change control during. construction, modifications to operating
[V} plants, control of discrepant 'or deficient ' design condi-tions, and reported unsatisfactory performance, provide for the identification of the need for_ design changes and a documented method to control these changes. Design and
. specification changes are subject to design control measures. commensurate with those applied during the original design.
Prior to receipt of an operating license, an independent q review and approval of design changes is performed by the l organization that conducted ^the original-design reviews, j unless NUSCO/NUPOC designates.another qualified j organization to perform this function.'
Subsequent to ' ret.eipt of an operating' license, proposed safety related design' change / modifications are submitted ( 1 to the in-service units management for processing and' review. This review includes the Plant. Operations Review ,
Committee'(PORC)/ Site. Operations Review Committee (SORC).
PORC/SORC is advisory to -the appropriate NUPOC Superin-tendents on matters ' relating to nuclear safety. _Its composition, responsibilities, and authority are defined in Section 6 of 'each in-service unit Technical Specifica-tion. NUPOC QA personnel cap be = represented at the
- p- -
(- .QAP 3.0 Rev.: 7 1 Da te :f'
-Page 3 of 6.
V : a
m.?i:.:- ,yn .. - e --v .c n 7 %.w ~.r p o a rs c; w wPF=M+hr --
w x:m%
L
.jev:
' iY-PORC/SORC Committees Jif assig' n ed by theLappropriate NUPOC-
')', Unit _ Superintendent. tIf the-change _ involves a Category 1,
- ' system, structure or component, the change - wi ll be - re-viewed by qualified engineering personnel for technital:
adequacy. Reviews of!the design; change requests are per-
~
l-formed by the Nuclear Review-Board / Environmental Review-Board on safety evaluations / environmental questions. .The- '*
sequence of 'the' NRB review depends upon the determination ,
of whether an unreviewed safety question'is-involved._
L (i.e.,.in~accordance with ANSI;N18.7, if a proposed. change: >
in the facility _ involves:an-unreviewed safety question-then the NRB review'is conducted prior to implementation.)
The combination of these independentLreviews by the PORC/SORC and NRB/ ERB are performed to assure that:
- a. the adequacy of the proposed change is determined;.
- b. unreviewed safety / environment'al' questions are pro-perly identified'and handled per_10 CFR150.59;,
- c. nuclear safety / environmental requirements have been considered.
Errors and deficiencies in design, including the. design
, process, that could adversely affect safety-related
' ) structures, systems, and components are documented and.
- ~' corrective action is taken to preclude repetition.
During the operations phase, notification of plant' design
~
changes are transmitted to responsible plant personnel as part of the design pa'cka'ge close out. . NUSC0/NUPOC Procedures describe this notification which assures that personnel are made aware of design changes / modifications which may affect the performance of their duties.
3.2.3 Design Interface Control During design, construction or mojifications~of nuclear power plants, the ' Nuclear-Engineering and Operations l Group -
is responsible for review, coor'dination"and documentation i- of design interfaces.- Procedures provide the method.for n identificati6n of design interfaces,cdesign interface' changes, and' modifications Laffecting drawings and _ design documents. .
During' plant design and construction' phases, control of ,
interfaces may be delegated to.the~ engineer-constructo'r-
- 7 and/or' the Nuclear Steam Supply System l(NSSS) ' supplier. ,
'N &
QAP 3.0 Rev.: 7 Date: AUG 0 9:1985
-Page 4,of.6-o e a s , . 1 s . - - n
c
.wy7 pmw.=3. , . .c x . g .w. pm m -7wn m ~ -
-w-, .m During the operations phase, proce'dures and instructions' (M);
identify design interfaces which are controlled by-the-appropriate NUPOC Superintendent. Resolution of design interface questions are documented.
3.2.4- Independent Design Verification-Original designs and design modifications are reviewed.for adequacy and the sign-of f performed .by .a person other than the originator of the design.- Design verification is documented in accordance with ~ procedures or instructions.
Simplified calculations or' computer models/ codes may be utilized.as alternate means of-design verification. When design-verification is performed by ' testing, the tests lare performed using approved procedures,1 which specify the authority and-responsibility of design verification
-personnel. Ultimate responsibility for design adequacy and evaluation is retained _ by NUSCO/NUPOC, as appropriate.
Design verification (if other'than'by qualification testing) is normally completed prior to release ' for '
procurement, manufacturing,- and construction, or to another organization for.use in other design activities.
For those cases where design verification cannot be completed prior to release for procurement, manufacturing,
-g and construction, procedures ensure that design verification is completed prior to the point when'the
( )" installation is declared operational.
NUSC0/NUPOC Procedures describe the requirements which assure the following when testing is considered as an alternate method of design verification:
- a. Specifications or procedures provide criteria :that specify when verification >should be by test.
- b. Prototype, component or. feature testing is performed-as early as possible prior to, installation of plant-equipment, or prior to the point when the
~
installation.is declared operational.
- c. Verification by test is-performed under conditions that simulate the most. adverse conditions as, determined by analysis..
Particular emphasis is placed on assuring that designs .are in conformance with applicable codes, .and.on selecting the .
proper design verification or checking method. Procedures-and instructions provide the requirements and necessaryE controls for design verification. . These controls include a review-to assure that designicharacteristics can be Ov QAP 3.0 Rev.: '7 Date:f'f; 4 ' ,
Page 5 of.6 !
}e
y sy.m5nmc7ewayx. m sg.n.w m~ s,+nn:om m7>.7x w m msm,zsy-=~m.
' +
z;- . -
2 e
, . g.
4 q . . e , ,
controlled, and verificationathatfthere_is-adequateL b n'
- . accessibility'for' inspection or test,1and that inspection . .
Land test acceptance; criteria are incorporated. .During the:
s <
operations phase, documentation ofl reviews is provided.
NUSCO/NUPOC1 Procedures incl'ude' requirements wh'ich' identify'-
the ' responsibility- of ' design verifiers , . the- areas and1 features to be verified. and the extent-of-the~
r l
-documentation' NUSCO/NUPOC Procedures assure.that procedural control is' -
~
established for design documents.thatfreflect.thei commitments'of.theiSAR. These'proceduraljcontrols; vary.
~
.for-design' documents 1which: receive? formal-designi .
~
verfication .by'several disciplines or1 organizations', and ,
those which.'canibe reviewed by a'. single individual.'!The.
specific' design; documents and, specialized reviews.are~
determined. and used as required by - the design: changes .and : ' '
modifications.
~ '
NUSCO/NUPOC Procedures are established:to assure that .,
verified safety-related computer codes'are certified for'a specific use.
During the design and construction phases,'the NUSC01 Nuclear Project Engineer / Project Engineer maintains < the-ultimate responsibility.for the design-docusents generated b- by the engineer-constructor,1 NSSS supplier and other NUSCO -
departments. - The evaluation of = selected documents - by- _ l project engineets may. be accomplish'ed with assistance from ,
~
other NUSCO departmentsLeoncerned with the equipment / subject covered.by the ~ document being' evaluated. s The NUSCO Nuclear Project: Engineer / Project' Engineer .is -
responsible for.the resolution of NUSCO> comments on-specifications'and' drawings issued by the engineer-constructor, NSSS supplier, and contractors.* ,
J 4
=(' ~
QAP.-3.0
. Rev.: E7:
Dat'e:([ . ,.
-^
" ,; Page 6-of.6 _
3 '
a.
1- f a I % "
t___________________.__*_ . - ir__.L______m.__'___'m __,___________..______.___.,__.__,_u______________;_______ _m__ ,
s.i... m m - w : e n .> w m. m : M p g m g e n .w s w v. n .: w . v n -: w, v.ww4 % v.
lh 4.0 PROCUREMENT DOCUMENT CONTROL 3 s/
4.1 GENERAL REQUIREMENTS
- The procurement of materials, equipment, parts and/or services required during the design, construction, operation and maintenance of Category I systems,' structures and components in nuclear power-plants is performed in a controlled manner which assures compliance with applicable regulatory requirements, procedures, quality assur-ance standards and regulations affecting- procurement documents.
Changes to procurement documents are subject to the same degree of control as utilized in the preparation of the original documents.
4.2 IMPLEMENTATION 4.2.1 Program A Nuclear Project Manager and a Nuclear Project Engineer is selected and a Project Team is formed for each new-nuclear power plant project (i.e. , Millstone Unit 3). The- ,
NUSCO Nuclerr Project Engineer by procedure coordinates the preparation, review and approval and control of HUSCO procurement documents for Category I material, equipment, parts or services. The review and approval. cycle of procurement documents initiated by NUSCO includes: the appropriate.NUSCO department for technical adequacy; NUSCO n\_/ Quality Assurance for inclusion 'of quality assurance requirements, and the Nuclear Project Manager.
A Project Manager and a Project Engineer are selected for each major modification to an in-service nuclear power plant. The project engineer coordinates the preparation, review and approval of procurement documents for: Category I .
material, equipment, parts or services, and ensures the technical adequacy and inclusion of quality assurance requirements.
During the operations phase of nuclear power plants, NUSCO/NUPOC Purchase Requisitions are reviewed for technical adequacy and verification of the Category I designation.
The appropriate NUSCO- Project Engineer /NUPOC Superintendent-reviews and approves Category I NUSCO/NUPOC Purchase l Requisitions. NUSCO quality assurance personnel then j review the purchase requisition,'for the inclusion and . H adequacy of quality assurance requirements, prior to the !
issuance of the purchase order.
During design, construction, preoperational' testing and' operation of nuclear power plants, and modifications thereto, the engineer-constructor, contractors, suppliers 7- y s_ .QAP 4.0
'Rev.: 7 Date AUG 0 9 1985 Page 1 of 4 ,
- i
'l
'I
l mM7?SC5,MG'iW;7MMMy zw ~:y? apon~?w&B?Wnxchy m% NW~ qtnMewpd W
- > 4+
5
,.-,t
- u 3
and engineering 1 service; organizations. utilized by NUSCO/NUPOCT are responsible to implementimeasures for control. of~ _ .
E ,
procurement documents-associated with Category I material',
equipment, parts:and servicesLtoLensure. applicable <rsquirements. s J
including quality: assurance. requirements are specified. .
NUSCO~ Quality' Assurance performs'on?and-off-site audits /surve .-
illances/in'spections to ensure organizations utilized ~by.-
NUSCO/NUPOC.are effectively compi.ying with6their. requirements-for the control'of procurement documents. . .
Changes to procurement documents,Twhetheriinitiated by, NUSCO/NUPOC or their representative,-are subjectedLto_ thei '
same degree of control:as' that utilized. in the: preparation y of the-original document. ; The' procurement 'of spare or:
replacement' parts for safety related systems, ' structures.
or components--is subject,to'the controls'of the' latest;NU QA Program and NUSCO/NUPOC procedure requirements. The' spare or replacement parts are subject to controls: equivalent to original ~or. subsequent' codes and standards. ,
QA review of procurementJdocuments idetermine that: , ,
- a. The quality requirements are correctly stated, ,
inspectable and controllable;.
~
p b. There are. adequate acceptance'and' rejection criteria;
- c. The procurement' document has been prepared, reviewed,-
and approved in accordance-with the NU QA program.
requirements.
4.2.2 Procurement Document Provisions' Procurement documents are prepared,' reviewed and; approved j in accordance with approved procedures.of.the issuing :
j organization or department and f are " documented prior to . 'l release and available for verification. These procedures '
- j require - that procurement documents' consist of ! f the. follow- - '
ing, as necessary:
- a. The scope of work'to be! performed;- !
l Technical requirementsI(specified or refarenced)
- b. .
j including the applicable components.and materials m J identification requirements, drawings,~.specifi ' .
cations, procedures,.instructi'ons,, codes and regula-J tions, and provide for identification ~ of applicable test, inspection and-acceptance requirements , _or? ,
-3 special process instructions;.-
-l b QAP 4.'O Rev.: 17 ' I
- i. . ba te :; \' .' y . , 'l Page 2 of 4.
- , , ; w q .,m -
., ,, 4 u-c m w ~v,wwn -. r--4
/
(m.
) c. - Quality Assurance Program requirements to be imposed on contractors which include the applicable require-ments of 10 CFR 50, Appendix B, and the NRC regula-tory position contained in the Regulatory Guides and their endorsed JWSI Standards listed in Appendix D of this Topical Report;
- d. Right of access which provides, as appropriate,- for access to contractor facilities and records for inspection or audit by NUSCO or its designated representative; and provides access for events such as.those requiring notification of hold points;
- e. The documentation required to be prepared, m'ain-tained, and/or submitted to NUSC0/NUPOC or its representative for review, approval or historical record. The time of submittal of this documentation and the retention and disposition of Quality'Assur-ance records which are not submitted to NUSCO/NUPOC is prescribed.
4.2.3 Selection of Procurement Sources If the engineer-constructor, contractor, or supplier is not delegated the function of procurement source selection,
, ~g the NUSCO Purchasing Department verifies that the procurement
(
\'
) document has been reviewed and approved, and that the supplier has been approved for Category I procurement prior to issuing the purchase order for Category I material, equipment, parts and services. Supplier approval is not required for the procurement of nonengineered items which are:
- a. Relatively simple and standard in design, manufac- I ture, and test (i.e. , off the shelf item, the catalog' number is in effect, a specification which controls the manufacture of the item) and; )
- b. Adaptable to standard or automated inspections and/cr ,
tests of the end product to verify quality charac-teristics af ter delivery and;
- c. Of such a nature that product acceptance inspec-tions/ test performed upon receipt of items do not require operations which could adversely affect the -
integrity, function, or cleanness of the , item.
Procurement documents may be issued to organizations with unapproved quality assurance programs. These procurement documents are approved by -the NUPOC Superintendents, or the cognizant NUSCO Vice Presidents / Directors within the s
\'
QAP 4.0 Rev.: 7 Date:... .
Page 3 of 4
- _ a
M j k ?f:ng g u 9 y.s s y m + ;. .. : ~ -~ pr :x v .
. . st.yc 99-w - : a:+ yr x ,:n un +:. .
h
).
- Nuclear Engineering and Operations Gr'oup, and by' the
- NUSC0/NUPOC Quality Assurance Departments who ensure ~
procurement documents to unapproved organizations contain detailed supplementary quality assurance- requirement.1to meet NUSCO requirements.
Procurement documents,are: reviewed;by NUSC0/NUPOC. Quality
. Assurance' to ensure appropriate quality assurance require-ments are specified. These requirements, included in the
~
procurement document as necessary,_ include audits and inspections at the suppliers facilities with scheduled
~
witness / hold points and' acceptance criteria during.the.
^
fabrication and process of the procurementritem. l Accep-
+
tance inspections and tests determined by NU shall be performed af ter receipt at NU but' prior to ' operation.
J 1
?
4 4
I i
i 4
l i
f 4
i i
l 1 -
l l
J l
., j
.. l l
b f l
- _ QAP,4.0 Rev.
- 7
, . Date:
- Page 4 of 4' l
,.-m,.~, + ,, . . ~ - , . , - # , .- _ , , ,. , , - - _ . -
mm,_ , , - - , ,
_ - _z--- -, 7, m 3 gagFn : *3 A'.1 d
5 1q 44d N d d dh 4 aI d i'.s.b b 4 S.0 PROCEDURES, INSTRUCTIONS, AND DRAWINGS 5.1 GENERAL REQUIREMENTS The NUQAP provides measures for the preparation, review, approval, control and distribution of procedures, instructions and drawings of activities affecting quality of Category I systems, structures and components during design, construction, preoperational testing and operation of nuclear power plants. These documents include appropriate quantitative and qualitative acceptance criteria which specify the activity to be performed, the methods of construction and testing to be employed, material, equipment or parts to b,e used, a sequence of operation and the required documentatio'n.
5.2 IMPLEMENTATION Quality related procedures provide direction for personnel perform-ing safety related functions. The applicable NUSCO/NUP0C Quality Assurance Organization reviews and concurs with quality related procedures originated by other departments. Comments concerning compliance with the NUQAP Topical Report and regulatory. requirements are resolved prior to issuance of the procedure. NUSCO Quality Assurance receives controlled copies of quality related procedures issued by other departments. During the design, construction and o procurement phases, the engineer-constructor, contractors, suppliers,
- , and engineering service organizations may be delegated responsibility L/ for preparing maintaining, issuing and' verifying the implementation of appropriate program documents which are selectively reviewed / approved by the appropriate NUPOC Superintendent, NUSCO System Superintendent Betterment Construction, NUSCO Superintendent New Construction, NUSCO Nuclear Project Engineer, or Project Engineer, as appropriate.
In this case, NUSCO Quality Assurance performs on-site and of f-site audits /surveillances/ inspections of the quality assurance programs to ensure the engineer-constructor, contractor, suppliers and engineering service organizations are effectively complying with their requirements for procedures and instructions. Contractor programs are required to clearly delineate the actinns to be accomplished in the preparation, review and control of procedures, instructions and drawings and the methods for complying.with 10 CFR 50, Appendix B.
5.2.1 Procedures and Instructions Procedures and instructions for activities af fecting quality are prepared, reviewed, and approved in accordance with written procedures and instructions.
During the design and construction phase, the NUSCO Superintendent New Construction, NUSCO System Superintendent Betterment Construct lon, NUSCO Nuclear Project Engineer, m
(
~ / QAP 5.0 Rev.: 7 Date: In)G 0 9 "%
Page 1 of 3
p;( . =n . .. y ,
3: : - m a . w . q: z p ; z. ;.;; & ;, 7 : p : ,.. ,,, -n l-l p
i, /- or Project Engineer, ensures that con t rac to rs , s:ippliers and engineering service organizations implement <,uality assurance programs which contain written instructions for p repa ration , review and approval of procedures and instructions affecting quality. In addition, Contractor's site quality related, construction procedures and quality control inspection procedures are reviewed for concurrence by NUSCO Quality Assurance to assure compliance with the Program.
The NUP0C organization is responsible, during the pre-operational s2st and in-service phase, for the prepara-tion, review and approval of plant quality related pro-cedures. These procedures include preoperational and startup test procedures which are prepared, reviewed and approved in accordance with an approved Startup Manual, and overall site administrative procedures which implement the requirements of the NUQAP' Topical Report. Each NUPOC i organization is also responsible for the preparation,
! review and approval of procedures covering safety related activities in accordance with individual license require- ,
ments. The applicable NUSC0/NUPOC Quality Assurasce' Organization reviews and concurs with inspection glans, tests, calibrations and special process proceduret ,
drawings and specifications, and changes thereto.
s (y) 5.2.2 D rawi ngs The design control and verification measures desciibed in QAP 3.0, are applicable for the review and approv41 of drawings. The Nuclear Engineering and Operations Group, during design and construction phase, or the appropriate
- NUPOC Superintendent, during the preoperational test and in-service phase of the nuclear power plants, has the ultimate responsibility for review and approval o
- new drawings or modifications to existing drawings. "he originating organization may delegate to other organi-zations or departments the work of design and rev .ew activities, or any part thereof, but retains ultinate responsibility for this work.
The measures taken to assure the preparation of aa-built drawings and related documentation in a- timely manner to accurately reflect the actual plant are described in NUSCO/NUPOC Procedures. Drawings critical to ope ration -
l are updated prior to system turnover to operation and are available to the operating personnel.
(8 .
( )
s/
QAP 5.0 ,
Rev.: 7 Date:',, .
Page 2 of 3
, MU f.;'jaf ?:? L.t:9M5i.j% .,4& D %s,$L MWOfude%n%7TW '::.';in gi %%%52;9;. ..; m"%:
. . . , , r h ',
4
~
' 2 ..
t 6
j .: 5. 2. 3 ' Acceptance Criteria ~ [
j- . .. . .
Cognizant Department Heads-review"and approve departmental' 4
{
procedures,' instructions and drawings to ensure the-1
! -- . inclusion of r adequate quantitative _and qualitative accep-tance: criteria, as appropriate,: for determining 'satisfact - !
t, ory work performance and quality compliance. These. s
- criteria apply to activities such 'as- design,.. operations,., -
, test control, inspection land. plant modifications. ,
4 ,
t a i.
i '
.i .. .
l- .
A 4
i- ;
I .. i 1 ,
i .- -I l
- t .t i i
, a 1
.o. ,
4
- 1 4
-1 j' <
t 5
i I L{
t- .
- 1 1 1 t'
l 4 i l
-1, q.
- i
! . i
- . I
- g. i i
8 I
t
?
L 1.
I .'
I 4
i QAP 5.0
' Rev.: '7 i
4- Date:
b ,
- Page' 3'. o f '.3 3
o
)
fQ @ @ 3?w,W S ? ?ht W a ?' ' W7:D .]?-WmDP% W.% MWW"H&?% [DW jr-<I ,
-6.0 -DOCUMENT CONTROL
.;V '
6.1' GENERAL REQUIREMENTS The NUQAP provides measures to assure controlled distribution of documents pertinent to quality assurance for the design, construction, preoperational testing, operation and major modification of nuclear power plant safety related systems, structures and components .in accordance with NUSCO/NUPOC quality'related procedures and 10 CFR 50, Appendix B.
Documents such as procedures, instructions, drawings, specifications and reports are prepared, reviewed for appropr'iate qualitative and quantitative acceptance criteria, and approved by authorized person-nel in the affected organization. Approved controlled documents are distributed to affected locations in accordance with controlled distribution lists. Changes to controlled documents are reviewed and approved by the same organization which performed the original review and approval, unless otherwise specified in the implementing procedures. Measures are provided for controlling documents to '
preclude the possibility of the use of outdated documents.
6.2 IMPLEMENTATION 6.2.1 Responsibility
* NUSCO/NUPOC Procedures and Instructions delineate the-measures for controlling documents including direction for the review for adequacy, approval by authorized personnel, distribution of controlled documents and verification-that changes are promptly incorporated and ' implemented. These control measures apply to documents affecting the quality of nuclear safety related systems, structures and compo-nents during design, construction, preoperational testing, operation and major modifications thereto such as:
- a. Design Specifications;
- b. Design, Manufacturing, Construction and Installation Drawings;
- c. As-Built Documents,
- d. Quality Assurance Program Manuals, Procedures and- .
Instructions;
- e. Manufacturing, Inspection and Testing Instructions;
- f. Test Procedures; s -
C/ QAP 6.0 Rev.: 7 Date: AUG 0 9L1985 -
_Page 1 of 4
Nf:T.T:9%; Wimle.M:D;#.WWQ :% uM*N;WMi+QpnW1Ct%%%;9QwWW=.wv w '
t i g. Preliminary Safety Analysis Report; v
- h. Facility Description and Safety Analysis;
- i. . Final Safety Analysis Report;
- j. Procurement documents;
- k. Design Change requests;
- 1. ~ Topical Report;
- m. Nonconformance Reports;
- n. Computer. Codes.
NUSC0/NUPOC Procedures describe the measures taken by NUSCO/NUPOC Quality Assurance or individuals other than the person who generated the. document but qualified in quality assurance, for the control of documents to assure review and concurrence, as necessary, for 'such documents . .
listed above with regards-to Quality Assurance-related aspects.
The requirements for control of procurement ~ documents are contained in QAP 4.0. During all phases of plant life, it x is the respondibility of each organization issuing con-trolled documents to employ document control procedures.
The issuing organization is additionally responsible for distribution of the documents.to appropriate locations.
There shall be provisions to assure that approved changes are included in instructions, procedures, drawings.and other documents prior to implementation of the changes.
During the design and construction phase, the engineer-constructor, contractors, suppliers and engineering service organizations are responsible for implementing measures for review, approval,. control and distribution of controlled documents, to ensure they are effectively complying with the requirements for document ' control.
NUSCO/NUPOC Quality Assurance performs periodic on-site and off-site audits /surveillances/ inspections of the engineer-constructor,- contractors, suppliers and engineering.
services organizations to verify compliance with their
~
approved quality assurance programs.
- 6.2.2 Distribution of Controlled Documents NUSCO/NUPOC Procedures, specify in what manner controlled documents and revisions thereof, are distributed to -
appropriate locations, prior to commencing the work.
O
~V QAP 6.0-Rev.: -7 Date:7J.* ?: 0 '.: ' "i
. Page 2 of 4
-- - - ___ - -_--- - - _ ____ _-- - - - - _:--__- _ _-___ _ __ __ __. _ _ - _ . ._-______-______-__-_-__---__.___-_a
.mp .fm; TGTpe og.y sw:py wm::2W0%g < y Me.us W :: m L
- l. 3 Holders of controlle'd copies.of. documents complete
- acknowledgement of receipt forms and return them to"the' distributor in order to' assure that obsolete or superseded
, documents are removed from the work areas in a timely
- manner. NUSCO/NUPOC-Quality Assurance' perform periodic
(~ on-site'and off-site Audits /Surveillances/ Inspections to L verify compliance with the requirements of procedures for i document control.
l' 6.2.3 Drawing Control During the preoperational test and the in-service phases of nuclear power plants, the NU Generation Facilities-Records Organization is responsible to implement a program, as per approved procedures, for the retention and retrieval of drawings and records s'ubmitted by the cognizant NUSC0/.
NUPOC project personnel. The NU Generation Facilities Records Organization maintains a drawing status file-for in-service units which includes drawings newly issued or revised with latest revision and current status.
The engineer-constructor, contractors, suppliers and engineering service organizations utilized by NUSCO/NUPOC during the design, construction and major: modification to nuclear power plants may-be delegated the function of drawing control and must furnish periodic. status reports O listing the revisions of applicable drawings which they issue.
NUSC0/NUPOC Quality Assurance' performs on-site and off-site audits /surveillances/ inspections of suppliers to verify they are effectively complying with their programs ' for document control of drawings.
If the engineer-constructor, contractor or supplier is not delegated the function of drawing control, the NUSCO Nuclear Project Engineer is' responsible .for. the distribution of drawings to appropriate NUSCO/NUPOC personnel in accordance with controlled distribution lists.-
6.2.4 Instruction and Procedure Control During the design and construction phase,'the engineer-constructor, contractors, suppliers and engineering.
service organizations are . responsible for control- of . .
quality related procedures and instructions issued by them~ NUSC0/NUPOC Quality Assurance performs on-site and off-site audits /surveillances/ inspections of the engineer-constructor, contractors, suppliers and engineering service organizations quality assurance programs.to ensure-
\
QAP 6.0" j Rev.: -7 l
, 'Date: ,
l Page 3 of 4- ,
6' _.________-_-__.______.-___.___-.___._L__._______ 1- --_:__
MG&sQGM!sm f: W.;.J ';&:4 NOlL; ;f.c. 7,uu;.: nim lnt'x a++.x.3.>.tv w %e m ;e, s 9~% L:'.q' e' l
'they are effectively complying with their program for.
~
control of procedures and instructions.
' During all phases of plant -life, Lthe originating depa.. ment '
is responsible for= establishing adequate control over quality related procedures and. instructions issued by1 ,
them. The responsible organization 'also issues status ,
reports or revised indices' listing the latest revision of applicable controlled. documents issued by them.- .
Y r
.QAP 6.0
' Rev. : '. 7 ,
Date: AUG 00 E6s
~
Page 4 of 4 J
r+i%yT(%;g.W;iydI!g $ ?t, W W9?M?& % MlVM]?M:P ?$%.WWP ' WWW ~ 9-My s O S+N
. r - ,
- ,s p; ,
c '
, 3 -
f .
, 7.0 CONTROL OF PURCHASED MATERIAL,-EQUIPMENT JAND SERVICES- ?
7.1 PURPOSE
- Measures for the control of, procured materia 1.. equipment, parts :and services by or for NU related to the safety of nuclear: power plantsi are established'and, imposed bytthe NUQAP.during design,. construction,
(;
preoperational testing,. operation, maintenance and major modification, to ensure conformance to procurement documents. .These measures
!. include provisions ; for source evaluation and selection, submission of objective evidence by the contractor or sub-contractor; inspection at the supplier source and examination of items'upon delivery..
Control of. quality by contractors and sub-cont'ractors'.is' assessed' for effectiveness at. intervals' consistent with the importance,,
complexity and quantity of the product or service. -
7.2 IMPLEMENTATION ,
The word supplier is used in this section to designate what.is otherwise described as the engineer-constructor, contractor, supplier "
or' engineering service organiza' tion.
The evaluation and selection of suppliers is performed in accordance-with procedures, which specify.that procurement source' evaluation and selection measures are performed tofdetermine supplier capabil-ity and delineate responsibilities of qualified' personnel.' involved ,
L in the evaluation and^ selection process.
l-7.2.1 NUSCO Quality Assurance utilizes one' or more of the following methods in evaluating the qualifications of a potential supplier:
- a. . Coordinated review of a potential supplier utilizing one or more departments l(i.eJ.. Engineering,;Construc-tion, Operations and/or-Purchasing);~
.b. Engineer-constructor /other utility supp1'ier evalua-tions;
- c. Coordinating Agency for Supplier Evaluation,(CASE))
evaluations.
- d. ASME MM or MS Quality System Certificates.
~
Evaluations ensure that NU suppliers employ a quality- .
assurance program-that conforms to applicable portions 'of the NUQAP Topical Report.E NUSCO Quality Assurance maintains-documented evidence of theievaluation and' acceptance of; -
the supplier's quality assurance program. The determination
.QAP 7.0L '
'Rev.: '7 Date:P) .M l'; 'l , '
p ,Page;l of 4.. f h' ,
l m
. ,y
.p v
gfe;593*W"esjfm y' % y ";.5 w ,a=m jp rygy:n, W W q n c.m y - api cW s 3 , ,
g , . u ; .
+
3 - , -
, .,. , n.
g v -
4 6 m 1
, e ~t
, , .j"
, t - of. supplier approva111s . based 'on^such : factors ?as prior; 2 .
' performance,' historical quality performance data J source- '
surveys- or audits 'and evaluationsLof the supplier's1 quality' assurance program. _
Suppliers Certificates of Conformance are periodically .. 1 f
evaluated by audits, independent-inspections and. tests, to
.' assure!they are valid; :This verification of Certificates; H.
of ~Conformance is documented. - , -
7.2.2 Source Inspection -
NUSCO Quality Assurance is. responsible for the performance of source inspections'at suppliers; facilities:tol ensure '
~
that the requirements of:a Purchase Order / Contract- have been met.
Surveillances' of suppliers are performed Lin accordance with written procedures which provide for:
~
- a. The method .of surveillance and the extent of docu- - '
mentation required and those responsible'for imple-menting those instructions; +
- b. Surveillances of those items where ve'rifications of procurement requirements'cannotzbe determined upon receipt. ,
7.2.3 Receipt Inspection If the supplier is not delegated the-function'of' receipt inspection for procured items,[it isiperformed under :the1 f, direction of NUSCO Construction Quality Control /NUPOC Quality Assurance in ~accordancef with quality procedures .
which delineate requireme'nts.and?r'esponsibilities necessaryo to perform inspection. functions'1: Contractual: obligation.
fulfillment and quality assurance. requirements'are veri-fled during receipt inspections.
Receiving inspection ofisupplier-fu'rnished material, equipment, and services .is performed to = assure thati ,
material, components, equipment 1and acceptance / records are-inspected and judged acceptable in'accordance'with'prede,j
~
termined inspection instructiens prior;to' installation.or.
use. Receipt inspections include,.as appropriate:. '
~
- a. Measures for verifying that1the shipment ;is complete, ~
properly identified, undamaged'and corresponds'with7L the receiving documentation;. '
4 6
. QAP 7.0; ,
Rev.t. 7' .
Date AUG 0 919851 mn -
- Page,2;of<4/
',1 i '
r' . (.
'k' I i
e .1 -
= TR
_:@ QpgMK>'GG;ipM.L
- u 2 5 9 -l -liQ p g % M + R B @ , W 7 _'l N 5. & 7 9 2 ;D.-?x.!s a ; 2 V ' ' *
- v. - ,
r ,
- p. -
, s .
,1 , ,
1 : [ .
l Measures for inspection of- the; item and review .of ri .
'b.
j ' M' -' supporting documentation-(e.g.,; mill? test reports ,' . ,
c NDE' reports)'as required.by the purchase documents;-
i
.c. Measures for inspection and. acceptance of. items to-inspection instructions;-
I~ d. Measures 1 for identifying- and controlling 1 acceptable g items. including-identification of. inspection status .
. prior to release from the receiving _. inspection area; -
- e. Measures for-identifying, segregating and handling 5 I nonconforming items; ,
o l, f. Measures to ascertain that inspection records or ;;
certificates of conformance are available prior to
. release to constructiou/ plant ~for installation.
1 Supplier Furnished Records- U 7.2.4 Records required to be: furnished by'the supplier are specified in the procurement document. Certifications.or! 1 documentation verifying conformance, provided by th'e supplier, identify that all the. specific procurement requirements-have been' met (either by. reference to the '
purchase ' order or* by delineation).
j The supplier must furnish the,following_ records as.a 1 minimum: l t
- a. Documentation thatfidentifies the. purchased siaterial-l or equipment and the specific. procurement require : j ments,-(e.g., codes, standards and~ specifications)-
met by the items; j l b. . Documentation that identifies any procurement' U requirements which have not been met, together with a' '
description of those nonconformances" dispositioned
" accept as is" or " repair"._
e ,
The responsible NUSCO/NUPOC QA/QC personnel:shall~ review for- 3 acceptability these documents which pertain to the; -!
requirements in the procurement' document, in accordance= W with the NUQAP Topical, Report and its applicable procedures. . ..
7.2.5 nUSC0/NUPOC Procedures address'the-measures taken'to.h.
assure that .for nonengineered "of f-the-sheif" Jitems, where 1 ,
specific quality assurance controls 'for nuclear applications . > , l cannot be imposed in a practicable manner,t special verificati.on
~
. requirements are established and' described.
- QAP 7.0 -
s-gey, ; - _7 4 Datedt)G0I.;'~ ,,-
- Page'3.of 4-
~
. , '.g ,
' s f
)
fI
_ ._-.-1.m.._____._ _ _ . _ _ _ _ _ _ . . . _ . . - _ - _ . __a._.m__2 _ _ _ _ . . - ___m-
-gsny; . , pg . .y - y..u ;>p . . 7 ;g,.g,,;;,;.. ggsg.g, . gg.gy
. '.r., w .,,g,y;,7 ,g.9 ,n j.; ;g , , j 3,,g a .
4 The'se measures follow the guidance in Regulatory Guide 1.144,
) -
. paragraph C.3.b(1) and Regulatory Guide;1.123 and applicable paragraphs of Section .10 Eof ' ANSI N45.2.13. These measures include. appropriate requirements:for special categoriz. tion
~
and identification within the procurement document, receiving inspection, and additional'controis during the installation and testing process-to be performed by applicable NUSC0/NUPOC Quality Assurance organizations.
-QAP 7.0 Rev.: 7 Dater,7', . .
! Page 4 of 4 i
~
- Q;im m m.,s .-Q "+; .-m =< - w w w. e 7m
,./3 i ) 8.0 IDENTIFICATION AND CONTROL OF MATERIALS, PARTS AND COMPONENTS' 8.1 GENERAL REQUIREMENTS During the operations phase, NUSCO/NUPOC organizations assure that the identification of inspections, tests, and operating status of structures, systems, and components is known by affected organ-izations.
The NUQAP provides measures for the identification and control of Category I material, parts and components, including partially fabricated assemblies, during design, construction, preoperational testing, operation, maintenance and major modifications thereto. To ensure that each item can be traced to associated documentation, the identification of the item is maintained by heat number, lot number, part number, serial number, or other appropriate methods, and is physically marked on the item and/or on records traceable to the item. Documentation associated with material, equipment, and components verify that these items have been designed, fabricated, manufactured, tested, and inspected in accordance with specified '
requirements. The object of these controls is to prevent the use of incorrect or defective material, parts and components, in accordance with 10 CFR 50, Appendix B.
8.2 IMPLEMENTATION O NUSCO/NUPOC Procedures establish the responsibilities and require-ments for the identification and control of materials, parts and components. The procedures assure that identification and control is maintained throughout fabrication, receipt, handling, storage and installation of items. Provisions include:
- a. Requirements for traceability to appropriate documentation such as: procurement documents, manufacturing documents, drawings, specifications, certifications, inspection and test records, and nonconformance reports.
- b. Controls to assure that the correct identification of an item is verified and documented prior to release for fabrication, assembly, shipping or installation.
- c. Requirements which ass'are that the method or location of markings do not affect the function or quality of an item.
- d. Establishment of identification requirements in specifications, drawings, procurement documents, procedures or instructions.
During the design, construction, preoperational testing, operation, maintenance or modifications to nuclear power plants, NUSCO/NUPOC 3 5
,/
QAP 8.0 Rev.: 7 Date: AUG 0 91985 Page 1 of 2
- -ygc.;grugjyw;;R w..;gm
- 7g;yr.pm;r-s 3 ry.,..ny.;gg745:,9;g m y g.x;;p 1 ,
may' delegate any portion of the implementation of~the'identificat' ion:
~
-and control program to the engineer-constructor, contractors, .
suppliers and engineering . service _ organizations',- as ; appropriate. If?
delegated,. contracts require that the contractor _ establish;an identification and control program which meets the NUQAP Topical Report:requirementsc In this~ case NUSC0/NUPOC Quality Assurance performs on-site and.off-site audits /surveillances/ inspections'of, the engineer-constructor, contractors, suppliers,: engineering service organizations quality assurance program;to-ensure they are effectively complying with their requirements for identification'and' control of material, equipment and components.:
During the preoperational. testing and the in-se,rvice' phase' oft nuclear power plants, receipt inspections are performed to verify .
that material, equipment and components are properly identified in accordance'with procurement. requirements.: ' NUPOC Quality Assur-ance/NUSCO Construction Quality Control-is responsible for assigning ~
and applying permanent identification to the items in.accordance with approved procedures. .If the application of a serial number is not practical, other means of ' identification are' implemented to assure proper identification and traceability.
~
In the event that the equipment, material or components are noncon-forming or the identification becomes lost or illegible, the items -
are considered nonconforming and are identified and controlled in accordance with QAP 15.0.
Y
.QAP 8.0 <
Rev.:- 7 ~,
LDaterl,,[Qgljij[ ,
Page 2 of 2;
j:@WOMyMP?MSW.;P .MW6fG*CU9W@/? yMcEDS7tN- eett wFT sJ MNWW v.MH r- .
r 9.0 CONTROL OF SPECIAL PROCESSES 9.1 . GENERAL REQUIREMENTS The NUQAP provides measures to assure control of special processes associated with Category I; systems, structures and components by the-use of qualified, approved procedures, equipment and personnel during, design, construction, preoperational-testing, operation, ,
. maintenance and major. modifications.to nuclear power plants'.
Special processes are performed under controlled conditions in accordance with special requirements and may include,.but are not limited to: . welding, cleaning, heat treating, and nondestructive examination and/or testing. .
9.2 IMPLEMENTATION During design and construction of nuclear power plants the NUSCO-Nuclear Project Engineer is responsible for ensuring that special process data and documentation is reviewed, and that contractors
- and/or engineering service organization's special process procedures; utilized at nuclear power plants are qualified and approved,'and that personnel and equipment utilizing special processes are properly.
qualified.
NUPOC special process procedures utilized during preoperational ,
testing, operation, maintenance, modification and refueling of the in-service nuclear power plant are prepared, reviewed and approved in accordance with procedures as specified in QAP 5.0.
During the design, construction, preoperational testing and opera--
tion phase of nuclear power ' plants' the ' responsibility for control'. of "
special processes, when applicable,_is delegated to the engineer-constructor, contractors, suppliers,and engineering service organizations utilizing special process procedures.which are approved.
Personnel and equipment involved in special process-procedures are qualified prior to the start of work. 'NUSCO/NUPOC Quality' Assurance personnel perform on-site and off-site audits /surveillances/ inspec-tions to ensure the engineer-constructor, contractors, suppliers, and engineering service organizations are effectively ~ complying with their quality assurance program requirements for' control of special processes.
9.2.1 ' Procedure Qualific'ation and' Control -,
NUSCO/NUPOC Procedures specify th'at. written process' control documents are utilized and qualified .as required, in accordance with applicable specifications, codes or-standards.
QAP 9.0 r
.Rev.! 7
< ge 019ab\
1 .
Ngw pvp .e.- ,
, ep.wuj ,7. s , ~ z a3 we n,=r ,, - .c 1
lo) v 9.2.2 Personnel Qualification and Certification Codes, standards and NUSC0/NUPOC procedures specify personnel qualification / certification requirements.
Personnel responsible for the performance and verification of special processes are trained, tested, and certified as required by applicable specifications, codes and stand-ards. Requirements for the period of certification, retesting, and recertification of personnel are also specified. . Contractors qualify personnel and maintain records of qualified personnel in accordance with applie-able codes, standards, specifications, and contract or procurement document requirements.
The NUSCO Manager, Quality Assurance is responsible for the training, testing, and certification of all NUSCO/
NUPOC NDE personnel in accordance with the requirements of Regulatory Guide 1,58 (Rev. 1, 9/80) and ASNT Recommended Practice No. SNT-TC-1A.
During construction, the NUSCO Nuclear Project Engineer, NUSCO Superintendent New Construction /NUSCO System Superintendent Betterment Construction, and Manager-NUSCO Construction Quality Control are responsible for the review of records of qualified personnel, equipment and procedures associated with special processes. During p)
( preoperational testing and operation of nuclear power N /' plants, the NUPOC Quality Assurance Supervisor' is responsible for the review of these records.
9.2.3 Special Process Records Records provide objective evidence that special processes were performed in accordance with approved procedures, by qualified personnel, and that when required by procedures, specifications, and codes, such performance was verified.
Results of nondestructive examinations are recorded in accordance with applicable specifications, codes and standards. These records are retained by the supplier or supplied to NUSCO/NUPOC as required by contract or purchase orders. If records are to be retained by the supplier, the contract or purchase order specifies -the retention period and instructions for final disposition of records.
During construction, the NUSCO Nuclear Project Engineer, .
NUSCO Superintendent New Construction /NUSCO System Superintendent Betterment Construction, and Manager-NUSCO Construction Quality Control are responsible for the review of documents for acceptance, and for assuring that documents for special processes utilized during construction are reviewed and accepted. During x/
) .
QAP 9.0 Rev.: 7 Datet[' ', . D Page 2 of 3
, s u -r ., n;.: : , ;mvt.m 7.gm: +g ,e; e.- . .m y .+-, .
m c.y mfn; e.3:w=m: ,
\ .
preoperational testing and operation, the NUPOC Quality Assurance Supervisor is responsible for the review for -
completeness of data and documentation associated with the performance of.spect.a1
' processes.
Special process documentation such as: special' process procedures, qualifying data, and personnnel and equipment qualification records associated with the performance of-special processes'at nuclear power plants, are kept current and maintained in appropriate NUSCO/NUPOC files, with final disposition to the appropriate NU Nuclear Plant Records Facility.- .
9
. QAP,9.0-Rev.: 7 Date: AUG 0 01985-Page-3 of 3 4
m, ; . ;m ~ ,, w. , .w,w. - -- . ,.: = , -
~
10.0 INSPECTION 10.1 GENERAL REQUIREMENTS Inspection of activities to verify the quality of Category I sys-tems, structures and components, which are performed by or for Northeast Utilities (NU), are executed in accordance with the -
. Quality Assurance Program (NUQAP) and appropriate procedures, instruc-tions and drawings by qualftied personnel independent from the individual or group performing the activity being inspected. If inspection is impossible or disadvantageous, indirect controls by monitoring processing methods, equipment and personnel are provided.
Inspection notification and hold points are identified, as required, in the applicable documents.
10.2 IMPLEMENTATION 10.2.1 Inspection Responsibilities During the construction phase, NUSCO/NUPOC Quality Assurance ,
performs audits /surveillances/ inspections to verify that the engineer-constructor, contractors, suppliers and engineering service organizations are effectively comply-ing with their quality assurance program requirements for o inspection. NUSC0/NUPOC Quality Assurance also observes the performance of' selected' inspections on-site and at contractors, suppliers and engineering service organiza-tions facilities, associated with or specified as " hold
or "notifica. tion" points in procurement documents. In all cases audit / surveillance / Inspection activities are performed as specified in written quality assurance procedures.
During the preoperational testing and the operations phase, qualified NUSCO/NUPOC Quality Assurance personnel shall review procedures for maintenance, modification, and inspection in order to determine the need'for:
- a. Inspections (e.g., receipt inspections, installation, system turnover, and product acceptance);
- b. Identification of inspection personnel;
- c. Documentation of inspection results. .
The review also ensures that the necessary inspection requirements, methods, and acceptance criteria have been identified.
QAP 10.0 Rev.: 1 Date:f,y3!)')'[j'*j Page 1 of 4
p: yew :,9w m ~ w. : c.sr
, . m s. m rp ~ p 3 3 m :n
, . . . n w.m m' ~ . w:m
'x y( ' .
a O *
- NUSC0/NUPOC'Qualit Assurance' performs audits / surveil-~
lances /inspectionsuto' verify that contractors, suppliers, and engineering; servicp organizations .are eIfectively '
complying with ;their qualityf assurance : program requirei aids i for inspection'and'for performing / witnessing inspections at " hold" or " notification"' points' identified in NUSCO/NUPOC procurement documents. -All audit /. surveillance / inspection activities are performed under requirements specified:in-written quality assurance procedures.
10.2.2 Inspection Plans and Schedules Documented inspection' plans may be eiti her a _ separate document or an ' integral part of work instruction ~docu ;
raents . .The plans are based on design specifications',
procurement documents, drawings, other specifications,'or-previous experience, as-appropriate. . Inspections are scheduled to assure that sufficient time and resources are available,'and to assure inspections are not inadvertently omitted or bypassed.
During NUSCO-directed activities of in-service nuclear-plants, NUSCO Procedures provide criteria for the.
determination of. accuracy requirements of' inspection equipment and when inspections are required. These procedures describe requirements for the preparation of' O inspection plans and schedules by NUSCO Construction Quality Control. NUSCO Procedures also describe requirements for audits and surveillances performed byi the NUSCO Construction Quality Assuran'ce Section to '
assure the implementation of the inspection '
plans and schedules. .
During the operations phase of in-service nuclear plants, inspection activities are performed'in accordance with.
NUPOC Procedures. NUPOC Quality Assurance participates.
in inspection activities by the review of work procedures and the preparation and approval of inspection plans.
The inspection criteria, including the.use of_ inspection equipment and'their accuracy.kequirements, are specified in the Job Packages / Inspection Plans.:
10.2.3 Inspection Personnel and Inspection Document Access a.. Inspections are performed by individuals other than those who performed or directly supervised the activity being inspected. . Inspection personnel are qualified and/or certified in accordance.with appro-priate codes, standards,. and/or NU trainins programs; O
QAP 10.0 Rev.: 7 -
.~
.Date: AUG 0 01905-Page 2:of 4'
__.______.__Em_____._._.____.i___.___.'_____.__-____m_._..__________i___.____.________
-_____m._'
w ;=.e: .,.y . , .-o.,. .wm- w , . - - - - = - - . . ,
< x,.
n: ., 3, r
I I 9, ~,.. } . [ .
- c! 6o . - r; . i _ , ,
i-
- b. Inspections are performed by NUSCO/NUPOC Quality-Assurance / Quality Control personnel or, by qualified
-] '
NUPOC plant personnel / contracted' personnel, who are independent from undue pressure such as cost. an('
schedule. When NUPOC plant personnel / contracted personnel perform inspections, their inspection plans / procedures and personnel qualification criteria are reviewed and found acceptable by the Quality Assurance organization prior to the initiation of the activity. ,
- c. Access to drawings, procedures, specifications or other documented criteria necessary for the perform-ance of inspections is provided prior to performing the inspection activity.
10.2.4 Inspection Procedures
- a. Required inspections, surveillance, or monitoring activities are performed and documented according to .
written, approved procedures and/or checklists. . .
Inspection procedures, plans or checklists contain the following: -
(1) Identification of characteristics to be inspec -
ted; *
. (2) Identification of the individual or groups responsible for performing the-inspection; (3) Requirements for the necessary measuring and test equipment and the required accuracy of this equipment.
(4) Acceptance criteria; (5) A description of the method of inspection; (6) A record of the results of the inspection; (7) Record of inspector or data _ recorder.
- b. Written anproved procedures specify surveillance or monitoring of processing' methods, or testing and operation of equipment when inspection is impossible, inaccessible or not applicable. ,
- c. Modification, repair, replacement or rework' items are inspected in accordance with original inspection requirements or approved alternatives.
b g QAP 10.0 Rev.:
.Date:M 7 , ,t 3,m Page 3 of 4
3 ~ w ; w .gc 5v.c g.a. w p e w c avyn y gyce- >= m w . .. . me: v ' .m . ~
- Ij.
2
.,, j -
i .#
(
) d
- d. During the preoperational testing and the operations f(o)
N-s phase, inspection procedures are reviewed by. Quality Assurance personnel to determine the need for: 1) an independent inspection, 2) the degree and method of the inspection, if such an inspection is required, 3)
~
the identification of inspection personnel, and 4) the documentation of inspection results (for proce-dure review requirements, see QAP 5.0).
10.2.5 Mandatory Hold-and Notification Points Mandatory hold points are utilized when an , inspection /
operation must be performed or witnessed and signed-off by the responsible personnel before work can proceed. Noti-fication points are used to identify the operations or completed processes that NUSCO/NUPOC or its representa-tives may elect to witness and/or inspect during the manu-facturing, construction, installation process. Mandatory ,
hold and notification points, as required, are identifled !
in procurement documents and procedures. These documents.
are subject'to the review and concurrence-of NUSCO/NUPOC Quality Assurance for adequacy of inspection, notification and/or mandatory hold controls.
10.2.6 Inspection Result Evaluation j
() Inspection results are-evaluated for acceptability in accordance with approved NUSCO/NUPOC Procedures which identify the responsible organizati.on.
These evaluations are performed by the responsible NUSCO/NUPOC personnel who are qualified in accordance with l the appropriate Regulatory Guide / ANSI Standard commitments listed in Appendix D.
NUSCO, Quality _ Assurance performs audits to assure that inspections are performed per the requirements of
- applicable NUSCO/NUPOC Procedures.
4 -
'1 l
'l l
fN' QAP 10.0 l Rev.: 7 Date:f 1 Page 4 'of.4 I
j
, . . .,, ;, w . . - . .w a . ,- := --- x ;
_ _ = ,
i t
y h-g q
.R
^
1 11.0 TEST CONTROL E
[ 11.1 GENERAL REQUIREMENTS g A documented test control program is established by the NU0AP for -5 Category I systems, structures and components to ensure that they ]
will perform satisfactorily in service and that test results are documented in accordance with 10 CFR 50, Appendix B and other _.'
I pertinent regulatory and/or technical requirements. .
4l 1 The test control program identifies the systems, structures and 'Bl components to be tested, method of conducting tests, evaluation of g tests and documentation of tests by qualified personnel to assure 3 g requirements have been satisfied.
fl The test control program is systematic and includes proof test prior to installation, construction tests, preoperational tests, sutveil- -]
3 N-lance tests, start-up tests and retest following repairs, replace-ment or modification.
h 11.2 IMPLEMENTATION -
11.2.1 Test Program El
} q t
i Test requirements to determine or to verify the capability a of an item to meet specified requirements in accordance i 9 with engineering / design documents, Safety Analysis Reports -
(SAR), technical specifications, procedures or procurement 5 documents, as appropriate, are accomplished by subjecting
- the item to a set of physical, chemical, environmental or operating conditions. Retest following repairs, replace-T
- Q-ment or modification is performed in accordance with the M
) original design requirements or acceptable alternatives i and is performed when original test results are invali- iy i dated. G_I y
w a
? NUSC0/NUPOC procedures are written and approved to delineate the methods and responsibilities for controlling, accomplishing j
4 ;
Y and documenting testing during the construction, preoperational 2 i
testing, maintenance, operation and modification of nuclear power plants. f g
I During design, construction, preoperational testing, ;
( operation, maintenance and modification to nuclear power
~
-_; plants the engineer-constructor, contractors, suppliers _3 y
and engineering service organizations, as appropriate, are -
I responsible for imple menting measures for the control of 3
[ tests to ensure that Category I material, equipment and g b parts will perform satisfactorily. NUSCO/NUPOC Quality @
y Assurance performs on-site and off-site audits /surveillances/ _
i; .
g, 5 '
(
QAP 11.0 Rev.: 7 3
i
- Date: AUG 0 S 1985 Page 1 of 3 ;;
Y '
~ '
i
. .y.vfg p,. , . - s c ; e e y w .. .m ss... , y, , .s - ,, .z-l i
~
[~'h , inspections of selected -proof tests when '_' notification" T, points.have been identiiied in Purchase Order / Contracts of the engineer-constructor, contractors, suppliers and engi-neering service organizations to verify they are complying with their. quality assurance program requirements for test-control. Documentation' associated with these observations are maintained by NUSCO/NUPOC Quality Assurance.
During the preoperational testing phase of nuclear power plants, preoperational and startup testing is conducted by qualified personnel in accordance with procedures pre-pared, reviewed and approved in conformance to a NUPOC startup manual. ,
During the in-service phase of nuclear power plants proof tests, product acceptance tests, retest, and periodic surveillance tests are conducted by qualified personnel in accordance with approved procedur,es. Personnel performing tests ensure that calibrated equipment'and instrumentation utilized.are within the calibration interval specified.
Documentation including test procedures and approved _ data '
sheets are maintained in appropriate files.
11.2.2 Test Procedure Preparation and Test Performance
_, Testing is accomplished in accordance with approved test procedures which incorporate or reference the requirements and acceptance criteria in the applicable design and procurement documents. The test procedure er test program documents include the following as a minimum:
- a. Instructions for the testing method used;
- b. Required test equipment and' instrumentation;
- c. Test requirements, such as acceptance and . rejection criteria;
- d. Hold, notification, inspection and data collection points;
- e. Test prerequisites such as: calibrated . instr umenta .
tion; trained, qualified,~and. licensed or certified-personnel; preparation, condition and completeness of item to be tested; suitable and controlled environ-mental conditions;
- f. Methods for documenting or recording test data and results;
- g. Provisions for data collection land storage.
i
- #'N s_/ QAP 11.0 Rev.: -7 s .)
Date:f;Ua 0 0 ; ;. 3 -i
'Page,2 of 3 b
- +.%&WW6
- Wur9W 9 FFW . -W% ' > -3 w~ -- e -
- - ' 'm . '-
11.2.3 Test Equipment (f%)
During NUSCO-directed activities of in-service nuclear plants, NUSC0/NUPOC Procedures provide the~ criteria . ' ar determining when a test is required and- the accuracy requirements of test equipment.
During the operations phase of an in-service nuclear plant, the'following steps are taken:
- a. To ensure accuracy, test instrumentation is checked -
and calibrated in accordance with NUSCO/NUPOC procedures.
- b. Plant instrumentation used in t'esting is calibrated.
It is maintained in calibration at regular intervals in.accordance with established surveillance and/or preventative maintenance procedu'res.
- c. Where special instrumentation is required for testing, the-requirements are stated in the procedures.
Instrument characteristics, including-accuracy requirements, ' are equivalent to lor better ~ than those specified by the vendor.
11.2.4 Evaluation of Test Results
[' The documented test results are evaluated against the predetermined acceptance criteria by an; individual or group having appropriate qualifications. The accep'ance t status of the test is documented. Deficiencies.noted during the evaluation are documented and dispositioned in-accordance with approved procedures.
The evaluation of test results may also be delegated.to other organizations. . The evaluating organization is required to assure the use of qualified personnel, eval- :
uate the data against predetermined criteria,and. document l the results of the evaluation and acceptance status of.the-test. NUSCO Quality Assurance performs audits / surveil-lances /inrpections to verify that these organizations arei effectively complying with their quality assurance program
~
requirements.for test control.
J 6
"~
.QAP 11.0-
'Rev.: 7 1 Date:f,'"'. .
-Page;3 of-3
- -w
- .= +w,.- : - , , .- a: ,v- 39 +
-e - wm , p , m w m.,, .~:- w- -
.s. s s.n . ;w n u
- , i 1
/ 12.0 CONTROL OF MEASURING-AND TEST EQUIPMENT 12.1 GENERAL ~ REQUIREMENTS The NUQAP provides-measures for the control of measuring and testing equipment (M&TE) .used as the basis' for acceptance :in activities affecting quality during inspection, testing and measurement off Category Ifmaterial, equipment and parts. Periodic calibration and-adjustment of measuring and test equipment is performed and controlled to assure accuracy is maintained within limits necessary to verify
'that design and operating condition requirements have been met.
Documentation is retained such that all items of M&TE are traceable to their calibration records.
12.2-IMPLEMENTATION 12.2.1 During the preoperational testing and the in-service phase' of nuclear power plants, approved procedures delineate the methods and responsibilities for: the . cont'rol, maintenance '
and calibration of M&TE, (including portable and installed instruments, tools, gages,-fixtures, reference and transfer standards, a'd n nondestructive test equipment).
All documentation associated with M&TE.is maintained in..
appropriate files, with eventual incorporation into the NU
. Nuclear Records Organization.
During NUSCO-directed activities of: an in-service nuclear plant, the NUSCO-calibration program is implemented in:
accordance with the requirements defined in NUSCO Procedures.
NUSCO Betterment Construction, Group is responsible. fort implementing these procedures which comply with the requirements contained in specifications-and dr'awings.
NUSCO Construction Quality Control is. responsible for -
verifying that receipt of calibrated. equipment is in conformance with the requirements of procurement: documents, .
and to control calibrated M&TE used.during'their inspections.
During the operations activities, the_ calibration program-g is implemented in accordance,with'theirequirements defined in NUPOC Procedures. The Site / Plant Operations ~ Review Committee (SORC/PORC) reviews and approves pro'cedures related to the calibration program. Department heads are responsible to. ensure that M&TE~~ equipment is. calibrated, issued,1and controlled in accordance with the: requirements 1 of the procedures. Department Heads are responsible for calibrating M&TE within the required' frequency and'for-reviewing calibration data associated;with M&TE calibration by outside vendors 11n accordance_with the procedures.
1 0 'QAP 12.0
- AIJG' 0 9 20$
Page 1:of 3
'L m
s GJ *; w wmm p - , a
- gas' . - *
'. r ye.u d m y y. w . g x w 7 :.n ip w .t n a r -- .
1 1
[ NUSCO/NUPOC Quality . Assurances performs audits / inspections /
< surveillances to verify implementation of the calibration programs.
The engineer-constructor, contractors,; suppliers-and-engineering' service organizations utilized by NUSC0/NUPOC, during the design, construction,' operation, maintenance- '
and modification of nuclear power plants, as- appropriate,-
J are responsible for implementing measures for the: control of M&TE to . ensure they .are properly calibrated, adjusted and maintained at specified intervals,in order to' maintain accuracy within. required limits. NUSCO/NUPOC Quality Assurance performs on-site and off-site audits /surveillan-ces/ inspections of-the quality assur'ance: programs of the' engineer-constructor,~ contractors, suppliers and engineering.
service organizations to verify they are effectively .
complying with their requirements for control .of M&TE.
12.2.2 Calibration Standards Measuring and test equipment is calibrated at specified
~
' l intervals based on the required accuracy, purpose,- degree of usage, stability characteristics, and other conditions-
~f affecting the measurement. Measuring and test' equipment l-j shall be labeled or tagged to indicate the date calibrated.
- and next calibration date.
NUSCO/NUPOC Procedures describe the measures taken to assure that reference and transfer standards are traceable
- to nationally recognized standards.and~that, where national standards do not exist, provisions are established to*
document the basis for calibration.
- Calibration of this equipment;should be against standards that have an accuracy of.at.least'four times the required
- accuracy of'the equipment being calibrated. When-this is; ,
- not possible,- the standards -shall have ,an. accuracy' that assures the equipment being, calibrated will
- be within?
. required tolerance and: the basis of; acceptance is . documented- l and authorized-by the System-Superintendent Betterment ,
l Construction (for NUSCO-directed activities)Jor the' SCRC/PORC'(for NUPOC-directed. activities). - In addition, t the calibrating standards shall have greater accuracy than.
secondary standards being ' calibrated. . : Calibrating standards" J with the same accuracy may;be used'if.they can be shown to~ .
be adequate for the requirements iand the basis'of ' acceptance :
is documented and authorized by.the System. Superintendent; -,
Betterment Construction or PORC/SORC.
1 l
iQAP/12 0
-Rev.: 7 lDate:f j3'O[j Tfj;;
m
'Page 2- of .3
.. .~ . - , ,
~
l o .
. ... . . . . , , , .-._,s... .. - .a. ,.,c.., , , , - . ,, ~ _ . ,
{3,yC.<
- VlQ:Q!29iMW2&h . l2.'22:'?M!RWLG%;u , af sn q'; 7ya ;mwww:rg7u;s',4:.13. 7.% - ni '
s r
' Implementing procedures. describe.the measures uti1ized in.
order?to maintain the proficiency of'the measuring and- ...
l ' test. equipment. ~l 1 12.2.3 "Out of Tolerance" Control -
M&TE and reference standardsi.when found out of tolerance.
- - are-so' identified and removed.from service. .A review is- .
conducted to determine the validity of previous inspection cr test results gained through;use-of~the' instrument, and -
' of the acceptability of items previously measured or
! - tested.-
e d
a: ,
3 1
l I
4 3 f .
i 1
I 2.
4
?
1 i
i e
7 ..
t i
k i- , ,
I
! '. I 4
i
~
.i j i QAP 12.0' :- -
- Rev.: 7. '. f. . ;
l Date:'-
- Page.3.of=3
-e--- - .a e .--,e,,-.- , n -
y c., nvu o., g ..w . e , m.,, 4, ,, , , e - g ;, - -,y.7p , ,- ,s-n. . , ,,n,A y + 4_,_4 ,.,,,yy,, , , , , ,
mgy..m :y < m + sw:.g.yzg;: mm W w. ex y k c y :-r u, w p e +.-<
- s % x 13.0 HANDLING, STORAGE AND SHIPPING '
( J-13.1 GENERAL REQUIREMENTS Measures are established by the NUQAP using approved ; procedures, instructions and procurement. documents to ensure. proper handling, storage, shipping, cleaning and preservation of Category I material, equipment and parts. .These measures _are imposed during the design, procurement, construction, preoperational testing and operation of nuclear power plants and major modifications _thereto, in order to ~
preclude damage, loss or deterioration of material, equipment and parts. ,
1 13.2 IMPLEMENTAT.10N l 13.2.1 General Procedures, instructions and procurement documents define :
.the requirements and responsibilities for the handling, storage, shipment, cleaning and preservation of Category I material, equipment and parts, and required implementation -l of established design and specification requirements.
During design and construction the responsibilities associated with handling, storage, shipment, cleaning and g--)g
( preservation of Category ~ I-material, equipment 'and parts may be delegated to the engineer-constructor, contractors, suppliers and engineering service organizations. These organizations are monitored through audits / surveil-lances / inspections by NUSC0/NUPOC' Quality _ Assurance to verify compliance with their quality assurance program
. requirements for handling,. shipping,Ecleaning and preser ' l vaticn.
. . .l Handling, storage, cleaning ano preservation requirements !
of material, equipment and parts is conducted in accor- .l dance with written procedures and: procurement documents j during the preoperational testing and the in-service phase- "
nuclear power plants. The Nuclear Plant Operating Compan-ies may utilize contractors, suppliers,-and engineer-ing service organizations, during the . operation, mainte -
nance and modification of-the in-service nuclear power !
plant. These organizations are responsible for implement- !
ing measures for handling,. storage, shipping, cleaning and . !
preserving Category I material, equipment and parts to _j preclude damage, loss or deterioration. NUSC0/NUPOC 1 Quality Assurance performs audits /surv'eillances/ inspections to verify that NUPOC, contractors, suppliers and .
engineering service organizations are effectively imple-1 l menting and complying with their_ approved procedures and 1
()
QAP 13.0-l
.Rev.: 7 ,
4
'Date: AUG0gJCr5; 2 Page 1 of 2 i
e
.:pc4.;p;w; + :1.mw,
- v - e
- n ~m. =nwn. ,cwqzvngnprggg2+cga.q;.y-4.;um, , ;.;; , :.m . ; w;,;w 9 f /m \ ~ instructions for handling, storage, shipping, cleaning and-I _sk s . preservation'of Category I material, equipment and parts.
2
._13.2.2 Establishment of Special Handling, Storage,- Shipping,
-Cleaning-and Preservation Requirements Special or additional handling, storage, shipping, clean-ing and preservation requirements are to be identified and implemented as.specified infproc.urement documents and.
approved procedures. .These established requirements are consistent with- the regulatory positions of :the NRC Regulatory. Guides and_their endorsed ANSI' Standards, listed in Appendix D of the NUQAP Topical Report, or specifications 1and/or suppliers technical manual, and will be consistent with accepted industry standards.
NUPOC Procedures describe the measures taken for.the storage of chemicals,-reagents (including control-of, shelf-life), lubricants, and other consumable materials.
J 4
9 d
l
("~\
V 'QAP.13.0
.Rev.: 7 Date:f [ 'i ; ^...i. ,
Page 2 off2
- nGWTCWWWW4M?M%*:M 5 " , :f;e - w. '
y WW?ny ?.L%W4w f = / w M m W q &F
. ,j 3l w
14.0 INSPECTION,= TEST'AND' OPERATING STATUS
--14.1' GENERAL REQUIREMENTS The NUQAP provides measures for indication, _by.khe use of marking l .
such as' stamps, tags, labels or other suitable means,: the status 'of tests and inspections .of . Category I material, equipment and parts? ,
throughout design, construction, preoperational testing, operation, maintenance and modification of nuclear power. plants,- to preclude -
the inadvertent bypassing of inspection and test. requirements.
These measures provide.for the identification of. items which have ~
satisfactorilyLpassed required inspections and tests. MeasuresJare: I also established fo'r. indicating the operating-status'of systems, structures and components to. prevent inadve'rtent-operation.
14.2 IMPLEMENTATION i
14.2.1 General The' engineer-constructor,.NUSCO/NUPOC contractors, sup- ,
pliers and engineering service organizations utilized by-7 NUSCO/NUPOC during design, construction, preoperational~
testing, operation, maintenance.and modification of' nuclear power -plants, as appropriate, are responsiblSl for e implementing- approved; measures for the: identification'of : -
inspection and test status ofLCategory?I materials, O- equipment and parts to preclude the. bypassing off requirei ments. NUSC0/NUPOC Qualityf Assurance performs on-site and :
off-site audits /surveillances/inspectionsJoffthe engineer -
constructor,' contractors', suppliers and engineering- ..
"t service organizations to verify that. they are effe,ctively -
complying with their requiresents for; identification of- ~
incpection and test status, in1 compliance with approved M procedures and instructions. .ElementsLofsthis system:
require that suppliers-and; contractors have a controlled ,
manufacturin'g and test. operation, in order'to: preclude cne inadvertent bypassing lof process finsp'ections or. tests,' and' ,
to. provide a'positiveLidentificatica,of: component status <
f) throughout all- phases of Lmanufacturing, testing;~ and : D
~
inspecting by neans of; tagging, routingjcards,astamping',
manufacturing or l test' reports,11abeling 'orL otherJappro :
~
priate methods. , ,
l Where NUSCO/NUPOC performs-receipt ~ inspections at;: nuclear;
-power plants,zthe NUSCO. Nuclear Pro.jectLEngineery(during
~
H plant construction)for the(NUPOC Quality Assurance ( _ _ '
-]
Supervisor /NUSCO Manager-Construction , Quality Control' (during:preoperational testing:phaseiand at in-service plants).-ensures that traceability lis maintained off
~
1 .
IQAP114.0 -
^
Rev.: :7 . .
VDate: AUG 0 91935$
< 1Pagejlfof'2) ;g ',
-; P . -
~ -
, .p::z
-tn. -
'%g > %)Ms.;4;M'.. . Ti', .Q:ciF,i:'n'y N ' ,' n % W W m :.q' m r y e c w W -~:'== w - - w cp e
I
- 1
'p
(,,) -
acceptable material,: equipment and' parts,'_to' indicate conformance to Purchase Order / Contract' requirements.
f 4
Nonconforming-material, equipment and parts are identified !
in accordance with QAP 15.0.
During tests and inspectionstof operating nuclear power plants;a status tagging system is, implemented, as per approved procedures and instructions, to prevent inadver-tent operations of Category I systems, structures and components.
NUSCO/NUPOC Procedures describe the measures.taken to i
control the altering of the sequence.,of required tests, I inspections and other operations taken during Betterment Construction / Operations.,'The review and approval for these actions is subject to the same contrcl as taken during'the original review and approval of tests, inspections and other operations.
1 14.2.2 Status Identification and Control Procedures and instructions describe control of the-application and removal of markings such as stamps, tags, labels and other suitable means to indicate the status of safety related systems, structures and components to S prevent inadvertent operation, and to preclude omission lof inspections, tests or other critical operations. These-l procedures and instructions delineate the requirements, methods and responsibilities for indicating the:statusf-of-the affected items. The complete status of all items under the calibration system is recorded-and maintained, u
Records associated with status = identification are main-tained in accordance with approved procedures.
i mb V t QAP.14.0 Rev;: ' Da te :fl.* ? ' ' ^ * ~, *,
. Page 2 of-2 g--r- p- * -
9-w'-'- w w w m-
'm iMy mwW=v . uw -b ' ;, c~= ~. -- '
' 3;,5 :. ,97 . -
j.q
-15.0 NONCONFORMING MATERIALS,' PARTS, COMPONENTS, OR SERVICES-15.1 General Requirements The NUQAP requires that documentation and control of nonconforming ~
material, ' parts, components, or services utilized in Category I systems, structures and components during design,. construction,.
preoperational testing, operation and maintenance of nuclear power plants and major modifications thereto, be performed in accordance with approved procedures in order to prevent inadvertent use or installation. These procedures include appropriate requirements for identification, docum.ntation, segregation and disposition of-nonconforming items, and notification to affected organizations. In accordance with procedures, nonconforming material, parts,_camponents, or services are reviewed and accepted, rejected, repaired or reworked.
15.2 Implementation 15.2.1 Program Approved procedures define the responsibilities and establish measures _ for identification, documentation, segregation, review and disposition of nonconforming materials, parts, components, or services, and notification
(
to affected organizations. .Each NU department is responsible
( for the identification, control and disposition of nonconformances within the , scope of their , departmental responsibilities.
NUSCO/NUPOC Quality Assurance performs on-site and off-site audits /surveillances/ inspections ' of the engineer-con-structor, contractors, suppliers and engineering.
service organizations to verify these organizations are effectively. complying with their quality assurance program requirements for documentation and control of nonconform--
ing material, parts, components, or. services.
15.2.2 Documenting and Controlling Nonconformances' Nonconformances of Category I systems,- structures - and components are documented and reported as requiring.
corrective action. Approved procedures delineate controls-required for further processing and installation of' nonconforming items. These controls include:
- a. Physical identification of the material,.part,
. component, or services as nonconforming; V'(N -
-QAP 15.0' 1Rev.: 7'
-Date:p,IJgQ0i9851
-Page.1 of 3
M ;.y p i g g.? , a.v ~.TVWW' 7 < +
- / r n
- . ;~
-.w w ,
7 . :6 4 x W j
- ' v b. Segregation of' nonconforming items or. services until ,
properly dispositioned. Where physical separation:
is not practical, suitable' tags, markings.and documentation are used'to assure control.
15.2.3 ' Documentation Documentatioc of-nonconforming items requires identifi-cation of the, items, description of;the nonconforn.ance, dispositior. of the nonconformance,; inspection requirements
-and'signskure approval' of the disposition. A trend'.
analysh of nonconformances is performed by NUSC0/NUPOC QA in accordance with approved procedures. ..The trend analysis results are periodically reported to.
the.NUSCO Manager Quality' Assurance and.then to upper management, including the Senior Vice President, Nuclear Engineering and Operations, for review and assessment.
An engineering evaluatia is performed, if necessary, prior to the resolution of nonconformances relating to Category I systems, structures a'nd components. ,
15.2.4 Evaluation and Disposition Evaluations are performed.to determine the disposition:of p)
(
nonconforming items and services. The evaluation determines whether an item or service is to be accepted as-is, returned to supplier, repaired, reworked, scrapped or salvaged. These:
evaluations assure that the : final condition does not adversely affect safety, operation or maintenance of the item or service, or of the component or system in which the item is -
installed or on which the service is performed. Applic--
able information is accumulated and records are maintained.
The engineer-constructor, contractors or NUSCO/NUPOC
~
personnel are required to report to ,the NUSCO' Project Engineer, NUSCO System Superintendent Betterment Construction, NUSCO Superintendent New Site _ Construction, NUSCO Nuclear.
Project Engineer or the appropriate NUPOC Superintendent,1 as applicable, to obtain release of-nonconforming item or.
service prior; to its installation or use. Thesecrelease items are identified by.a Nonconformance Tagging System -
which defines the description of-the nonconformance and.-its' nonconformance status.
9 Nonconformance:reportsdispositioned"acceptasis"[or
" repair" are forwarded to the NUSCO _ Nuclear- Project ~ .. ,
Engineer, NUSCO System Superintendent Betterment Construction, NbSCO Superintendent New-Site Construction, NUSCO Project Engineer,' or . the appropriate NUPOC ' Superintendent,; as .
applicable, and to NUSCO/NUPOC Quality Assurance for -
.QAP 15.0:
Rev.: 7-
'Date:/'IlO015,0.
IPage 2 of'3 Th
' m, ~ ma N - 7;. ;ru n n -
29& e ,,s -
m.u > m W.rg.:,:M tr::n.m . ms3 w ty;}
t I
+
) review and approval, and 'then made part of the materials
~ ~
receipt inspection records. ;In: addition, the status of-all safety-related materials, parts, or. components is-maintained by a system.of tags,' which is'administrati.ely controlled by the cognizant QA/QC Department'.
During NUSCO-directed. activities'of an in-service nuclear
- plant, NUSCO Generation Betterment Construction and.
2 NUSCO Construction Quality Control organizations are l' responsible!for' documenting the. status of nonconforming, inoperative, or malfunctioning structures, systems,.
components, and serviceslas described in NUSCO Procedures.
During - the operations activities of an in-service -nuclear.
plant, the ' status of nonconforming, inoperative, or-malfunctioning systems,Estructures.' components, and services:
is documented as-necessary by NUPOC Quality' Assurance / Quality Control and NUPOC Operations personnel as-described ini
! applicable NUPOC Procedures.
The need to release nonconforming material, parts or components shall be-based on-such considerations as: ,
- a. Impact on plant safety;-
- b. Safety of personnel;,
1
! c. Suitability-of material ~or items in the "as-is" j condition, i.e. , probability of eventual satisfactory.
resolution of the nonconformity without repair, rework or replacement;.
- d. Accessibility of: material or items after release;
- e. Ccst of removal and repair;or. replacement should
! material or items eventually have'toHbe removed, ,
repaired, or replaced; i
- f. Effect on the~ orderly. progress of work. <
l .
Items reworked or repaired in accordance with. procedures are verified by reinspecting the item as originally =
! inspected or by a documented' method which iss equivalent' to j the original inspection method.
] .
j ..
1
- t 1
1 i
4,
\~ / QAPT 15.0 Rev.: 7 .. .
-Date: AUG 0 01985. '
-Page:3.of 3' ;
,y - ,,; m- ~ .x s ; , . , mu7r m;~,:;w. m;:. < w 03.m:nsy w,y w:e ., m , . w.73,,m, .p i
'I
-g j 16.0 CORRECTIVE ACTION O
16.l' GENERAL REQUIREMENTS The NUQAP provides documented measures for-corrective action to-ensure that-nonconforming Category I systems, structures and components-are identified and promptly corrected. These measures shall include, -
as appropriate, procedures for identification, documentation, segregation, disposition, notification to affected organizations and follow-up to prevent recurrence. Nonconforming items shall be reviewed and accepted, rejected, -repaired or reworked in accordance -
with approved procedures. When conditions, adverse to quality, are identified through trend analysis, measures are taken to ensure-corrective action and to prevent recurrence.of the-problem.
16.2 IMPI.EMENTATION 16.2.1 Corrective Action and Follow-Up Evaluation of conditions adverse to quality such as,. .
nonconformances, failures, malfunctions, deficiencies, deviations, and defective material and equipment is conducted to determine the need for corrective action in-accordance with established procedures. NUSCO/NUPOC Procedures describe the measures taken to evaluate conditions' adverse to quality, to determine the need for corrective action, to document the evaluation, and to assure Quality Assurance concurrence with the adequacy of the corrective action. NUSCO/NUPOC Procedures also describe th.e measures taken to assure what follow-up action'is taken by NUSCO/NUPOC Quality Assurance to verify ' proper implementation and close out of cerrective action in a' timely manner.
Procedures describe the measures taken.by NUSCO/NUPOC Quality Assurance to review and' document concurrences with b-corrective action procedures established by applicable -
NUSCO/NUPOC departments.-
During design, construction, preoperational' testing and- ~
operation of nuclear power-plants, the engineer-construc-tor, contractors, suppliers, engineering. service organizations '
and their subtier contractors, (utilized by NUSC0/NUPOC),- ,
and NU personnel are responsible for informing the NUSCO ,
Senior Vice President Nuclear Engineering and Operations, -
through.their-respective organizational chains (of' command, 9 of significant conditions which are adverse to quality,.
the cause of-the condition and the corrective' action
.taken. NUSCO/NUPOC Quality Assurance or .NUSCO Construction -
Quality Control, as appropriate, idtntifies deficiencies-by audits /surveillances/ inspections of.the engineer-constructor's, L/
QAPLl6.0
. Rev.: 7 , . ,, .
Date:v,: n U J,_. ),
Page,liof 2. , . ,
~. . .
AJ$%I.7 %;p.ia;=;:::;57 g?+70 m p~ J~ p . + maxmig;pp;,e wmWmn , m:mp.hp f
contractor's, supplier's and engineering service organiza-:
. N- # . tion's quality Lassurance programs for ^ corrective action.
- A reaudit/ inspection / surveillance to. verify implementation of corrective action and close-out of corrective acti;n-documentation shall be. accomplished by the original:
auditing organization.
. NUSCO Quality Assurance performs audits-toLidentify.
deficiencies in departmental' corrective ' action programs. -
The appropriate NUSCO Department.Directo'r/ Branch Manager / Sectio.
supervisor or the appropriate NUPOC Superintendent, .is .
responsible to implement-timely corrective a'ction. -NUSC0f
~
Quality Assurance may reaudit the affected department to- _ .
verify corrective action has been'_ implemented and documented.
If corrective action is inadequate or not timely,~ the.
follow-up organization requests corrective action-from management as delineated in procedures. . The.NUSCO Senior Vice President Nuclear Engineering and Operations.has the final authority in. the event that' agreement is. not1 reached at lower levels. .
Wherecorrectiveacti'o[nisrequiredofcodtractor-per-sonnel, JUSC0/NUPOC defines =in procedures and contracts-the corrective action interface between:NUSCO/NUPOC and the contractor. NUSCO/NUPOC requires the engineer-con- '
structor, contractor, suppliers:and engineering service.
organizations, as appropriate, to have 1 ajdocumented= . ,
corrective action program for safety related materials 1and se rvices .
16.2.2 Recurrence Control The organization which'is responsible for tha condition adverre to quality, shall ensure that the' corrective action will not only correct- the immediate' condition, ' tut' also prevent the adverse condition from recurring.
NUSCO/NUP0C procedures establish.the, responsibilities and-measures taken to; identify trends of conditions,Ladverse-to quality, and to ensure that corrective action is taken' ~
for those conditions lto prevent their recurrence. A trend-analysis report; which identifies-the' conditions,-adverse
~
-to quality;-is1 issued.to appropriate-levels.of NU management.
The NUSCO Manager, Quality Assurance is responsible:for 1 follow-up of the trend analysis' items and their corrective action.
. Trends concerning specific contractor's performance'shall; '
- be reported to the raffected : contractor :for_. resolution and :
-corrective action to prevent;recurrencejofLthe problem.
~
a QAP16h0.
Rev.: ' 7.
4 Date:
- Page 2 of 2l --
a s
r
- g. A ^
- m. __
h-- _ ,
J.ex gwppgyEyvy.%tyggi;3yp-L;x re-w;nn amsg;;@gs .49;'TpWiegygg,,w;; gem , e e .t .
l( 17.0 QUALITY' ASSURANCE. RECORDS 17.1 GENERAL: REQUIREMENTS The NUQAP.provides for the maintena' ace, identification,-retention and retrieval of records to furnish evidence'of: activities affecting; quality during-design, construction, preoperationalitesting, operation, maintenance and modification of nuclear power plants. The records:
include but are not limited to: foperatingl logs and the;results of
~
reviews, inspections, _ tests, audits, monitoring of work performance and material analyses. 'The records also' include. closely related-data such as qualifications - of personnel, procedures - and equipment.'
Inspection and test records contain as a minimum but are not limited
~
to: identification of inspector or data . recorder. and the taccepta-bility and the action taken in connection with any deficiencies,_and Reportable 0ccurrences noted. Approved procedures establish requirements concerning record retention such as' duration, location and assigned responsibility.
17.2 IMPLEMENTATION .
NUSC0/NUPOC Procedures and InstructionsJestablish!the responsibilitiesL and requiremen's for the maintenance, identification, retention and --
retrievabilitt of records pertaining to the quality of material, g- g equipment, parts, processes or operations relating to Category I ;
systems, structures and components which when founded on observations,
( / measurements or tests can be fully! verified,7and documented by-cognizant personnel.
During design, construction, preoperational testing, operation,-
~
a maintenance and modification of. nucle'ra power plants the engineer- (
constructor, contractors, suppliers .and engineering service organizations, as appropriate, utilized by NUSC0/NUPOC are respon-sible to implement measures for identification, maintenance, _ reten . l tion, retrieval and turnover, to the NUSCO . Nuclear Project. Engineer /NUSCO Project Engineer / Cognizant NUPOC personnel ~,1of-documented ~and approved records which contain objective eviden'ce of quality,J as specified in Purchase Order / Contracts. NUSCO/.NUPOC-Quality .
Assurance performs on-site and off-site audits /surveillances/J ' '
inspections of the engineer-constructor,fcontractors, suppliers - q and engineering service organizations-, as? appropriate, _to_ verify _
they are ef fectively complying with: their program for ' quality '
assurance records.
During the preoperational testing and in-service phase of:nucleari
power plants NUSCO/NUPOC quality records are_ identified,fcontrolled and maintained in appropriate files and are identifiable to specific.
systems, structures and components within ' the .nuclearipower plant. I When identification to'a specific. system,~ structure or; component;is: j i
\ . .
QAP 17.0- .
Rev.: .7 Date: AUG 0SL1936-
- Page;1;of 2
~ :~Q:Bry? s.SW. 9,TQS%;l;M.%gg.;%;769.i%&&M MWW Ge%L.n %:;r+WW Y.,& ~.'+2v:n
> , m m
O M ,/
not. practical, records are. filed.by category;-(e.g. specification,;
nonconformance reports, audits, etc).
- 17.3 RETENTION NU Quality Assurance records:'are classified as life records;or-non'-life recordss as delineated by Generation Facilities. Records.
Non-life records are those quality documents-that are maintained for a specific. period of time other-than,the life time of the in-service nuclear power plant or. the particular . component or part. -Life records are those quality documentr. that are maintained ~for the-lifetime of the in-service nuclear:powerJ plant;or for -the life of the particular component or part. Life recordsJare those which- ~
i' would be.of significant value in meetingione'or morefof the following criteria:
- a. . Demonstrating capability for' safe operation;
- b. Maintaining, reworking,; repairing,' replacin'g or modifying; the item;
- c. Determining the cause of an ac'c'ident or malfunction o'f an
- item;
- d. Providing required base line data for in-service-inspec-tion.
O- Records are reviewed.and approved by the NUSCO Nuclear-Project _ .
Engineer,. Project Engineer or other cognizant! qualified personnel of NUSCO/NUPOC, engineer-constructor,.etc., as' appropriate,-and/are .
transmitted to the appropriate Nuclear Plant' Records Facility; The responsibility of the appropriate Nuclear Plant Records Facility i upon receipt of records, is.to maintain and provide control' led retrievability of records affecting the quality of nuclear power:
plants, in such a. manner as to prevent;destructionLof records by fire, flood, theft, and. environmental conditions,-such as.
tenperature or humidity, as delineated:in procedures.
t 7
0- QAP.17.0f lRev.: :7.
.Date: -
4'jg -2c Page'2,of Q ..f '.' v Y
___-._.___-_-____--_-_--__L._--____.=- _ - _ _ _ _ .- _ _ - . . - _ _ - - - , _ -3 - _ . - _ _ x - - . ~ . . . - _ . - - - _ _ _ . . - - . _ - . _ .
N qy.J M .<' er4 %cuppN; me u.#: reVto .yw:#cN.:y;r a m-
'j T 18.0 AUDITS-
\s /
18.1 GENERAL REQUIREMENTS The NUQAP requires that measures be provided to implement an effective audit program. These measures are applied during the design, construction, preoperational (esting and operation of nuclear power plants and major modifications thereto, through the performance of audits. Audits are conducted in accordance with preestablished procedures and written checklists by qualified personne1'not having.
direct responsibilities in the areas being audited to ensure compliance with the NUQAP Topical Report. The 'results of audit findings ' are-documented and then reviewed with management having responsibility in the area audited.
18.2 IMPLEMENTATION 18.2.1 Program The following audits relating to the NUQAP are performed: .
- a. NUSCO Internal Audits; (audits of the IE' criteria of Appendix B to 10CFR, Part 50:
(1) are conducted annually for design and construction
(]
. x,./
phase activities of new nuclear generating facilities, and (2) are completed within a pericd of two (2) years for operational phase activities.
- b. NUSCO/hUPOC Engineer-Constructor, Contractor, Sapplie'r, and Engineering Service Organization Audits; (as per-procurement documents) j
- c. NUSCO Construction Site Audits; (annually or as applicable by the procurement documents)
- d. Preoperational Testing Audits; (as per test schedule :)
and administered under the directi6a of the NUSCO l I
Ardit Program)
- e. Plant Audits; (audits of the '18 criteria of Appendix B 10CFR Part 50 are completed within a ' period of: two ,
' (2) years and _ are administered under the direction ;of ,
the NUSCO Audit Program) ,
R In addition, provisions are established to require that-audits be performed of those activities,where the requirements 7 ~g- '
k,. QAP.18.0
, Rev: 4. . .
Late: AUG Q 9 l38$_
._Page 1 of 4 t
~ ~ '; 52%%:ggithe ' v2!L 2 ~ mrm -i-at.%WWyr~+W wyn n: " - <m o +; y
,A-
'( $
of Appendix B to l'0 CFR, Part 50, are being implemented,
-~
and associated with:
- a. 'The determination of. site' features which affect plant safety (e.g., core' sampling, site and foundation preparation);
- b. The preparation, review, approval and control of-early procurements;
- c. Indoctrination and training programs;
- d. -Interface control among the lic,ensee and the principal contractors.
Measures are provided to perform audits of those safety-related activities performed during the operational phase.
Those areas are listed below:
- a. Operation, maintenance, and modifications;
- b. The preparation, review,' approval and control of design documents , ' specifications , . procurement docu-ments and instructions, procedures;and. drawings;
- c. Receiving and plant inspections;
- d. Indoctrination and training programs;
- e. The implementation of. operating and test procedures;
- f. Calibration of r easuring and ' test ' equipment.
Audits are scheduled on the basis _of the status and safety importance of the activities being. performed. Schedules are originated-and maintained by NUSCO. Quality Assurance.
Audits are performed as specified in procedures by qualified personnel using a preestablished written audit plan prepared by the auditing' organization. Auditors evaluate work areas, activities, processes, items; review documents and records to determine.the' effectiveness of implementation.
and conformance to the NUQAP. <
The engineer-constructor, contractors, suppliers and .
engineering service organizations utilized during the design, construction, preoperational testing and operation.
of nuclear power plants and major modifications thereto, are responsible for developing and implementing a system.
of planned and periodic audits to . verify compliance with .
and the ef fectiveness of all, aspects of their _ quality.
b- 'QAP 18.0 Rev: 7 , , , ,
Da te : k.. ; . .,.. . . ' !
Page 2 of_4'. -
WRWN{.? qui &WOM@%%WMMW't::WWoMGBM%? %!.k%~ & 5"' 'M ~
4{ '
?'
- E a
() assurance-programs? including ' reporting and resolution' of deficiencies. NUSCO/NUPOC Quality Assurance personnel. ,
perform on-site.and off-site audits /surveillances/inspec-tions to ensure these-organizations tare effectively.
1 complying with their quality-assurance ' requirements for- -
a'udits. .
. Departments withinLthe NUSCO/NUPOC organizations are U responsible for~ implementing quality related functions in-accordance with- approved procedures and : instructions.
' Internal . audits are performed '.to verify cimplementation ' o f
~
the requirements prescribed in the NUQAP; Topical Report; and' implementing departmental procedures. ,
18.2.2 Review of Au'it'd Findings ,
~
Audit results are documentsd.. reviewed, and analyzed withi management having responsibility in the area audited. :The. -
responsible management is. required to take the necessary?
action to correct the deficiencies revealed by the audit.
18.2.3-Reporting of Audit Results' Audit results are reviewed and approved by the-Manager, .
Quality Assurance / Designee. He is' responsible, based _on -
- the audit documentation',= - for issuing the audit reports _ to the appropriate management of,the area' audited and'fo'r
^ '
ensuring that timely corrective action.is taken to rectify deficiencies. In addition,. audit data and reports lare" accumulated for the' review and assessment of quality:
trends and the effectiveness of the Quality Assurance t Program. This report is then submitted to the~ Senior Vice" President, Nuclear Engineering'and Operations.
18.2.4 Resolution of Audit Deficien'cies i Appropriate action to resolve deficiencies identified during audits ,is to be taken' by. the cognizant engineer '
constructor, contractor,- supplier, engineering. service organization or internal management before the sc~eduled. n resolution date.- Follow-up1 audits are performed as necessary, to. verify appropriatefactions have'beenLtaken to resolve.' deficiencies.
~
Items which exceed;the~ scheduled'
- resolution date and.cannot be' resolved by affected management are submitted for resolution 'to the NUSCO SeniorLVice ' ,,
President NuclearLEngineeringjand Operations.
o
,, -QAP 18.0 -
~
J' Rev- 17 -
$Date:' AUG '0 9 1985'
_ _ iPage?3 of24 _
1 1
_ w y
~.;s i;o..: '.,Wi T.3:,,ap v:+ ,
- i: ~; e- ...
2;~ c' : W A -: r 6 .'. ,w, -vMirJm' - .x+ ;:s:: c c kee =
5 s
. 18.2.5 : Records / Reports'of Audits' .
Audit records,' reports and associated documentation pertinent to audits are maintained in the.appropriat.e:
NUSCO files with disposition to the appropriate Nuclear
-Plant ~ Records Facility, as:specified in procedures.
)
J 9
4 i
3 !
1
-1
-l 1
- I l
1
.1 i
a l l
QAP 18.0 ,
-i
~Rev: .7- ..
l s -
Date: NUI.C '.II
-Page-4 of 4-l 4
i e
.em + s +ew-m
~ \ W ,:- @ ,, .7 e;g 7, L . ,i - n:a;; W " %s%59 3::Jh.Mg.v m~:3.s mm : r =.'4
, , 'l
, 1
. f.y
( h- -
\- ^ APPENDIX.A CATEGORY I SYSTEMS,' STRUCTURES, AND COMPONENTS The . following systems, st'ructures and components of. a' nuclear power
, plant, including their foundations and, supports, are designated as.
Category I. The pertinent . quality assurance requirements of Appendix -B to 10 CFR Part 50, should be-applied, as'a minimum',' to.all quality.
related activities affecting the safety related function of these: systems, structures and components as listed -below and to other items and services--
specifically identified by NU in each FSAR/FDSA; addressing Section 3.2.1 of NRC Regulatory Juide 1.70.
(a) The reactor coolant pressure boundary.
(b) The reactor core and reactor vessel. internals.
(c) Systems or portions of systems' that are required for -(l) emergency core cooling; (2) post-accident containment heat removal or; (3) post-accident containment atmosphere cleanup (e.g., hydrogen removal '
system).
(d) Systems or portions of systems that.are' required for (1)l reactor-shutdown; (2) residual heat' removal or; (3): cooling the spent fuel..
storage pool.
(e) Those portions of the steam systems of-boiling water reactors extending from the outermost containment isolation . valve up tof but' not including the turbine stop valve, and connected piping of-2-1/2 inches or larger nominal pipe size up to and including the'first.
valve that is either normally closed or capable of automatic-closure during all modes of normal reactor operation.
(f) Those portions of 'the steam and feedwater systems of. pressurized water reactors extending from'and' including che. secondary side of-steam generators up to. and including the outermost containment 1 isolation valves, and connected' piping of'2-1/2.in"ch'es or larger nominal pipe size up to and including the-first' valve'(including an safety or relief valve) that. is either normally. closed or. capable of L automatic closure during all modes of. norcal reactor operation.
(g) Cooling water, component cooling and auxiliary'feedwater systems or.-
portions of these systems including the intake. structures, that are
- required for (1) emergency core cooling;i(2) post-accident; con-tainment heat removal; 2 (3) post-accident containment < atmosphere cleanup; (4) residual heatf removal. from the reactor 'or; -(5) cooling the spent fuel storage pool.
O V.
.. . QAP - Appendix A'
-Rev.: '7 Date: , -
- .Page-l'of.3
~
a ' v a
y m y:&p pyp :.t,5qm:ggzq grny,wg;ryp.y. n g; %.c ,sp.wny,3ny wnrgy rw. , p
.e {
a, (h) Cooling water and seal water systems ~.or' port' ions of these systems
' that.are required for functioning of -reactor-coolant system _ com-ponents important to safety, such as' reactor coolant pumps.
(i) Systems _or portions of systems that are required to supply; fuel.forf emergency-equipment.
(j) All electric.and mechanical. devices andl circuitry between the,
_ process and the input _ terminals _of .the actuator systems involved .in generating signals that initiate protective actuation _of; safeguard-systems.
(k) Systems or portions of systems that are required for.(1) monitoring
~
of systems important to safety a~nd; _(2) actuation of systems Limpor-tant to safety.
(1) The spent fuel storage pool structure, including the fuel. racks.
(m) The reactivity control system (e.g., control rods,rcontrol rod drives, and boron- injection system).
(n) The control roomi including its associated. equipment and all equip-ment needed to maintain the control room within safe habitability-limits for personnel and safe environacatal. limitsofor vital; equip-ment.
~
(c) Primary and secondary reactor containment.
(p) Systems other than radioactive waste. management. systems-nos covered !
by items (a) through (o) above which.contain or may;contain. radio s active materials and whose postulated failure would result in !
conservatively calculated potential offsite doses'(using meteorology as prescribed by Regulatory Guides 1.3 and 1.;4) which.are more.than-0.5 rem-to the whole body or its' equivalent"tofany~part of?the body.
(q) The Class IE electric systems, including,the auxiliary' systems'for o the onsite electric power supplies, that: provide the emergency electric power needed for functioning of plant. features' included in-items (a) through (p)'above, d
(r) Those portions of systems, structures or: components _whose; continued- !!
function is not required but' whose failureTeould . reduce the func-- ,
tioning of any plant: feature included in? items (a).through *q)labove=
to an unacceptable safety level-or.~ could result' in incapacitating : l injury to_ occupants-of the control room.should b'e designed ~.ind-
- q constructed so that the SSE would not cause such failures. H
, (s) Items and services associated with Radioactive Material-Transport
. Packages as described in.10CFR71. l
- QAP' Appendix A JRev.
- 7 tDate:'AUULO r198 F
. Page 2 of-3
_m__m.b_______. _m._._._I___._.
,;;;;.y.T-9y;;[9ll2;.gf.9yK+ : tj,4...
- t
- . msg.?l.e;s;.,;py
- W.+%;t = ;;?7x e
- ;W&:%y94)i~;:i9% ;g:4gm;q:gv+, e.x si s .- .
.: (L) . items and services associated wi th the preparat inn and.-
classification of radioactive wastes. for shipnient I n' a land disposa t- faciliLy or a 1icensed waste collector as' required.by.
10CFR 20.311(d)(3) and encompassing 10CFR'61.55 and 10CFR 61.56.
CONSUMABLES' The following specific consumables when utilized in. safety related .
systems;shall be. included in those portions of the NUQAP, as applicable.
- 1. Emergency generator. diesel fuels
- 2. Hydraulic snubber fluids
- 3. Reagents
- 4. Resins
- 5. Boric Acid
- 6. Lubricants e
QAP'- Appendix':A'
'Rev.: 7
- Da te : p, r j p, <<- -
Page 3 of 3
+ .
":F;;Gia?gsp;2 wtg?-y;;'-' ~y:. z-n.r n;e. :qq;= pq:gg, ;g;g,yn?;t.yW:a ' .'=wz tu i
1
. ,m APPENDIX B NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT QUALIFICATION AND EXPERIENCE' REQUIREMENTS NUSCO MANAGER, QUALITY ASSURANCE The NUSCO Manager, Quality Assurance shall satisfy the following. require-ments:
. Graduate of a four year accredited engineering or science college or university; plus twelve (12) or more years of industrial experience including three years in positions of leadership, such as. lead engineer, project engineer, audit team leader, etc. At,least two-years of this experience should be associated with nuclear Quality
- Assurance Activities. And at least one year of this experience is in a Quality Assurance Organization. A masters degree in engineering.
~
or business management is considered equivalent to two years' of experience. .
Note: The education and experience' requirements should not b'e treate'd as absolute when similar training or an outstanding record will -
provide reasonable assurance that a person can perform the-required tasks. .
e N
QAP.- Appendix B Rev.: 7 Dat'e:f,3, - -
Page'I of 1
^
~
ciQQIf,Jpf 4; W :1',;w ? W .% G N ,@ m 'wiPW _ W g %. W .9 W 75 2 79'JA 44TV ~(f N
\ APPENDIX-C 1 NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL' REPORT LIST OF TYPICAL QUALITY ASSURANCE RELATED PROCEDURES INDEX PAGES NUSCO QUALITY ASSURANCE BRANCH PROCEDURES 2-5 NUCLEAR ENGINEERING AND OPERATIONS POLICIES AND PROCEDURES. MANUAL 6-9 NUSCO GENERATION ENGINEERING AND CONSTRUCTION DIVISION PROCEDURES MANUAL 10 MILLSTONE LNIT 3 PROJECT PROCEDURES MANUAL 13-15 NUCLEAR PIJRT RECORDS MANUAL 16-18 ENGINEERING COMPUTER SERVICES DEPARTMENT PROCEDURES MANUAL 19 NUSCONUCLI:AROPERATIONSDEPARTMEhfTPROCEDURES 20 MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES 21-25 CONNECTICUT YANKEE QA PROCEDURES 26-29 NUSCO GENERATION CONSTRUCTION QUALITY CONTROL MANUAL 30 NORTHEAST UTILITIES WELDING MANUAL 31 NU PURCHASING BUSINESS PROCEDURES 32 NUSCO RELIABILITY ENGINEERING PROCEDURES MANUAL 33 REACTOR ENGINEERING BRANCH-PROCEDURES 34 GENERATION FACILITIES LICENSING BRANCH PROCEDURES 35 l
1 p .
U QAP - Appendix C q
Date: ,. . . )
Topical Rev.: -7.. ;
< c Page 1-of.35 .j
..j. j
y; =r.my.x.5 - _ _ .;; , ;; :gg:py;; e, , m; . m;;n y +..i5 p >g e:g g g;. v .: . v c; . .
p NUSCO QUALITY ASSURANCE BRANCH PROCEDURES r . .
V 10CFR50 APP. B CRITERIA NQA - PROCEDURES I. Organization NQA-1.01 . Quality Assurance Branch Organiza- ,
tion. l II. Quality Assurance Program NQA-1.02 Preparation, Issuance, and Con-trol of the Northeast Utilities Quality Assurance Program Topical Report.
NQA-1.05 NUSCO Quality Assurance Branch Indoctrination and Training Pro-gram.
NQA-1.07 Training and Qualification of NQA Lead Auditors & Surveyors.
NQA-1.08 Selection, Training, Qualifica-tion and Certification of NUSCO Non-NDE Inspection.and Testing
~ Personnel.
NQA-1.19 Preparation and Issuance of NUSCO Quality Assurance Branch Quarter-ly and Annual Activity Reports.
NQA-1.27 Quality Assurance Work Assignment System.
NQA-4.02 Preparation, Issuance anc Control of NUSCO Construction Quality As-surance Weekly Reports.
III. Design Control -
IV. Procurement Document Control NQA-2.03 Procurement Document Review.
NQA-2.05 Review of " Objective Evidence" Submitted by the Engineer - Con- ,
structor and NUSCO Contractors, Suppliers, and Engineering Ser-vice Organizations.
l V. Instruction, Pro- NQA-1.03 Preparation Issuance and' Control ;
cedures, & Drawings of NUSCO Quality-Assurance Branch j Procedures. l l
(%.~)\
QAP - Appendix C Date: AUG 0 01985 l Topical Rev.: 7' Page 2 of 35 l
i
gy' wqtc,g - teg.: +a ;+f. . r.1n?qu gggyspy " @g;We: . *
+v, 2 ~
N .
NUSCO QUALITY ASSL9tANCE BRANCH PROCEDURES i(-i 10CFR50: APP. B CRITERIA NQA - PROCEDURES NQA-1.10 Review of NUSCO/NUPOC Quality
, Documents.
g Is .
. Construction Quality Assurance NQA-4.05 Review and Approval of' Procedures For NUSCO Betterment Projects.
VI. Document Control NQA-1.20 , Issuance of'NUSCO Quality Assur-ance Correspondence /Comrinications.
NQA-1.28 Control of Safeguards Information.
NQA-2.02 ' Routing, Follewup, Review and Ap-proval of Engineer -' Constructor, NUSCO Contractor, and. Engineering Service Organization Quality Documents.
VII. Cor; trol of Purchased Material, Equipment',
and Services NQA-1.11 Supplier Evaluations. ,
4 NQA-1.12 Preparation, Issuante'and Co'ntrol of the NUSCO Quality Assurance Category 'I Contractor, Supplier, and. Engineering Service Organiza-tion' List. 1 i
NQA-1.13 Instructions for -Use of the NUSCO Quality' Assurance Supplier-Infor-mation Computer Program. I NQA-1.15 Review and- Approval of. the QA
~
Program /QA Surveys.'of NUSCO Sup- :l pliers.
NQA-1.26 Prepration, Issuance and Control of the NUSCO Commercial Commodity List.' ,
I
.VIII. Identification &
Control of Materials, j Parts, and Components ;
i l
.j QAP - Appendix'C Date:[M ','; , l h
. Topical-Rev.: 7- :q e :f, Page 3 of 35 _
.,,-,e -)
. j:. A
ff @ !59:f4i.R p W , M . ~. N e.-*;1 ii~u4 m"~ L e_ 4 - - a % <
~
NUSCO-QUALITY ASSURANCE BRANCH PROCEDURES mO
.(__/ -
10CFR50 APP. B CRITERIA NQA - PROCEDURES IX. Control of Special Processes NQA-1.09 Selection, Training, Qualifica ~
tion,:and Certification of NUSCO and NUPOC Nondestructive Examina-tion Personnel.
X. Inspection NQA-2.07' Preparation of Inspection Packages.
NQA-2.08 Conduct and' Reporting of NUSCO Quality Assurance' Inspections.
NQA-2.10 Performance, Reporting, and fol-lowup of Surveillance Activities.
XI. Test Control XII. Control of Measuring and Test Equipment XIII. Handling, Storage, and Shipping
\ XIV. Inspection, Test, and Operating Status XV. Nonconforming Materials ,
Parts, or Components NQA-1.17. Instructions.for-use of the NUSCO Quality' Assurance Branch Defici-ency Surveillance Computer Program.
NQA-1.18 Procedure to Stop Work.
NQA-1.33 Processing, Control and Follow-up-of Design Drawing'Nonconformance and -
Disposition Reports.
NQA-4.01 Review & Approval of Nonconfor-mances Dispositioned "Use-As-Is" and " Repair".
XVI. Corrective Action '~
1 1
'NQA-1.24 Commitment Follow Program. H NQA-3.01 Verification of Corrective Action Contained in Significant Defici-ency Reports Submitted'to:the NRC.
~QAP - Appendix C Date:AUG U 91985
. Topical Rev.: 7~
Page 4 of 35 L-
-5ggg;y -,
7,.
. ,; . , a --w .
< w- ; , ..
p.:. ,. . n.;,- w z. , x .. . x;; g
_ .x. ;.;..;p .,. ; a ,. 9 NUSCO' QUALITY [ ASSURANCE BRANCH PROCEDURES s
^
('J L .
10CFR50 APP. B CRITERIA- NQI - PROCEDURES XVII. Quality Assurance .
l~
Records. NQA-l'22 . Retention and Control.of Quality
' Records at the'NUSCO Quality Records Center at Berlin and at-the Nuclear Construction Site.
NQA-4.06 ' Review, Approval, a'nd Transmit tal-
~
of NUSCO Betterment Project.
Records.
XVIII. Audits NQA-1.14 ~ Conduct,' Reporting, and Followup of Audits.
NQA-1.16 Audit, Survey, and Inspection Com-puter Program.
NQA-2.09 Joint Audits.
NQA-4.03 Preparation of NUSCO Construction Quality Assurance Audit Checklists.
NQA-4.04 Id-Process Verification of Con-struction Activities l
f I
1 r
-f s
O 'QAP - A endix C'
~
Dat'e:[.' T 0 9 Is ,;, .
. Topical Rev.. 7 Page 5 ~of 35 P
t-
n.. q;m q.:ct n v-g ;py y ::.pu;pe m ;.=ys ~ ~ w c ..n - . .- :=
. , - ., r -,;
INUCLEAR ENGINEERING AND OPERATIONS.
. ~ POLICIES'AND' PROCEDURES MANUAL-10CFR50 APP. B s CRITERIA NEO - PROCEDURES:
'I. Organization NEO-1.01/-Organization of;the Nuclear
. Engineering-and Operations Group.
NE0-2.02 ' Charter for Nuclear Review ~
Boards.
II. Quality Assurance . .
Program NE0-1.02 . Scope;and Function of Nuclear Engineering and Operations' Poli-~
- cies and Procedures-Manual.
NEO-1.07 . Review of NE0' Procedures'as
- Required by Revisions to Northeast Utilities-Quality Assurance-Program Topical Report.
NEO-2.03 Nuclear Training NE0-2.06 Operating Experience Assessment and Utilization.
O ~
NEO-2.08 - Management Review of The Northeast.
~ Utilities Quality Assurance' j Program.
NEO-2.14 Nuclear Plant Fire Protection.
Program. 1 NEO-3.08 Processing = Proposed' Revisions to.
the' Northeast Utilities Quality
, Assurance Program Topical Report.
NE0-7.01- Construction Implementation of Operating Pl~nt a Modifications.
~NEO-7.02 Turnover of . Systems, Compene nts',
and-Structures.
~
III. Design Control .NEO-3.03' Preparation,:. Review and Disposi-
' tion of Plant Design Change Re-
. quests -'(PDCR's) .
-NEO-3.04 Preparation,. Issuance, and' Control of Project Assignments.
'NEO-3.12 Safety evaluations.
QAP.- Apgendix C
'Date: AUu 0 3.1985
- Topical-Rev.: '7
- Page 6 of 35, 3
M 'i 7 7:2WMACW7.Lii.;G@;2?n -?WO:+t"e.-o W WWla:: R W z w M 'O-Tr. w ' *
- r f
NUCLEAR ENGINEERING'AND OPERATIONS POLICIES AND PROCEDURES MANUAL-3, ,_
N ,%)' _ _ _ .
10CFR50. APP. B CRITERIA: 'NEO - PROCEDURES NEO-5.04LPreparation,. Review,LApproval, .
Revision, and Control.of Specifications.
NE0-5.05 De's ign Inputs and Design. Verificatiom NE0-5.06 Preparation, Review, Approval of.
Design Analyses and Calculations.
NE0-5.07 . Quality Related Computer Program -
Verification, Validation, and-Documentation.
NE0-5.08 Quality Assurance Requirements for Quality Related Software, NE0-5.11 Design Change Notices 'for Design- -
Documents.
NE0-5.12 Performance of' Fire Protection Reviews.
\~- NEO-6.01 Material, Equipment,.and' Parts.
Lists for In-Service Nuclear Generation Facilities.
IV. Procurement Document Control NE0-6.02 Preparation and Review of Quality l~
Related Purchase Requsitions.
NE0-6.04 ~ Review of Proposals.
V. Instructions, Pro-cedures & Drawings NE0-1.03 Format and Content of Nuclear En-- .
gineering and Operations'Proce -
dures.
NE0-1.04' Preparation, Issuance'and Control-of Nuclear' Engineering ' and Opera-tions Procedures.
NE0-3.10 Preparation and Processing of--
Proposed Revisions to In-Service.
Inspection. Manuals.
l VI. Document Control NE0-1.05 Documentation of . Telephone ,
Conversations. l
(~' +
v QAP - Appendix C LDate: 0'.,'T 0j} ff"'I '
Topical Rev.: 7:
Page 7 of 35 l
mW:m , , c:r ~ r =;- < :q fr-a.:mi., .. +wxva :: c.
- ~~ ~u m.ww am.n%: ~e:no:e m~www
. NUCLEAR ENGINEERING AND OPERATIONS-
-s POLICIES-AND PROCEDURES MANUAL
. Lf . . .
10CFR50 APP. 8 CRITERIA NEO - PROCEDURES NE0-1.06 Documentation of Meetings.
NE0-4.01 Correspondence withithe Nuclear- ~l Regulatory Commission.
NEO-4.02 Proposed Technical Specification Change Requests.
NE0-4.03 Changes and Updates to Final Safety Analysis Reports for Operating Nuclear Power Plants.
NEO-4.04 Proposed License Amendment Requests and Proposed Licensee Action Approval Requests.
NE0-5.03 -Controlled Distribution of Design Documents.
VII. Control of Purchased O
Material, Equipment, .
and Services NEO-2.11 Trend analysis.from Quality.
Related Documents.
NE0-6.03 Transfer of Material, Equipment l and Parts.
VIII. Identification &-
Control of Materials, Parts and Components IX. Control of Special . .
Processes -
NEO-3.09 Certification of Non-Destructive Testing Personnel.
NE0-3.11 Preparation, Qualification, Approval and Revision of Northeast Utilities Nondestructive Examina -
tion Procedures.
X. Inspe'ction NEO-2.07 Management of In-Service Inspec-
- tion Programs.
XI. . Test Control NEO-7.03 Preoperational Testing of. Plant Modifications.
O -QAP-ppgendixC- ~
Date: Muu 0 91985
. Topical Rev.: 7 Page 8 of 35
w u r y 7== =.-7 ny .q;q.w .mm.ymym.wgg.ns.n.:
. m e. +cw; m. . . w p.- -- = - ~ c
. . NUCLEAR ENGINEERING AND OPERATIO'S.N POLICIES-AND PROCEDURES-MANUAL-1 _,
10CFR50 APP.-B CRITERIA -NEO - PROCEDURES XII. Control of Measuring .
and Test Equipment XIII. Handling, Storage, and Shipping P
XIV.' Inspection, Test, and' NEO-8.01 Jumper, Lif t;ed Lead-,andlBypass-Operating Status Control.
XV. Nonconforming Materials, NEO-2.01 Implementation of the Parts, or Components. -Requirements'of Part 21 of.
Title 10,~ Code of Federal Regulations: Reporting of Defects and Noncompliance.
XVI. Corrective Action NEO-2.09 - Computer Tracking Program.
NEO-2.18 Corrective Action. l NEO-3.07 Resolut. ion of Audit Findings.
XVII. Quality Assurance-Records NEO-2.10 Safeguarding of Supplier Proprie-tary. Material. l NEO-2.12 ' Control of Nuclear Facilities-Safeguards Information.
NE0-2.13 Managment of, Nuclear Power Plant Records.
XVIII. Audits NEO-2.16 Quality Assurance Plan,t Audit Program.
NE0-3.01 Conduct and Format 'of Nuclear Review Board Audits.
.i J
l l
( '
QAP;- Appendix'C Date:;A,fJQ()yyrr-Topical Rev.: '7 Page<9 of 35T U
v.,.m gw - -
.nr., - . := m. , w;,r: w,w
+
- , m .- .. :. .. ~ . m . w 4
-NUSCO GENERATION' ENGINEERING AND CONSTRUCTION DIVISION PROCEDURES MANUAL
/{
.10CFR50 APP.:B
~ CRITERIA GE&C'-UPROCEDURES
'I. Organization GE&C-1.01 Generation Engineering ~and Construction Division. ci II. Quality Assurance
. Program -GE&C-1.02. Applicability.and Use of Gen' era-tion Engineering and: Construction Procedures Manual.
GE&C-l'.03 Procedure fo'r : Review of c Genera-
. tion Engineering and_ Construction Division Procedures as Required by Revisions to. NU QA Topical:
Report.
GE&C-1.05 Generation Engineering.and '
Construction Procedures _ Training-Program.
III. Design Control GE&C-2.01 Preparation,. Review, Approval, Revision, and, Control.of NUSCO O Generation Engineering _and Construction Division Specifications.
~
GE&C-4.02 Review of. Engineering Service Or-ganization, Supplier, and Engineer Constructor Design Documents.
l.
GE&C-4.06 Materials List.
l; IV. Procurement Document Control GE&C-2.06 Purchase of Materials List , Equip-ment.
V. Instructions, Pro- GE&C-1.04 Preparation,. Issuance and Control cedures, & Drawings of Generation _ Engineering and i Construction Division Procedures.
GE&C-2.07 Preparation, Issuance and' Control' of Project Descriptions. ,
GE&C-3.01 -Design Information. ;
GE&C-3.05 Preparation-and Control of Design 1
' Drawings. .
s QAPL- Appendix'C.
_Date: AUG. 0 9.1035' Topical Rev.: 7 Page 10 of r a.
WWMpqficQ W@%e %-aQ.ep,#M % 'iM+M!7fyrO33Sgg g@ W q q:4%g ; ,
% .ry- ;py m s , ~
NUSCO GENERATION ENGINEERING AND CONSTRUCTION' A l
. DIVISION PROCEDURES MANUAL
\
G ~ . _ _ _
10CFR50 APP. B .
CRITERIA 'GE&C - PROCEDURES GE&C-3.06 Preparation, Rehiew'and Approval.
of Drawing'Chan'ge Requests (DCR)
Jand Drawing Submittal Requests 1(DSR) for In-Service Nucleare Plants.
GE&C-3.07 Processing ^ and Control of Drawing - .,
- Change Requests;and~ Drawing Sub-
' mittal Requests-by Generation-En-gineering Design.
GE&C-5.01 Processing, Documenting, and-Filing of Results of the Review-of. Contractor Procedures.
GE&C-5.08 Preparation,-Issuance, and Control of NUSCO Betterment Construction Work /Special and.
Administrative Work Procedures?
() GE&C-5.09 Preparation,-Issuance, and' Control of NUSCO Betterment-Construction Special:Instruc-tions/ Requirement Sheets.
~
VI. Document Control GE&C-3.04 Des'ign Document Summary Log.
GE&C-5.10 Preparation, Issuance and Control
'of NUSCO. Betterment Construction' Project Documents List.
VII. Control of Purchased "
Material, Equipment, .
and Services GE&C-2.02 ReviewL of ' Proposals Submitted by Engineering Service Organizations, Suppliers,' Vendors,1and Contractors..
VIII. Identification and Control of Materials ,
Parts & Components IX. Control of Special GE&C-5.03 ' Control. of Special Processes.
Processes ,
X.
Inspection >
s.
m QAPL -' Appendix C.
Date:5..:,';]f.
-. Topical Rev.:! -
PageL11 of:35.
,y J
y: a;c9:5 :;nn , .;+7(f.zyma ; 't *; cp.Y aws:W:e , Hv&v;?;:,m=-n ~. - .+. wp NUSCO GENERATION ENGINEERING AND CONSTRUCTION DIVISION PROCEDURES MANUAL 10CFR50 APP. B' CRITERIA GE&C - PROCEDURES t
XI. Test Control .i XII. Control of Measuring. GE&C-5.04 Measuring.and Test Equipment'
& Test Equipment Control Program. ,
XIII. Handling, Storage,.
and Shipping GE&C-5.02 Control, Inspection, Handling, Storage, Receiving of-Purchased Material,. Equipment, and: Parts. .r XIV. Inspection,_ Test, and Operating Status -
XV. Nonconforming GE&C-5.05' Issuance.of a Stop Work Order. '[
Materials, Parts, . .
or Components GE&C-5.06 Installation of Nonconforming ;
Material, Equipment, Land Parts.-
i GE&C-5.07 Processing Nonconformance Reports.
XVI. Corrective Action XVII. Quality Assurance i Records GE&C-2.05 Retention, Control and Final' !
Disposition of Project Document .
- Files for Betterment. Projects . ;
XVIII. Audits ,
i
(
t I
f i
l
- f. ,
.QAPf. Appendix C' j
.Date: AUG 0 91985 Topical Rev.: <7 .
Page '12 of -35 ,
i
^
, \
.n!;M;:&M):,.= g5 .+ ' :y: q; ',' .: w =-
- '*L ' .J
- c+ :'V wn; *: '
~*:',
1 -
MILLSTONE UNIT 'l PROJECT
- PROCEDURES MANUAL' n
)
10CFR50 APP. B
- CRITERIA - MP3 - PROCEDURES _
I. Organization MP3-1.01 . Millstone Unit 3 Project.
II. Quality Assurance .
Program MP3-1.02 Applicability and Use of Millstone-Unit 3 Project Procedures Manual.
MP3-1.03 ' Procedure for Review of Millstone Unit 3. Project Procedures as required by. revisions to NUQAP' Topical Report.
MP3-1.05 Millstone Unit No. 3 Project Procedures Training Program.
III. Design Control MP3-3.01 = Preparation, Approval, Distribu-tion and Control of Category I' -
System, Structure and~ Component' List.
l
! MP3-4.12 Project Change Control. .
MP3-6.06 Basic Design Input. Documents.
~
4 MP3-6.08 Design Inputs and Design Verification.
3- IV. Procurement Document '
Control 4
MP3-6.02 Approval of Engineer-Constructor
! Purchase Orders for Non-Permanent Plant Materials, Equipment and Services.
V. Instructions, Pro- MP3-1.04 Preparation, Issuance and Control cedures, and Drawings of Millstone Unit 3 Project Procedures.
VI. Document Control MP3-4.01.. Processing,, Documenting and Filing of Results of Construction Procedure Review.
f
- u -QAP - A di
.Date:A 0 5 I Topical Rev.: 7
' Page 13'of.35
- - - , e w; p; ;.;u , , . . , :w ;a . ,
yx. t :: -
- c. gas.g.: z gg.;y-;;.y -
aa > .
., m MILLSTONE UNIT 3 PROJECT-
-. PROCEDURES MANUAL O - 10CFR50 . APP. B CRITERIA MP3 - PROCEDURES VII. Control of Purchased-
- Material, Equipment,'
and Services MP3-4.03 Control of Purchased Material, Equipment and Services' New Con- .
struction.
MP3-4.13 Receipt Inspection of NUSCO Procured Material.
VIII.' Identification and Control of Materials Parts and Components IX. Control of Special Processes MP3-4.04 Control of Special Processes. ,
l X. Inspection XI. Test Control XII'. Control of Measuring and Test Equipment XIII. Handling, Storage
- and Shipping XIV. Inspection, Test and Operating Status XV. Nonconforming Materials, Parts & .
~
Components MP3-4.08. Identification and Disposition of--
Deficiencies Identified During.-
- Construction and Installation.
MP3-4.09 Documenting land Reporting Significant-Deficiencies.
MP3-4.10' Installation of Nonco forming n . .
. Material, Equipment,& Parts.
MP3-4.11 Review and Approval of Nonconfor-mances Dispositioned_" Accept As Is and " Repair" l XVI. Corrective Action '
O *
'QAP - A) endix C, Date: A G 0 9 M85
, Topical Rev.: 7 Page 14 ofj35
- 3. -;g. an.3;,a.;,::9
- . ; _3., 9, . , ,yg , , q ;.g 7,c , ; ;;g,p g ,;;; g.g;z. y m :.y -x,g ,.> p.p;. ,n s : ,g.
4 t
MILLSTONE' UNIT 3 PROJECT.
-PROCEDURES MANUAL 10CFR50 APP. B-CRITERIA' '
MP3 - PROCEDURES XVII. Quality Assurance . .
. Record's - MP3-2.03 Retention &' Control of. Quality Working Documents in the Project
. File in Berlin and Plant Site.
XVIII.' Audits t
- t QAP - A ? pendix C
.Date: A JG:0 91985
_. Topical Rev.: . 7
,Page 15'of 35 N.-*--- .-- -_----_._----__-_L. ----.-_..-----.__----__.-_._.------.-_-aN.------.-_---__ - - - - u- - . - n
( W6.'l:: Wf;:;n-:k'.%,.. !" e'%' ;%v:;'y 2yF~'< % ~ 'e ' fM.A,jsqQ +:?,y-4;a:.;xt '** .A:. - ~ + ' %;< .
N v
NUCLEAR PLANT RECORDS MANUAL
'i
- 10CFR50 APP. B CRITERIA' NPRM - PROCEDURES: __.
i I. Orgsnization NPRM-1.01 Responsibility. Guidelines for.
Nuclear Plant Records Facilities ,
Located _at Nuclear Power Stations.
NPRM-1.07 Nuclear Records Section and-I -
- Responsibilities.
II. . Quality Assurance Program NPRM-6.01 Training Requirements.
- V. Instructions Proce- NPRM-1.02 Issuing of the Nuclear Plant cedures, and Drawings Records Manual.
NPRM-1.04 Preparation of Nuclear Plant-
- Records Manual.
VI. Document Control NPRM-1.03 Document Review and Acknowledge-- _l ment.
NPRM-2.02- Maintaining Nuclear Plant Records '
Vendor and Manufacturer File'.
I f NPRM-2.03 Maintenance of Nuclear Plant Records Backup Index.
4 NPRM-2.04 Quality. Checking of Record-
+
I Indexing.
1 NPRM-3.01 NUPOC/NUSCO Drawing Control System.
a NPRM-3.06 Request for Nuclear. Plant Drawing j
or Aperture Card Copies.
NPRM-3.09 Maintenance of. Backup to_the Drawing Status Files.
NPRM-3.10 NUSCO NPRF's Function in. Implementing the NUPOC/NUSCO Drawing Control" System.
XVII. Quality Assurance Records NPRM-1.05 Establishing Submittal Schedules.
for Transfer of Nuclear Records '
Into Nuclear Records Facilities.
1 2
-QAP - Appendix C- l i
l 'Date: AUG 0 01985 Topical Rev.: 7 ,
' Page 16 of' 35 i 4 ,
.q. :pp=; 7;;+;;g cy;,,fgu;mn:e s.+s:;rwx y.ppu :spq,r:.rp p pg. p 3gi.:.;3 a-:
. NUCLEAR--PLANT-RECORDS MANUAL I
'\
10CFR50 APP. B CRITERIA NPRM - PROCEDURES ___
NPRM-1.06 Nuclear Power Plant Quality Assurance Records Generated Collected and/or Transmitted by
~ External Organizations.
NPRM-1.08 Retention -and Control of Quality
. Assurance Records Generateduin-Support of the Nuclear Plant =
Records System.
NPRM-2.01 16MM Roll Film Microfilming Procedure.
NPRM-2.05 Inspection of Permanent Storage Vaults for Temperature, Humidity,-
l and General Condition. .
- NPRM-2.06. Inspection of the Physical.Condi-tion of Nuclear Plant Documents.
of Record Stored Within Nuclear i
Records Vaults, i
4 l NPRM-2.07 Storage of Radiographs and Photo-graphic Materials Other Than Mi-
.crofilm..
NPRM-2.08 Use of Updateable Microfiche Sys-tems.
l NPRM-3.08 35MM Aperature Card Microfilming 3
Procedure Using the 3M 2000E ,
Camera.
NPRM-4.01 Housecleaning Guidelines for Records.
I NPRM-4.02 Transmittal / Receipt of Nuclear t Records.
NPRM-4.03 Access to -Nuclear Plant Records -
1 i Facilities and Records.
NPRM-4.04 Disposition of Nuclear Plant a Records.
QAP - Appendix C.
Date: [ T U ',l pv Topical.Rev.: -7 Page'17 of 35
~yy7,;(s3.;(v +~n; ..;,gpvy.;g.l 3;473,,z;;(yyg,g.;.pyggpg.;. .
, y;.;g .y; ,;. .
- . - . ,y NUCLEAR PLANT RECORDS-MANUAL
[ \
N _.
10CFR50. APP. B CRITERIA NPRM - PROCEDURES __
NPRM-4.05 Checklist of Required Nuclear Power. Plant Records Including Quality Assurance Records.
NPRM-4.06 Descriptions of Nuclear Plant 1
-Records. Storage. Vaults.
NPRM-4.07 Guide for Writing Implements and ,
' Paper Stock to be used for Docu-ments Intended for Microfilming.
NPRM-4.08 Proprietary / Confidential Record ~
Control.
NPRM-4.09 Assignment of Source. Record Storage Locations to Nuclear .
Records NPR Computer File Entries.
NPRM-5.01 Nuclear Records System Descrip-tion.
NRPM-5.02 NPR/DWG Computer Program Diction- ,
ary Maintenance.
NPRM-5.03 NPR/DWG Computer File Integrity Vertification.
NPRM-5.04 Nuclear Records'IndeNing Guide-~
lines & Minimum Index Entry Re- ,
quirement.
i t
t O '
QAP - Appendix C Date: AUG 091hus Topical Rev.: 7 Page 18 of 35
M ,y,j_k h G: Fw:L r :97 %.M M ;&?O9W swnWM:i: . W t?W
~!
I ENGINEERING COMPUTER SERVICES' DEPARTMENT j PROCEDURES o 10CFR50 APP. B CRITERIA ECSP'- PROCEDURES V. Instructions, Pro-cedures and Drawings ECSP-1.1 1 Preparation of Engineerir.g Com-puter Services Department Proce-~ :
dures.
ECSP-1.2. Issuing of the Engineering.Ccapu-ter Services Department Procedure -
Manual. .
VI. Document Control ECSP-l'3 Document Review and Acknowledge-ment.
ECSP-2.1 ESD Program Development and Main-tenance.
ECSP-3.1 Generation and Storage of Backup .
Files in Systems and Operations.
ECSP-4.1 PCE Program Development and Maintenance.
\ .
'QAP - Appendix C Date: AUG 0 01985' i'
Topical Rev.: 7 Page-19 of'35 W- :r -
,< ?; " N;:: ; ~-
. "z43,3 -idgT@M, Er, W3.;. L 93y .;w ;vag,qas,;g3qat;.:/7qc,e:gp3rmc "
NUSCO NUCLEAR OPERATIONS DEPARTMENT ,
PROCEDURES s
10CFR50 APP. B CRITERIA NOD - PROCEDURES I. Organization NOD-1.01 Organization.
V. Instructions, Pro-cedures and Drawings NOD-1.02 ~ Preparation, Issuance, and Control of Department. Procedures.
NOD-1.03 Distribution and Accountability of Department Procedures.
VI. Document Control N0D-1.04 Distribution of Design Documents.
I N0D-3.02 Production Maintenance Management.
System (PMMS) Automated Work Order System.
XVII. Quality Assurance Records NOD-1.05 QualityAssurance Records. .
A QAP - Appendix C -
DatesAljC O D i.133 Topical Rev. 7-
,Page.20 of 35
j ..ryd@v.7.sngpa-;g g, cpg - p 5p ; ;g .,yv - ;up a 9. -- .,;_ . x : 7 '
4 6: .
, .. _ MILLSTONE QA ADMINISTRATIVE' CONTROL PROCEDURES (ACPS)
.t Q;
, APPENDIX B TO 10CFR PART 50 MILLSTONE QA (ACPS)
I. Organization ACP-QA 1.01 Millstone Administration.
ACP-QA 1.02 Organization & Responsibt- :(
lities. ,
ACP-QA 21.04 Plant Operations Review.ConL mittee'.' i
.a ACP-QA. 1.05 Site Operations Review Com-mittee. 'j
.l. >
II. Quality-Assurance ACP-QA 1.06 Quality Assurance / Quality. ~
t Program. Control Program.
-)
ACP-QA 1.10 Fire Protection Quality As-surance Program.
~
ACP-QA 2.01 QA Program Boundary. ;
I ACP-QA 2.02C Work Orders. ;
ACP-QA 2.05' Fire Protection. Program.
ACP-QA 2.14 Turnover of Systems, Components, and Structures (NEO 7.02)-. :
1 ACP-QA 8.01 Millstone Station Training.
l.
ACP-QA 8.07 QA Training Program.-
8.08 Millstene' Reactor 0perator
~
ACP-QA ,
Training Program. ,
ACP-QA 8.16 Training, certification &
Identification of Qualified '
-Inspection and Testing Personnel.
ACP-QA- 8.21 Qualificati6n of Audit P'er-sonnel.
III. Design Control 2.13A Computer Software Implementation. - i ACP-QA ACP-QA 2.138 Maintenance and Control of. .,
Site Computer Systems. .
'l QAP - Appendix C Date: G 'O 91985 -
Topica ev.: 7,.
. Page 21 of.35 I
\. .> ,
m _1__.____.__.__. _ _ _ _ _ _ _ -
ppK ;-y ~ .v ;7 MM5c y:, % m : pyw.7 1n " r-
+ -p y 2 x ;p. / ' - = . -
A .
c ,
~
MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES ~(ACPS) n
-APPENDIX-B TO 10CFR PART 50- < MILLSTONE QA (ACPS) 5 ACP-QA -3,04A Design Change Control -
Design Phase.
ACP-QA '3.04B Design Change Control -
- Processing.
ACP-QA 3.08 Safety Evaluations.' (NEO 3.12)i .
l ACP-QA. 3.09 Preparation' Issuance and Control of Project Assignments.
ACP-QA- 3.10 Preparation, Review, and Disposition of Plant Design Change Request (PDCRs).
(NEO 3.03).
ACP-QA 3.11 Preparation, Review, Approval,- -
Revision, and Control of Specification's (NEO 5.04).
ACP-QA 3.12 Design ~ Inputs and Design Verification (NEO 5.04) .=
ACP-QA 3.13 Prepar: tion, Review, and
- Approval ~ of Design Analyses and Calculations'(NEO 5.06).
ACP-QA 3.14 Design Change Notices'for-Design Documents:(NEO 5.11).
ACP-QA 3.15 Performance of Fire Protection Reviews (NEO 5.12)..
IV. Procurement Document ACP-QA 4.02 Procurement Control & Iden-Concrol tification of Material.
ACP-QA 4.06 Procurement..and Evaluation of Shelf Life Material.
V. Instructions, Pro-cedures, & Drawings (l'
ACP-QA 3.05 Review & Approval of Vendor Procedures.
ACP-QA 3.06 Preservice.. Unit Instructions.
1 l
QAP - Appendix C
-Date: A!j, f) (
Topical R}ev.j p7 g Page 22 of 35
r - ,.
~~ . ;. w, ,y;-~ m;;g;p tp ,.p i.".;&g._ .? m, : ,e a MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)
A L) APPENDIX B TO 10CFL PART 50 MILLSTONE QA (ACPS)
ACP-QA 3.07 Maintenance of Station implementing Procedures in accordance with NUSCO Governing Documents.
VI. Document Control ACP-QA 3.01 ACP's & Station Forms.
ACP-QA 3.02 Station Procedures & Forms.
ACP-QA 3.03 Document Control.
ACP-QA 3.19 Controlled Distribution of-Design Documents (NEO 5.03).-
VII. Co'ntrol of Purchased' Materfsl, Equipment &
Services ACP-QA 4.05 Product Acceptance-Inspec- -
tion & Testing.
ACP-QA 4.09 Transfer of Haterial Equipment and Parts'(NEO 6.03).
( ACP-QA 5.02 Trend Analysis from Quality-Related Documents VIII. Identification &
Control of Materials, Parts & Components ACP-QA 4.03 Classifying & Upgrading Spare Parts.
ACP-QA 4.07 Control of Weld Haterial.
IX. Control of Special Processes ACP-QA 2.07 Control of Special Processes.
X. Inspections ACP-QA 2.02A Installation Inspections.
1 ACP-QA 9.06 In-service Inspaction-Program.
ACP-QA 9.07 Quality Assurance Surveillance Program.
XI. Test Control ACP-QA 2.02B Retests.
QAP - Ap pendix C Date: AUG 0 01985 Topical Rev.: 7 Page 23 of 35
w- - y ,...,;;z9, -
.g , y=~,, , .: , s v- .m y, qgap3m MILLSTONE QA ADMINISTRATIVE CONTROL PROCEDURES (ACPS)
,_s APPENDIX B TO 10CFR PART 50 _
MILLSTONE QA (ACPS)
ACP-QA 2.15 Presperational Test'ing of Plant Modifications (NEO 7.03).
ACP-QA 9.02 Station Surveillance Program.
ACP-QA 9.02A Unit 1 Surveillance Master j Control List.
ACP-QA 9.028 Unit 2 Surveillance Master l Test Control List.
ACP-QA 9.03 Inservice Plant Testing.
XII. Control of Measuring &
Test Equipment ACP-QA 9.04 Control & Calibration of Measuring and Test Equipment.
XIII. Handling, Storage Shipping ACP-QA 4.01 Plant Housekeeping.
ACP-QA 4.04 Instructions for Packaging, Shipping, Receiving, Storage
['s,_/
} & Handling.
ACP-QA 6.04 Radioactive Material Ship-ping Requirements.
XIV. Inspection, Test &
Operating Status ACP-QA 2.06A Station Tagging.
ACP-QA 2.06B Station Bypass /Jemper Control (NEO E.01). l ACP-QA 2.06C Station Bypass / Jumper Control for Trouble Shooting, Red Lining, and Calibration.
l ACP-QA 2.12 System Valve Alignment Con-l trol.
i XV. Nonconforming Materials, Parts ;
or Components ACP-QA 5.01 Nonconforming Materials & i Parts.
XVI. Corrective Action ACP-QA 10.01 Plant Incident Report, (o)
\ _,/ QAP - Appendix C Date: AUG 0 31385 Topical Rev.: 7 Page 24 of 35
n y 1,~yl.c;y ,tG6.?;;q;t, m : ?+; & % w n:,, m lia: ; "59 .?+R;59:2=.= ' Jma % :ne*+: v.:+ + 'n}G:.@
, Y-e A
MILLSTONE QA ADMINISTRATIVE. CONTROL PROCEDURES:(ACPS)_
-APPENDIX B TO 10CFR PART-50 MILLSTONE QA (ACPS)
ACP-QA- ' 10.06 NRC Comunitment' Follow -Pro-(gram.
ACP-QA 10.08 Station Services Event Report.
ACP-QA 10.09 Licensee Event Report.
ACP-QA' 10.10 Corrective Action.
XVII. Quality Assurance Records ACP-QA 10.04 Nuclear Power Plant Records.
XVIII. Audits ACP-QA .9.01 Quality Assurance Audits' .
ACP-QA 9.05 Monitoring of QA Actihities. .
t C
.t
'l l
QAPJ- Appendix C
- (
Date:[iRev:'lj ',', 7() ') ' 'j.
Topica .
Page 25 of'35 l
y,;;=: v: aw: y g;;q;.,,.:9,.: ,q: , p sm:y > ~ is5yyc-am;,m.ugge . e.- --
CONNECTICUT YANKEE Q
A. PROCEDURE
S O
-(
CONNECTICUT YANKEE APPENDIX B TO 10CFR'PART 50 QA PROCEDURES _
I. Organization ACP 1.0-3 The Connecticut-Yankee.
Organization _ Responsibility:'
and Authority.
II. Quality Assurance .
Program . ACP 1.2-2.3 Certification, and Identifications of Qualified Inspection and Testing, Personnel.
ACP 1.2-2.1 Request for'a Category Evaluation.
QA 1.2-2.2 ' Quality Assurance Program Boundary.
ACP 1.2-2.4 Housekeeping Requirements. ,
ACP 1,2-2.5 Classifying and Upgrading i Spare Parts.
III. Design Control ACP 1.2-3.1, NEO 3.03 - Preparation, Review and Disposition of
( .
Plant Design Change Requests (PDCRs),
ACP 1,2-3.3 Setpoint Change Request (SCR)
ACP 1.2-3.4- NEO 5.04 - Preparation, Review Approval, Revision and Control of Specifications.
ACP 1.2-6.9 'NEO 3.12 Safety Evaluations IV. Procurement Document Control ACP 1.2-4.1' Procurement Document Review.
V. Instructions, Pro-cedures & Drawings ACP 1.2-5.1 PMMS Trouble Reporting System,and Automated Work .
Order.
ADM 1.1 Drawing Changes & New Sub-
.mittals.
VI. Document Control ACP 1.2-6.1 'Documant 9!stribution &
-Accountability, e 393 Topical.Rev.: ;7 Page 26.of 35.
u -_:_-_-______-__----___-. . _ _ - _ - _ . _ _- _ _ - - - _ - _ _ .
(; .hp;;~:y;y., ..Wegy;emMsg: ;;c%;j.m. cm;u :;u.gvpg; m ,8 7 CONNECTICUT YANKEE Q
A. PROCEDURE
S' pw kj
^ - -
-CONNECTICUT YANKEE.
APPENDIX B TO 10CFR PART 50- QA PROCEDURES ACP 1.2-6.2' ' Master. Document'Index.
_ACP 1.2-6.4 ~ Temporary. Procedure Change.
ACP 1.2-6.5 Station' Procedures.
1.2-6.10 Maintenance of Station-ACP Implementing Procedures with NUSCO Governing Documents.
ACP 1.2-11.6. Proposed' Technical Specification Change Requests.
VII. Control of Purchased Material, Equipment & .
Services QA 1.2-7.1. . Receipt Inspection and
- Identification of Materials,.
l Parts, and Components.
QA 1.2-7.2 Fuel Assembly Receipt Inspection.
OiJ VIII. Identification &
Control of Materials, Parts & Components ACP 1.2-8.2 ; Material Issue.
ACP 1.2-8.3 Weld Material Control.
IX. Control of Special Processes ACP 1.2-9.1 Control of Special Processes.
Qa 1.2-9.2 Requirements for Cleaning of-Fluid Systems & Associated Components.
ACP 1,2-9.3 .NE0 3.11 - Preparation, Qualification, Approval, and Revision of Northeast Utilities! Nondestructive Examination Procedures. ,
X. Inspections ACP 1,2-10.1 Installation Inspections.
ADM 1.1-51 -Inserv1ce Inspection Program.
QA 1,2-10,3 Authorized Nuclear Inspector (ANI)/ Authorized. Nuclear g
Inservice Inspector .(t.NII) .
QAP - Appendix C Dates AUG 0 9 1983-Topical Rev.: 7 Page 27 of 35'
~ }lQ:q qzk W :Qn . . . :_- ,L :v: . 5.W L q u ..: ~ y % b - m." MV ' ei CONNECTICUT YANKEE QA PROCEDURES,
(~NJ-r CONNECTICUT YANKEE APPENDIX B TO 10CFR PART 50 QA PROCEDURES _
2 ACP 1.2-10.4- Monitoring of QA Activities. '
.l XI. Test Contro1~ ACP 1.2-11.1 Technical Specification Surveillance Tracking.
ACP 1.2-11.2 Review of. Test Data. l ACP 1.2-11.3 Retests..
ACP 1.2-11.4 Product Acceptance Tests.
ACP 1,2-11.5 QA Activity Surveillance.
XII. Control of Measuring &
Test Equipment ACP 1.2-12.1 Control of Measuring and Test Equipment.. .
XIII. Handling, Storage &
Shipping ACP 1.2-13.1 Handling of Material &
Equipment.
QA 1.2-13.2 Storage of Material & Equip-ment.
ACP 1.2-13.5 Entry and Exit from Station of Transporter for Nuclear By-Product Material (Radwaste).
ACP 1.2-13.6 Packaging and Shipping Requirements for Material.
~
Parts and Components.
XIV. Inspection, Test &
Operating Status ACP 1.2-14.1 NEO 8.01 - Jumper, Lifted Lead and Bypass Control.
QA 1.2-14.2 Equipment Control (Locking,&'-
Tagging).
XV. Nonconforming
- I Materials, Parts, !
or Components ACP 1.2+15.1 Nonconformance Control. i ACP 1 0-14 Determination and Follow of- l Substantial Safety Has:ards !
(SSil) , l O -QAP - Appendix C l Dates AltF-f * '
- Topical'Wev'.: 7* .
Page 28 of 35 w _ __ -_____ __ _ _ _ _ _ _ _
.u,: ' W (lh i N'; 7 lW & 4 m i.;llv! +4;+ i;;%&9% ~.iF5p5.WruvW 7E;
oste: AUG 0 0.1985 -
- Topical _Rev.
- 7 ;
- Page 29 of 35 4 e
.._...___..___._a._...._____.._._c.3 l ,
my, _ :.gqy,gg.33 ..,,$pq.;. . ;pgro ; , . -m,, --
w, , - .r-e, - . . ,. _
-NUSCO GENERATION CONSTRUCTION ~
QUALITY CONTROL MANUAL M. "~
10CiR50 APP. B CRITERIA QC-G - PROCEDURES II. Quality Assurance .
Program QC-G-1.01 Hanual Application,' Control and Assignment of Responsibilities.
QC-G-8.01 Selection, Orientation, Training, Qualification and certification of Quality Control Personnel.
V. Instructions, Proce-dures and Drawings QC-G-2.01 Quality Control Instructions.
VII. Control of Purchased Material, Equipment & -
Se rvices QC-G-6.01 Receiving and Handling.
X. Inspections QC-G-3.01 Inspection and Inspection Surveillance,-
Reports.
XII. Control of Measuring and. Test Equipment QC-G-5.01 Control of Measuring and Test Equipment.
XIII. Hancling, Storage, and Shipping QC-G-6.02 Storage of Materials, Equipment and Parts.
XIV. Inspection, Test, and -
Operating Status QC-0-7.01 Inspection Status (Tagging).
XV. Nonconforming Materials, Parts and Components QC-G-4.01 Control of Nonconformance and.
Disposition Reporting.
I
(
QAP - Appendix'C Date: A U 2 0 .9 r et.
Topical Rev.: '7 i Page 30 of'35 .
_._____._._.._____.__.__...__m
' %7
. .' -- W W 6 ', < $ $ i ? . .
- -JA l' - ~ # 7 c'~ .
- '-" - '?~2
. < - ac -- 7 s k
~ '
..' 1 l
I
- i NU WELDING MANUAL WELDING MANUAL APPEKDIX B TO-10CFR PART~SO QA PROCEDURES _
4 I.- -Organization AP'700 Organization & Control of NUSCO .
Welding Manual.
IX. Control of Special
+
Processes AP 701 Preparation, Qualification, 4 Approval'& Revision of NUSCO Welding Procedures.
! AP 703 Preparation [ Review &Approvalof f
Detailed Welding Procedures; 1
1 AP 702 Control of Welder & Brazer Quali- '
fications.
4 1
l i
i-l h
. I
,e 1
J-a e J d
{ K ,
1-i .. -;
4 0* /
s -.r J 1
i QAP.- Appendix:C-
>D*te:l AUG 0 9 1985 Topical Rev.: . 7.
t,* - Page~31 of 35: .
s ., .
-- - . . , . _ ~
f . _"r*
t
-v ~iv,- ,-r-e, ,v- Y r" f - W er =rr er v "w e 'w E % w *m*-w fwaew"'+J **+ ++eo e 'r-'e ?= * * * = * * ' ' ' ' t'* ** >w=r5
---*-r-r* -+e
~ , *'
.:yl) ~/ , ' ;;, - " @ ;x.- , ;e;;: c > ,:. : a;#;c i. ..m , n 3,7;cgy g;;;s-;p. . .;g,;- .
NU PURCHASING BUSINESS ~ PROCEDURES, PURCHASING APPENDIX B TO 10CFR'PART 50 QA PROCEDURES _ ,; _
c IV. Procurcaent Document 4 Cont.rol BP - 3.1 Requisition: _ Standard and Repeating.
BP - 3.3 Purchase Orders.
BP - 3.4 Changes to Purchase Orders.
4 h '
BP - 3.19' Blanket Purchase Orders.
4 I i I
1
<.% . - ' W Xl5%m%: '? =n:n"5DB':", *:+:: r.q?~+ un:EQ.%~-@+M REACTOR' ENGINEERING BRANCH PROCEDURES w
10CFR50 APP. B CRITERIA REB'- PROCEDURES- . _ _ _
III. Design Control' REB-3.01 Generation of_INCORE Analytical
+ Input From-B&W Data.
REB-2.01 Project Follow, Review and Documentation for Initial Core and Reload Fuel. Campaigns. l REB-3.02 Generation of Millstone Unit 1 Bundle Exposure and Isotopic Data-for. thel
~ Nuclear Fuel Branch.
REB-3.03Q' Generation.and Evaluation of
-Incore Code Results to-Verify Technical-Specification Compliance. ,
REB-3.06 ' Computer Program Development -
and Control.
REB-1.01 Preparation,LIssuance.and V. Instructions, Procedure.
O and Drawings . Control of REB Procedures.
and Subtier Instructions.
XVII. Quality Assurance Records REB-1.02- Reactor Engineering Branch ~
Record Retention -. Management-of Nuclear Power Plant -
Records.
i
~o ~
O '
.QAP: . Appendix ~C a; ,
' Da te ': AUG 0 9125: 0>
- Topical Rev.: 7.-
I Page:34 of 35
{; i .
,, _ _ : . a, - _
- ,. - , . :- . . . - , - .,, . . -. .z,.- . :.. . m ^ .;... . .~.
.'W9C-M.QL@D.?WJ YT=)G%.37 '?:M :' W \ % E + R 3 % n p y y;: p ; g y.e: s + M : g . vm .- . : n . . ; . m
. GENERATION FACILITIES LICENSING BRANCH
.1 PROCEDURES l
~
10CFR50 APP. B _ .
CRITERIA GFL - PROCEDURES _
II. Quality Assurance ~ Program GFL-2.01Q Training in NEO Group Nucleat Policies, Procedures,
-and Programs.
V. Instructions, Procedures, GFL-1.01Q Preparation,' Issuance and- ,
and Drawings = Control of Generation Facilities Licensing Branch' Proced2res and-Instructions.
VI. Document Control GFL-3.01Q Regulatory Agency.Correspoodence.
GFL-3.03Q U.S. Nuclear Regulatory Cosmission NUREG's. a GFL-3.04Q'U.S. Nuclear Regulatory Commision Federal Register
-Notices.
GFL-3.05Q U.S.i Nuclear Regulatory
. Commission Regulatory ,
Guides. .
GFL-3.06Q Documentation of-Telephone
' Conversations.
GFL-3.07y Forward Commitments.
.GFL-3.08Q Preparation and Submittal of.
Special Nuclear-Material,.
Source Material, and: Byproduct Material License Applications.
XVII. Quality Assurance Records GFL-3.02Q Management:of Nuclear Power Plant Records.
x
( _
-QAP- .Ap3endix C'-
LDate: AlG 0 9.1985 Topical.Rev.: - 71
- Page.35'ofs35:
$ j f-
. , . - . . , .._.m.. . . . _ . . - . . . - , - . -, ,.m.,.
-Q%g.25$5?i(U??f0&f,3 ,;tiqRsq.9FPC- + + - J.C 'wn W C:M ,'T> R W - WT' We
. APPENDIX D.
NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT REGULATORY GUIDE AND ANSI STANDARD COMMITMENTS
-NOTE: The NUQAP is committed to utilize the guidance obtained from the following regulatory documents and their. endorsed standards.
Exceptions to these positions are listed ~in Appendixt F-of thisi topical report.
Appendix B to 10 CFR, Part 50 -' Quality Assuranc'e Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.
10 CFR 50, Section 50.54, Condition of Licenses.
'=
10 CFR, Part 55 - Operator's Licenses -and its Appendix A ' Requalifi-cation Programs for Licensed Operators of Production and Utilization Facilities.
Regulatory Guide 1.8 R - 5/77 - Personnel Selection and Training -
Endorses ANSI N18.1 - 1971.
Regulatory Guide 1.28 - 2/79 - Quality Assurance Program Requirements (Design and Construction) Endorses ANSI N45.2 - 1977.
Regulatory Guide 1.30 (Safety Guide 30),'8-11-72-- Quality Assurance-Requirements for the Installations, Inspection, and Testing of Instru-mentation and Electrical Equipment'- Endorses ANSI N45.2.4-1972.
Regulatory Guide l'.33 - 2/i8 - Quality Assurance Program Requirements (Operation) - Endorses ANSI N18.7-1976/ANS3.2.
Regulatory Guide 1.37 - Quality Assurance Requirements for Cleaning of.
Fluid Systems and Associated Components.of Water-Cooled Nuclear Power. <
Plants, 3-16-73 -Endorses ANSI N45.2.1 -'1973.
I Regulatory Guide 1.38 - Quality Assurance Requirements for Packaging, j
-Shipping, Receiving, Storage and Handling of Items'for Water-Cooled Nuclear Power Plants, 5/77 --Endorses ANSI N45.2.2 - 1972' Regulatory Guide 1.39 - Housekeeping Requirements for 'Watier -~ Coole'd ' !
Nuclear Power Plants, 9/77- Endorses. ANSI N45.2.3 - 1973.-
Reg'ulatory Guide 1.58 . Qualification of Nuclear Power Plant: Inspection, 1 Examination, and Testing Personnel,-Rev.-1, 9/80'- Endorses.ANST N45.2.6.- i 1978.
' Regulatory Guide 1.64 - Quality Assurance Requirements for'the Design'of H Nuclear' Power Plants, 6/76- Endorses ANSI. N45.2.11'-'1974.
~
QAP - Append'ix D1 j
~Rev.: 7L Da'te : !,W s . ; .
-Page 1Jof 2..
-=:. r .;2 y m ;. , ',
, . r:sn s.; y. m;: m:p . :n.ci?;:n.mu.p.M:6Mo; ; ;.m ..
p
(,,). Regulatory Guide 1.70, " Standard Format and Content' of Safety Analysis Reports for Nuclear Power Plants'- LWR Edition", Revision 2, September 1975 is utilized for Connecticut Yankee, Millstone.1, and Millstone 2. Revision 3, November 1978 is utilized for Millstone 3.
Regulatory Guide-1.74 - Quality Assurance Terms and' Definitions, Feb.
74 -Endorses ANSI N45.2.10 - 1973.
Regulatory Guide 1.88 - Collection, Storage,' and Maintenance of _ Nuclear Power Plant Quality Assurance Records - 10/76 - Endorses ANSI N45.2.9 -
1974.
Regulatory Guide 1.94 - Quality Assurance Requirements for Installation,.
Inspectionzand Testing of Structural Concrete and Structural Steel'During the Construction Phase of Nuclear Power Plants - 4/76 -Endorses ANSI N45.2.5 - 1974.
Regulatory Guide - 1.116 - Qual'ity Assurante Requirements for Installa-tion, Inspection, and Testing Mechanical Equipment and Systems - 5/77 -
Endorses-ANSI N45.2.8 - 1975.
Regulatory Guide 1.123 - Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants ~ 7/77 -
Endorses ANSI N45.2.13 - 1976.
("'\ . Regulatory Guide 1.144 - Auditing of. Quality Assurance Programs For
\ ,) Nuclear Power Plants - Rev. 1 - 9/80 -Endorses ANSI N45.2.12 - 1977.
~
Regulatory Guide 1.146 - Qualification of Quality Assurance Program Audit _
Personnel For Nuclear Power Plants - 8/80 -Endorses ANSI N45.2.23 - 1978.
4 N g/
.QAP ; Appendix D Rev.: '7 Date: AUG ~ 0 91985 -
-Page:2 of 2 9
r yg%G.' WMM.4 {+'6Mi"!M9:i?:5G@%;WFfiWs W+WS!&6W9W 6
WW &}
N 4 e
s r APPENDIX ~E D
NORTHEAST UTILITIES QUALITY! ASSURANCE PROGRAM TOPICAL REPORT-l GLOSSARY OF QUALITY ASSURANCE TERMS L
~ '
Accept As Is -' {also known 'as '?Use-As-Is") a Misposition' which may be /
imposed for a nonconformance: when it can be established -that the;. discrepancy
. will result in' no . adverse conditions and that the-item under consideration -
will' continue to meet all engineering functional requirements including.
] performance, maintainability, fit and-safety.
! As-Built Documents - Documents whichl accurately _ describe the condition i actually achieved in a system, structure, -or component. .These; documents:
[ include: material; certification.and test' data; reports of. inspections,-
p examinations, and test results; drawings, specifications, procedures,'
[ and instructions; and records of nonconformance and t. heir resolution. -
i Audit - a formal, documented. activity performed in accordance wi'th
- . written checklists or procedures to verify by evaluation 1of objective' -
M-4-
evidence that a quality assurance program has been developed,; documented ~,-
and implemented in accordance with appliccble'. requirements.
Calibration - the' process by which measuring and-test. equipment are j % checked against standards of known higher accuracy and adjusted;as necessary to ensure their compliance with designated.. specifications.
~
- . Category I - designation given to systems, structures, and compon'ents of-
] a Northeast Utilities nuclear power plant that prevent .or mitigate :the :
consequences of postulated' accident's that could cause undue risk;to the'
.j health and. safety of the public.
Categor3 _ Systems, Structures, and Components
-defined (in Appendix'A.
Cleaning --those actions performed to maintain an~ item in atcordance with'
, cleanliness requirements. ,
J e
Contractor - organizations that provide: services.th'at may inclu'de.engi '
~
2 U
4 neering, procurement, construction, and installationlof material;fequip- .:
ment, and parts. The Nuclear Steam. Supply System SupplierL (NSSS Suppli - l er) it, included in this category. '
~l m )
L ' Corrective: Action - action taken to correct conditions 1 adverse to quality- i i in order to preclude recurrence of theiconditions.
g.
4 Deficiencies - departures from specified: requirements. ,-
- a. -
, , . , ~, . - . . , . . -
w i~ Department.- The use ofsthe word department,'throughoutLthe.NUQAP. Topical;
- 9
- Report,' canfrefer to'~any portion:of the NUSCO/NUPOC organization'(iie.,;
~
, d
& Group Division, Department, Branch,/Section, , .
orfUnit,T.asl applicable). 1 i-5
_ 4-
~ QAP3 Appendix E' fj
'~ 'Revy:. 70 ,
s
.q
, ;Date: ". JT'jQ1, t f
- > --e Page
- a lf o[f97 i
.m. .
Q
_~
1 j .
u
- 5
. ~ .m
. - c. 2.~ w. , < - _ - .. - - - . m-- - - - ~ ' - - - -- -
C~::z9.ygf.wpwn%gt;w . ye - p ; g wqq % ~ y; Wu,.;
- =
> a}w g:n c - - wg MF ;q w-g ,
, s -
x .
- q '
s' 4 , . ,
-s.
lt em 6
Departmental Measuring and Test Equipment List' - ~a Llist iof all'departmen-l J L ,
tal_measuri'ng and test equipment included in the NUPOC calibration program.
Design - technical and management processes which lead to and include-the.
~
i issuance of design. output documents such.as.' drawings, specifications,;and other documents: defining technical requirements of systems,4 structures, and components. -
Design Changes'- changes in' drawings and specificatNns.which define'the; ~ '
design of Category I systems, < structures, and components :of -nuclear power t
},
plants.
Design Documents - design _ documents referred to herein are the drawings and specifications that define-the-design of Category I systems, struc - ^,
tures, and components;; the Facility Description and Safety Analysis . _
(FDSA)/ Final. Safety Analysis _ Report (FSAR); the License. Document; Techni-cal Specifications;:and Environmental Technical Specifications.
Drawing Change Request -a document useduto request ^ approval of^ revisions to existing NUSCO drawings. .
Engineer-Constructor - the principal organization contracted by-NkJSCO that performs the overall engineering,: procurement,' construction, and installation of Category I systems, structures,.and components of a:
nuclear power plant. D' Engineer-Constructor / Contractor Installation Inspection -:an . inspection ;
of Category I systems, structures and components performed by the. Engineer-1 Constructor / Contractor prior to system release / transfer to.NUPOCifor-preoperational testing,'as defined in.the NUPOC Startup Manual.
Engineering Service Organization - organizations-that provide services-such as analysis, testing, and inspection.
Generation Facilties Records -/ the ' organization ' responsible' for. establishing the Corporate Nuclear Plant Records! Program'.which 'is implementediat each- _
Nuclear Plant Records Facility.'
Handling - the transfer of, an item from one location. to~ another within a contractor's, supplier's or' engineering' service organizationf s facility ori at - the nuelear power plant.
Identification - a means by which material,; equipment'and parts:can bel
' traced to their associated documentation through the use'of heat numbers,- .
lot . numbers,' part . numbers, serial numbers ,f or other ' appropriate means. -
. Inspection - a. phase of. quality. control wi$$ch;'bylmeans;ofiexamination,_ -
' observation, or- measurement determines the conformance' of material,-
equipment,fparts,-and:proce'sses to predetermined; quality requirements'.'
~
O
~ ;QAPJ-' Appendix E; Rev.:.--'7 -
TDate:[tE09]os aPage22-of471 y-m ,y.
.m '
. > s
~
q: ',! sv<,' .. x . 427 4 e .
- ' 5e - ' v' mW.a w. MJ1/? 'n
. /~r I .
-A_,[.
L Inspection Sta'tus - identifica' tion of material, equipment, and parts.that have completed inspection, either acceptable or unacceptable.
Life Records - those quality documentsLthat are maintained for the lifetime of the in-service nuclear power plant or for the life of the particular component or part. Life records are those which would be of-significant value.in meeting one or more of the following criteria:
4 (1) demonstrating capability for safe operation.
(2) maintaining,' reworking, repairing,' rep' lacing or modifyirg the item.
(3) determining the cause of an accident or malfunction of an item.
4 (4) providing required base line data for. in-service inspection.
Manager, QA/ Designee - the designee is a NUSCO Quality Assurance emp-loyee, as well as the respective NUPOC QA/QC Supervisor or NUPOC QA/QC-employee as depicted by Figure 1.6 of QAP 1.0.
Measuring and Test Equipment - those instruments, gages, tools, '
fixtures, reference and transfer standards, nondestructive. test equipment, and measuring devices used during inspection and. testing to determine that measuring and test parameters comply with appropriate
/ requirements in specifications and drawings.
O) Nonconforming Material, Equipment, and Parts - any material, equipment, or parts which do not conform to specified requirements.
Nonengineered Items - Material, equipment and parts which are:
(1) Relatively simple and standard in design,= manufacture and ,
test.
(2) Adaptable to standard or automated inspections'and/or~ tests of ,
the end product to verify quality characteristics'after deli- i very.
(3) Of such a nature that product acceptance inspections / tests performed upon receipt of the items do not' require operations which could adversely affect the integrity, function, or cleanness of the item.
Non-Life Records - those quality documents-that are maintained for a.
specific period of time other than the lifetime of the in-service nuclear power plant or the particular . component or part. .i i
l J
(~~h l
\_s! ..
QAP_- Appendix EL j
-Rev.: 7-Date: ~ ' [ "
Page 3.of'7
, ,.y; ,
,- . g.
s ;v w.g m ;, g..q m;,p w m g...m y.g m v .- .~. .f
. gxga kf Northeast Utilities (NU) - a public utility holding company which owns Northeast Utilities Service Company and The Northeast Nuclear Energy Company and thru its operating subsidiaries has a controlling interest in The Connecticut Yankee Atomic Power Company.
Northeast Utilities Service Company (NUSCO) - a wholly' owned subsidiary of Northeast Utilities that provides engineering, . procurement, . construc-tion, and quality assurance services for Northeast Utilities relating to design, construction, and preoperational testing of nuclear power plants and major modifications thereto.
Northeast Utilities Quality Assurance. Program (NUQAP) - consists-of the NUQAP Topical Report, Quality Assurance Branch Procedures and other-Northeast Utilities Group / Divisional / Departmental / Branch /Section quality related procedures.
Nuclear Plant Operating Companies (NUPOC) - which as a subsidiary of Northeast Utilities performs preoperational testing of Category I sys-tems, structures and components of nuclear power plants and major modifi-cations thereto subsequent to completion of their design and construction and is also responsible for the operation of in-service nuclear power .
plants. The companies which comprise NUPOC are The Connecticut Yankee ~
Atomic Power Company and The Northeast Nuclear Energy Company.
Nuclear Plant Records Facilities - three separate facilities; located at O
(j Millstone Station, Connecticut Yankee, and Berlin; responsible.for indexing, retention, retrieval, and protection ~of Nuclear, Plant Records.
NUSCO Internal Audits - audits performed by NUSCO-Quality' Assurance of NUSCO quality related activities at the corporate office.
NUSCO Nuclear Project Engineer - the engineer- designated to act as project engineer during design, construction and preolerational testing of a new nuclear power plant. He may or may not. be tinled engineer.
NUSCO Nuclear Project Manager - NUSCO employee assigned the responsibility to coordinate all activities addressed in the NUQAP relating to a new-Nuclear Power Plant Project (i.e., Project Manager - Millstone. Unit 3).
NUSCO/NUPOC Engineer-Constructor Contractor, Supplier, and Engineering
- . Service Organization Audits - audits performed by NUSC0/NUPOC Quality-Assurance of the Engineer Constructor, contractors, suppliers, and
, engineering service organizations . quality' related activities.-
NUSCO Quality' Assurance Contractor, Suoplier,.'nd a Engineering Service
- Organization List - a List identifying the approval status of the quality assurance programs of contractors, suppliers, and engineering service organizations.
QAP'- Appendix-E--
Rev.: 7.
,Date: AUG 0 01?85 Pagef4 of'7
Jg.::Mp m::tlR .M .w= - W :: w na "m v -c.p:wpu:'.n-m' ? we; e 7 ;;m y-ws .
~ f, ) NUSCO Quality Records Center - the location at-NUSCO.of the NUSCO Quality-N'-
Assurance records files under the cognizance of the NUSCO Quality. Assu-rance Branch.
" Objective Evidence" - any statement of fact, information, or record, either quantitative or qualitative, pertaining tolthe quality of an item or service bas'ed on observation, measurements,. or tests which can be verified.
Plant Audits Audits performed at the in-service nuclear . power plant 1by .
NUSCO/NUPOC Quality Assurance of NUPOC _ quality related activities.
Preoperational Testing tests performed by NUPOC tp ensure Category I systems, structures, and components will perform satisfactorily during operation of the ' in-service nuclear power. plant.
Preoperationa'l Testing Audits - Audits performed by NUSCO/NUPOC Ouality; Assurance during preoperational testing to verify implementation of the requirements of the Northeast _ Utilities Quality Assurance Program.
Preservation - those actions performed to maintain an item in its origi- .
nal and usable condition.
Procedures and Instructions - documents that specify how an activity:is to be performed. They may include methods to be employed; material, f-s equipment, or parts to be used; and a sequence of operations.
Nu ,) '
Procurement Documents'- letters of Intent, Contracts, Purchase Requisi- l tions, and Purchase Orders which provide contractual basis for services '
such as engineering and procurement; supply of material, equipment, and parts; construction; installation; inspection; and testing. They define' l
the requirements which items and services must meet,'in order to.be 1 considered acceptable by the purchaser.
. Product Acceptance Inspection / Test - Inspection / test performed as part of receipt inspection at the nuclear power plant to verify- the quality characteristics of nonengineered items. Operations utilized during product acceptance inspections / tests are such that they-do not adversely affect the integrity, function or cleanness of'the item.
Proof Test - a test conducted: prior to installation of Category.1 sys-tems, structures and components to verify specification requirements have.
been met.
Project Engineer - a NUSCO/NUPOC employee assigned the_ responsibility to -
coordinate the engineering activities addressed in NUQAP.
Project Manager - A NUSCO employee assigned the responsibility to coordinate all activities addressed in NUQAP relating to their assigned Projects.
QAP - Appendix E'
-Rev.: 7 Date: AUG 0 0 1985'
.Pagel5 of.7 _
r.
. .g. ; '. , -- --: "- -
_ :m. ;g.:. .,. -
- " ' ' ' =
a Y.
Purchased Material, Equipment, and Pa rts - items prm ured for use in Category I systems, structures, and components.
Purchased Service - services procured to assist in operation, main-tenance, modification, and refueling of in-service nuclear power plants. _
Quality Assurance Records - any record pertaining to the quality of material, equipment, parts, processes, or operations relating to Category I systems, structures and components which are founded on observations,
)
measurements, or tests which can be fully checked or verified. Such statements may be recorded on a written or preprinted documert or tag. T The statements are authorized with a signature or stamp identifiable.to 1 the person making the statement of fact. @
n Quality Related Proceoures - an administrative document issued by a g NUPOC Station Superintendent or NUSCO department head to implement the requirements of the NUQAP Topical Report.
f Repair - a disposition applied to nonconforming material, equipment, and '
part: that are unsuitable for their intended purpose which are modified g by the use of additional operations and/or processes so that they are _
suitable for their intended purposa but may not meet all specified
- requirements. N Retest - a test conducted prior to operation following installation in-spections of work associated with maintenance, modification, and refuel- 1 ing to verify that Category I systems, structures, and components will 4 function satisfactorily when in opera' tion. A retest may also be per- __
formed when original test results are invalidated.
]
Return g Supplier - a disposition applied to nonconforming material, Z equip nent , and parts that are unsuitable for their intended purpose but =
which are feasible to repair or rework at a supplier's facility. --'
Rework - a disposition applied to nonconforming material, equipment, and parts that are unsuitable for their intended purpose due to incomplete 3 operations or variations from original engineering requirements but which '
are modified through the use of additional operations or processes to meet all specified requirements.
3
=
i_
Salvage - a disposition applied to nonconforming material, equipment, and t-parts that are unsuitable for their intended purpose and not feasible for =
rework or repair but which contain material, equipment, or parts which ---[
are reclaimable for future use.
a-Special Processes - an operation performed under controlled conditions in accordance with special requirements utilizing qualified procedures, "
equipment, and personnel. These special processes may include, but are a not limited to: welding, brazing, soldering, cleaning, heat treating, and nondestructive testing.
=
I O~ QAP - Appendix E d Rev.: ,7 ,,
Date:. ,, ,
=
Page 6 of 7 O.
m k ..
, . - - ;++'.
ms.;a,4.c ;s:. 09..;g w emv6; m p.,evu.wnwgn;w a.a-een w-i, 1,e aw; ..; r/cyrc: s. - ,
~
Stor'.3ge - Maintenance of an item in-the environment speci f icil in appro-priate documents.
Supplier - organizations that provide material, equipment, and parts.
Surveillance .- A documented record of' the observation of work operations performed at the construction or vendors site. Surveillances are not:
performed to a preplanned checklist. However, the results are : formally documented and reviewed and follow-up action, if necessary,' is provided.
Test'and Operating Status . identification of material, equipment, and parts that are ready for test or operation, or an existing stage of a test operation. .
Testing - the determination or verification of the capability of an item to meet specified requirements by subjecting the item to a set of physi-cal, chemical, environmental, or operating conditions.
t F
QAP.- Appendix E' Rev.: 7 .
i
.Date:
Page 7AUG0 of 7. 01985'- -
s
C 4%Wm?.wWs:-M c- w e' - % y S M W w;, -n . w w- M vW;v v l N
. c ,
5 i (^~'\ gj APPENDIX Fi
~
NORTHEAST UTILITIES QUALITY' ASSURANCE PROGRAM TOPICAL ~ REPORT .
Program Exceptions .
- 1. ANSI N45.2.9, states in part, <'iStructure,Ddoors, frames, and hkrdware should be Class A fire-related.with a recommended f four-hour minimum ;
rating." The records storage vault door and hardware at NNECO has a two-hour rating and'the record storage vault door and hardware at CYAPCo has a three-hour rating. "
n Both NNECO and CYAPCO's. vaults.are used f for-storage of documentation-that is unsuitable for filmingior awaiting filming'. ;
~
A records organization exists along with written procedures. addressing
~
the control of quality assurance records. ~
- 2. ANSI N18.7-1976, paragraph 4.3.2.3. " Quorum" states in part: ' A' quorum for formal meetings of the (Independent Review) Committee . . ,
a held under the provisions of 4.3.2.2 shall consist of not less'than' a majority of the principals, or. duly appointed alternates...".
~
The use of Alternates was eliminated from the-Northeast-Utilitiesi -
Nuclear Review' Board'(NRB) Charte'r duento the difficulties of: M
)
~
keeping t.he Alternates up to date. The elimination.of Alternates :
forced the creation of a larger NRB membership- (seven to eleven .
members) for greater diversity, resources, and availability. .
A quorum of the Nuclear Review' Board shall consist'ofJ the. Chairman or Vice Chairman and at least four NRB members. No more than a. ,
minority of the quorum shall be-from-the Nuclear Op'erations Depart-ment. a t
- 3. ANSI N45.2.9-1974, paragraph 1.4, definition .of " Quality Assurance Records" states in part: "For the purposes of :this standard, ' a =
document is considered aLquality.assurancelrecord"when the docume'nt has been completed". ',
Northeast Utilities has developed.the following alternative: definition.
l to provide guidance during-the interim. period?from the time.a- -;
document-is completed until it isttransmitted to~the; Nuclear: Plant Records Facility:
"A record ts. considered'a: working document i untiliit is" transmitted'- -
to the appropriate Nuclear Plant Records. Facility;(NPRF) at which 0 time it is desigsated.as a Quality Assurance Records. . The following" maximum time limits are established 'for the ' transmittal of working J documents to the 1H90P: * ~
i
- > QAPL Appendix Fi "Rev.: 17; Date:M(J Q gqg Pagerl.o ~~ -
C .
.. __ _ = . - . .
, , : .s. , .--,, ,---..-.------- -
7 m
Ri
-a S
2 Operations Documents - Documentation generated during Plant E Operations may be maintained, as needed, by operating plant departments, for up to one year. w
==
New Construction or Betterment Documents - Documents which evolve during new construction or betterment projects shall be _g transmitted to NPRF within 90 days of completion of a new g construction project or turnover of a betterment project to _ --
plant operations. '
t 7
All Other Working Documents - All other working documents shall _-,]
be transmitted to NPRF within 6 months of their receipt or -
completion."
Ee The requirements of ANSI N45.2.9-1974 do not apply to these " working documents" based on paragraph 1.1 of the ANSI standard which states:
j
{ "It (ANSI N45.2.9) is not intended to cover the preparation of the records nor to include working documents not yet designated g
n as Quality Assurance Records."
g
- - ,i Y
N
-25E p _N
'Q O ,
h
=
_n I
M
- -e a
y
-m =
m 5 -N--
4 --
e i
h E h 2
~
4 7 -
m -
E
-t w
[ M
,E ~ -:
- P _
QAP - Appendix F ,
D E ' " P '
^-
Page 2 of 2 ----
_=
- w.qcrWh; 943geepi . , r.1.
. ,....y., -wy..g,coru w s.3y.m<wr =c.~ w e , ; ,y - g
- a
-i
.5.
j Operations Documents - Dhcumentation generated during Plant
-(J-
.N Operations may be maintained,1as needed,-by operating plant-cdepartments,- for up.to one year.
New Construction or Betterment Documents - Documents which .
evolve during new construction or betterment projects - shall . be '
. transmitted to'NPRF within 90' days of completion of a new.
construction' project ;or turnover of.a; betterment project to "
~
plant operations.
All Oth'er Working Documents.- All other working documents shall!
- be transmitted to.NPRF within 6 months of ~their receipt or
. completion." ,
The requirements of ANSI N45.'2.9-1974'do not apply to these " working documents" based on paragraph 1.11of the ANSI standard which states:
"It (ANSI N45.2.9) is not intended 'to cover the preparation of the records nor to include working documents not'yet designated ,
as Quality Assurance Records.'
A
-i
. l I
~
\ :
QtP - Appendix F Rev.: 7 Date: [i '. '.3 0 *' ' ' a -
- Page 2 of 21
-I
< ,