ML19338D634
| ML19338D634 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 09/10/1980 |
| From: | Bandazza J, Frizzle C, Lawton R Maine Yankee |
| To: | |
| Shared Package | |
| ML19338D625 | List: |
| References | |
| NUDOCS 8009230591 | |
| Download: ML19338D634 (68) | |
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i-MAINE YANKEE ATOMIC POWER COMPANY OPERATIONAL QUALITY ASSURANCE PROGRAM l
REVIEWED BY: k N Nuke R. R. Lawton,"Direc tor, Operational Quality Assuran :e i.
Maine Yankee Atomic Power Company l
REVIEWED BY:/
C. D. Frizzle, Manag'er, Nuclear Support Maine Yankee Atomic Power Company REVIEWED BY:
E. C. Wood, Plant Manager Maine Yankee Atomic Power Company REVIEWED BY:
W. P.
o son, Vice President Yankeei clear Services Division APPROVED BY:
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.Z/ B. Randazza,Gl4e President-Manager of Operations Maine Yankee Atomic Power Company II -
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Rev. No.: 0 Date: Seotember 10. 1980 POLICY STATEMENT
' Operational Quality Assurance Program
!'e As a matter of company policy, the Maine Yankee Atomic Power Company
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Operational Quality Assurance Program shall cceply with the requirements of the Code of Federal Regulations Title 10, Part 50, Appendix B, with respect to the operation and maintenance of, and changes to the nuclear generating r
facility.' The Program shall be consistent with ANSI Standard N18.7-1976 and its referenced standards; and the Regulatory Guides specified in Section II,
- i
" Quality Assurance Program" of the Topical Report. Any exceptions shall be specifically noted.
i The Vice President Manager of Operations is responsible for establishment and Lnplementation of the Program within the Maine Yankee Atomic Power Company.
The' Director of Operational Quality Assurance shall be responsible for ensuring that the Program is Unplemented - for all activities requiring quality The Quality Assurance staff shall be responsible for auditing the assurance.
program as necessary and surveying / inspecting activities required by the Program to assure compliance with its requirements. The Quality Assurance staff shall have the authority and organizational f reedom necessary to meet the requirements of 10CFR50, Appendix B.
The Plant Manager shall be responsible for the day-to-day implementation of the Program's procedural requirements at the plant.
The Nuclear Safety Audit and Review Committee (NSARC) shall periodically review the adequacy and ef fectiveness of the Program. Any discr'epancies in
~
the implementation of this policy or the Program that are revealed during the review and that require corporate action for correction, will be reported to both the Vice President Manager of Operations and the Vice President,' Yankee Nuclear Services Division, together with appropriate recocmendations.
Implementation of this policy will enhance the reliability and safety of-the nuclear generating facility. Each person involved in activities affecting the quality of structures, systems, and components usad 'to prevent or mitigate the consequences of postulated accidents that could cause undue risk to th.
health and safety of the public, shall be responsible for assuring quality in his own work, and for compliance with the reouirements of the Program. The Operational Quality Assurance Program is a (scument which shall be adhered to by all responsible organizations and indiv'. duals.
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Title:
..'Section I.. Organizatior.
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September 10, 1980:
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!4 I.
ORCANIZATION J i
A.
' SCOPE"
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, This section ofithe Operational Quality Assuranc'e ' Program describes h~
' the dutiesL and responsibilities ' of the-personnel involved..in ~
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,establ sh ng _and execut ng the Operat onal' Quality Assurance Program.-
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' B.' RESPONSIBILITY The responsibility for ' design, evaluation,'_ maintenance,~ and " operation U
of -the Plant reses with the Maine Yankee-Atomic Power Company. The
.j responsibility for developing and implementing the Operational Quality ' Assurance Program,is. vested 'in the Vice President Manager of -
i Operations. He has delegated areas 'of authority for the development -
and implementation.of certain phases of.the Program 'as set forth in:
.the.following paragraphs of-this section.
. The Operational Quality Assurance Department has the organizational
' responsibility for the continuing review l and audit 'of the implementation'of the Operational Quality Assuranc'e Program, s
C.
ORGANIZATIONAL ' RELATIONSHIPS -
Maine Yankee Atomic Power Company line's of authority of'all personnel involved -in' the unplementation of the Operational Quality. Assurance Program are shown in Figure 1.
A Vice President of Maine Yankee Atomic Power Company i's also a
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corporate officer of -the Yankee Atomic Electric' Company, Nuclear -
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' Services Division l(YNSD), which has a continuing contractural.
- obligation ~ to provide services - to the Maine Yankee Atomic Power
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Company. This ' interlocking corporate officer shall be herein identified
- as ' the Vice ? President (YNSD). The Vice Preeident (YNSD) conducts, through NSARC, fan independent review of. all : aspects of plant safetyjand,; by. virtue of. his interlocking positions,' assures that YNSD provides 'the services assigned. and requested.
D.
QUALITY' ASSURANCE PilDGRAM RESPONSIBILITIES
- 1.. (Vice President-Manager of Operations m
a..
Assumes and maintains responsibility for the Operational
? Quality' Assurance Program.
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Provides':for establishment and implementation of the 4'
Op_erational Quality Assurance Program.
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Title:
Section I. Organization
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Rev. No.. 0 -
-Date: ~ September 10, 1980-l 1'
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, Establishes and enforces company policies in the ' area of -
b.-
0peratiocal; Quality Assurance..
-d.
Establishes and implements an organization capable of and directed toward a proper Operational: Quality Assurance
- Program.-
Provides for a periodte review of ' the Operational Quality e.
~
Assurance Program to determine the' adequacy and p
effectiveness of the Program.
f.
Ensures that personnel performing Quality Assurance functions have sufficient authority and organizational freedom to:
i.
identify quality problems,
ii. initiate, recommend, or provide solutions through -
designated channels, and, iii. verify implementation of solutions..
g.
Provides for independent operational review and/or approval
- of ' plant repairs,. and design changes.
h.
_ Provides for review and approval of training programs,-
, plant procedures, drawings, specifications and purchase ~
requests.
i.
Provides for and coordinates review of industry ope' ating r
'3-problems with 'the aim of minimizing likelihood Lof
~
occurrence at the plant.
j.-
Evaluates the auditL" discrepancy", " discrepancy response",
and " Recommended Corrective Action" and prepares
" Implementation Directives" to resolve disagreements.
k.
Approves all ~ changes to the Operational Quality Assurance Program.
1.
Reviews the qualification requirements for the principal-Quality Assurance management position to assure competence consensurate with responsibility.
(SeeLAppendix A) m.
Pro'vides for resolution of NSARC. recommendations.
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Vice President - Yankee Nuclear Services Division Provide independent review of all aspects of plant safet.y, a.
via the Nuclear Saf ety Audit and Review Committee. Appoint the membership of the-Cocinittee, and review their reports.
b.
Monitor response to NSAR Committee and MY Project Manager recournendations and bring to the attention of the Maine Yankee President, all saf ety related disputes,
disagreements or discrepancies which cannot be resolved at a lower level.
Provides for independent audits of the Maine Yankee Atomic c.
Power Company Operational Quality Assurance Department to verify compliance with the Quality Assurance Program.
d.
Provides for independent engineering review of proposed design changes to verify the adequacy of designs and to assure the quality and consistency with safety and licensing requirements.
Provides for the development, maintenance, and control of e.
special process procedures, such as, NDE, Welding, and Heat Treating.
f.
Provides for technical, engineering, ' licensing, compliance,
operational, and quality assurance support as requested.
g.
Provides for Internal Audits, vendor surveillance,
1 inspection, or audit as requested by the Manager of Nuclear Support.
h.
Provides for emergency preparedness, environmental, fuel management, and nuclear engineering support as requested.
i.
Provides for the development, maintenance, and control af Yankee Nuclear Services Division General Specifications, j.
Provides a qualified Fire Protection Engineer to review design changes to fire protection systems and components.
k.
Review the operational quality assucance program and changes thereto.
]l 3.
Manager - Nuclear Support a.
Reports Directly to the Vice President Manager of 1
O perations.
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Page: 4 of 12 Rev. No.: 0 Date:, september 10, 1980 s
b.
Reviews all changes to the Operational Quality Assurance
-Program Manual.
Provides for review of and compliance.with federal and
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state regulations and standares for nuclear power facilities.
d.
Provides for the control and storage of appropriate, quality assurance records.
Provides for the engineering and quality assurance review e.
of design changes, plant alterations, material / service purchase requests, drawings, specifications' and appropriate procedures.
f.
Provides for the coordination of the engineering r
requirements necessary to support changes related to operation of the plant.
g.
Provides '%ecommended Corrective Action" to be taken on Internal Audit Discrepancies,
h.
Establishes the qualification requirements for the principal Quality Assurance management position to assure competence commensurate with responsibility.
i.
Resolves disputes between Quality Assurance Department and other departments /organizstions, involving quality.
j.
Provides for independent verification of plant operation by individuals or groups who do not have direct responsibility for performing the work, to assure that applicabl-approved procedures, specifications, licenses and safety regulations are satisfiml.
k.
Acts in an advisory capacity in the areas of engineering, licensing, compliance, and quality assurance when requested by the Plant Operation Review Committee (PORC) or the Nuclear Safety Audit and Review Committee (NSARC).
1.
Provides for the coordination of activities necessary to 4
support plant environmental issues.
m.
Provides for the coordination of activities necessary to support plant safety analysis issues.
j i
Provides for the surveillance, inspection, audit of I
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j contractors to assess the control of quality by the contractors.
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Provides for the review-of: nonconformances 'and Jcorrective
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1Provides for-interf acing betwe n the Company _ and Yankee
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- ? operation' Support, Fire Protection), and Quality Assurance.
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l 4'. - ; Plant Manager L a'. [ Reports directly. to the Vice President Mana'ger of I
. Operations.
'b.-
Reviews'all changes lto the Operational Quality Assurance Program Manual.
~ Directs the 'on-site simpiementation. of the Operational
.c.
Quality. Assurance Program, including compliance with all-State and Federal licens'es andiregulations.
d.-
Acts as' Chairman of:the Plant Operations Review Committee i
. with ' authority - and : responsibility' 'a's e'st ablished_ in; the Technicals Specifications 'of the' pfant operating license.
i Assumes overal1Lresponsibility for.all activities at' the e.
plant.
f.
LProvides for the coordination of plant security and Fire Protectionf activities.
g.
. Aces in.an advisory capacity in-the areas of plant activities, such ~as, maintenance, operation, testing, tiraining,1when requested by NSARC.:
- h.
' Provides :f or interf acing between.the' Company and Yankee L Nuclear ~ Services Division for on-site = activities.
Provides forl' h'e review of industry operating: problems with
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t the aim 'ofi inimizing~ likelihood 'of occurrence-at the plant.
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=Provides'for__the coordination.of. activities'necessary to
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Provides; for,the coordination :of; planti activities necessary 1 support (plant reporting' requirements.
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toJsupportithe' plant environmental surveillance programs.
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fl. - Provides for. implementation of the Maine; Yankee Emergency 1
Plan.'
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Administrative Supervisor 1 e
(Reports directily to ' he^ Manager;of Nuclear Support.
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Title:
.Section I. - Organization 1
Page: :6 of 12 I
s Rev. No.: 0
.Date:- September 10, 1980 j
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.b.
Establishes the means for the control and distribution of
~.the Operational Quality A~nrance Program and revisions F
1.
-thereto.
9 Establishes - the means for the control,. distribution,' and y.
c.
-storage of the Quality Assurance. Documents. and^ Records
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-under the jurisdiction of the Manager of Nuclear Support.
Estab1'shes 'the means: for the control and distribution of i
d.-
the Maine; Yankee : audit and surveillance program.
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Director of Plant Engineering Reports directly to the Manager of Nuclear Support.
a.
b.
Maintains the Operational Quality Assurance Program Manual and the associated ' administrative implementing quality.
assurance procedures.
Coordinates the development, review, and implementation of
~
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plant changes and alterations. -
ds-Direct the Plant Inservice Inspection Program.
e.
Directs the engineering reviews of material purchase requests.
f.
Directs the engineering reviews of nonconforman'ces and corrective actions.
g
. Directs independent engineering and quality assurance reviews of maintenance and repair activities..
I h.
' Maintains and disseminates information regarding codes,
, standards, criteria, and guidelines to ' applicable. personnel.
i.
Coordinates interfacing plant engineering activities
.between. the : Company, Yankee Nuclear.' Services Division, and outside agencies, j.
Directs. plant surveillance programs assigned by the Manager p
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'of Nuclear Support.
k.
Directs plant test programs assigned by the Manager of i
. Nuclear Support.
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Acts in an advisory capacity in the area of plant engineering when requested by PORC or NSARC.
m.
Provides for technical support to the plant.
n.
Provides for the documentation and maintenance of quality assurance records associated with plant engineering.
7.
Director of Nuclear Engineering and Licensing Reports directly to the Manager of Nuclear Support.
u.
3f.,[I b.
Acts in an advisory capacity in the areas of licensing and nuclear engineering when requested by PORC or NSARC.
c.
Directs the licensing activities necessary to support and maintain the Technical Specifications, Safety Analysis Report, and other licensing issues.
d.
Establishes and maintains radiological environmental surveillance programs, e.
Provides for the documentation and maintenance of quality assurance records in licensing.
f.
Coordinates interf acing licensing activities between the Company, Yankee Nuclear Services Division, and outside agencies.
g.
Coordinates interfacing nuclear engineering activities between the Company, Yankee Nuclear Services Division, and c itside agencies.
h.
Establishes Emergency Plans pursuant to state and federal regulatory requirements and Company policy.
i.
Provides for the general supervision and coordination of all core camponent design and fuel cycle economic ac tivities.
8.
Director of Operational Quality Assurance a.
Reports directly to the Manager of Nuclear Support.
i b.
Assures that the Operational Quality Assurance Program i
i satisfies the requirements of 10CFR50, Appendix B ANSI N18.7-1976.
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. Directs the reviewof design; changes and material purchase!
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requests for; adequacy of ; quality : requirements..
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' Directs the-^ evaluation, inspection ahd/or surveill'ance of; t
contractor / vendor activities at the operating plant to assure effective lines Lof1consunicationLand compliance with
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i the: applicable criteria of -10CFR50, Appendix B and ANSI'
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D'.ecta the -inspection, surveillance 'and/or - audit of-i
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4 c.ctivities ~ affecting the quality of structures,, systems and ?
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W' components - important to 'saf ety.
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Ensures through -verification that the Program is implemented for all activiti~es requiring quality assurance.
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Directs the ' independent verification of plant operati~onal activities, to. assure that applicable approved l procedures,-
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s peci fications,.- licenses iand safety regulations !are satisfied.
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. Reviews all changes to the Operational Quality Assurance -
' Program Manual.
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. Ensures that' the' Program is modified and/or revised as
- standards, regulations and experience dictate.
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- j.. Directs ~ the _ quality assurance reviews of nonc* nforme.nces.
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Coordinaties interf acing quality assurance activities -
between the Company, Yankee Nuclear Services' Division, and l outside agencies.
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Acts in an advisory capacity:in [the crea of quality
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.~acsurance when requested by PORClor NSARC.
Directs the Internal-Audit Program to verify compliance m.
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with all' aspects of the Quality Assurance Program and to determine the effectiveness of the program..
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Provides for the documentation and maintenance of -
department quality. assurance records.
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Provides' for the stoppage of unsatisf actory work.
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- Provides -for review and inspection of. repair and -
haaintenance activities ~.
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Director of Operatiobal Support.
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-. Reports idirectlyito 'the Manage' D,.
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JActsiin(anfadvisory capacity.in the area;of regulatory -
compli'ance"when requested. by PORC or NSARC.
Lc. ; 1 Directs Lthe -activities necess'ary-lt'o support f ederal and
' Lstatejenforcementdocuments.-
4 d.
-Provides for the documentation and maintenance 1of quality assurance records in regulatory compliance activities.
.' Coordinates interf acing compliance, activities between the -
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Company, Yank'ee Nuclear Services Division, and outside agencies.-
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s f.-. Provides for. operati'ona1Lsupport to the plantV
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- 10. Administration 1)epartment Head a.-
Reports directly to "the Plant Manager.
- b.. ' Provides-for; an approved Plant Training Program and the impicmentation tof the' program..
Provides -for theicoordination of activities necessary to
- c.. ' maintain the Plant Trainisg Manual.--
.d.-
Establishes the means for-the control, distribution, and storage 'of the Quality. Assurance Documents and Records
~
under :.the ~ jurisdiction of the Plant Manager.
J e.;
ProvidesL for an approved Fire-Protection Program and training of personnel-therein.
?Provides for 'an approved Security Program and training of
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- personnel therein.~
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- g.. f Provides for' the. preparation of requisition for purchase orders.-
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lh.,. Provides fe.- the control and identification of material and
- equisnent'upon receipt, storage, and issuance.
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Provides for the' control and storage Jof Quality Assurance l
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.docisment'ation of: purchased' materials.
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Providesifor-the ' control'and maintenance of the plant spare-ipartsLinventoryl system.-
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Title:
Section I. Organization
%km dD Page:
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Date:
September 10, 1980 I
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Establishes the retention period for the-Quality Assurance Documents and Records.
- 11. Maintenance Department Head a.
Reports directly to the Plant Manager.
b.
Prepares, schedules and directs approved maintenance ac tivities.
Directs preparation and implementation of procedures c.
utilizing sound engineering policies and practices for the installation of new material, equipment or spare parts.
d.
Provides for an approved program of preventive maintenance, calibration, and testing for instruments and electrical / mechanical equipment in conformance with established approved procedures, Provides for the Unplenentation of a continuing e.
surveillance program as cutlined in the Technical Speci fica tions.
f.
Provides for the training and qualification of department personnel in the application of special processes, such as, NDE and Welding.
g.
Provides for the documentation and maintenance of quality assurance records in Maintenance Department a' tivities.
c
- 12. Operations Department Head a.
Reports directly to the Plant Manager.
b.
Assures plant operations are conducted in accordance with approved documents and specifications, c.
Provides for system surveillance and operational testing.
d.
Provides Maintenance Requests for the repair or replacement of defective parts and/or components.
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Verifies the operability of systems and/or camponents e.
following maintenance, or changes by providing for the performance of written test documents which incorporate the requirements and acceptance criteria contained in 1
applicable design documents.
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Provides for the safe handling' of core e4 reactor
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components during1 refueling opeistions.
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Provides for. the 'dormentatijn' and maintenance.of quality.
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assurance records ~ in Operation Department activities.
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' Provides for the development, control, 'and maintenance of operatingand emergency, operating' procedures.
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- 13.. ' Technical Support Department Head ;
=E a.-
Reports directly to' the Plant Manager.
b.
Provides for the general ~ supervision and coordination of reactor physics and nuclear, tests for plant operation and
' adherence to Technical Specifications.
'c.
L Follows ' and reviews radiation protection programs and activities at the plant.
d.
Establishes and maintains' radiological and nonradiological
~
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effluent. release control and -surveillance program. -
e.
Provides for the maintenance of refuelin's procedures -
~
relative' to fuel core components handling and inspection.
zi f.
Performs fuel cycle, nuclear engineering, and economic studies' requested by plant manager.-
i g.
Directs ' the' on-site activities necessary to support federal and~ state enforcement documents.
h.
Provides for the documentation and maintenance of quality
. assurance records in chemistry, health physics,
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enviror.asncol', reactor physics and nuclear ~ fuel.-
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- i. "ProviSs for the control and maintenance of plant. computer
. systems.
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Provides. for..the preparation 'and maintenance of procedures
' associated with radiological, chemistry, and reactor i
w iy physics.
s E.
REVIEW AND ' AUDIT
~
Two committee'sLhave been' established for the operating plant whose-objectives are to insure the plant. is'~ operated safely, utilizing.
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accepted, engineering prac tices. The comunittees are charge / with,
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, making:recossendations to modify 1 operational methods or safety j
- precautions; when' appropriate.
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J Lone Committee, the Plant Operations Review committee, is~ made up of:
E Plant personnel. The 'other Committ'ee, the Nuclear-Safety Audit - and
. Review Committee,;is made up'~of individuals not having lina -
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responsibility for the.foperation. of. the plant.
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-. Plant Operations Review Committee ;-
See -Section! 5.5, " Review and Audit" of Technica: Speci fications ~-
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. to ' the Operating License. DPR-36.,
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' Nuclear S'afety Audit and Review Committee i
See Section 5.5,:" Review and Audit" of Technical Specifications to the Operating License DPR-36.-
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e MAINE TANKEE ATOMIC POWER COMPANT q
PRESIDENT ORGANIZATIONAI, CIL4RT I
I PRESIDENT &
- PR ENT.
. PRE DENT -
A ER 0 g
VICE PRESIDENTS ADMINISTRATIVg FINANCE OTFRATI^NS.
SERVICES I
1 4
M/INE YANKEE.
NUCLEAR SAFETY AUDIT & REVIEW
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PROJECT MANACER TTEE I
MANAGER.
PIANT NUCLEAR SUPPORT MANACER' l
1 MAI!rrENANCE TANKEE NUCLEAR ADMINISTRATIVE SUPERVISOR DEPARTMENT l
SERVICES.
r HEAD 8
DIVISION STAFF I
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DIRECTOR 1
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NUCLEAA
, ADMINISTRATION DEPAR N l
ENCINEERING HEAD ttrTne7 4 t
DIRECTu'.s I
- 0NE CORPORATE OFFICER OF TNSD IS ALSO
.'OPERATIURM.
TECHNICAL I
A CORPORATE OFFICER OF MTAPC, AND SHAL1.
QUALIT-SUPPORT BE REFERRED TO AS "VICE PRESIDENT (TNSE)"
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ASStIRAN M DEPh g G l
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DIRECT 0g OPERATIONS PLANT DEPARTMENT l
ENGINEER!NC HEAD-l DIRECTGR OPERATIONAL MAINE YANKEE TANKEE ATOMIC ELECTRIC CO.
SUPTORT ATOMIC POWER Co.
3 NUCLEAR SERVICE DIVISION i
(MTAPC) 5 (TNSD) l l
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Title:
Section II. QA Program Page 1 of 5 Rev. No.: 0 j-Date:
September 10, 1980 j
'II. QUALITY ASSURANCE PROGRAM t'
-A.
SCOPE i
The Quality Assurance Program provides control' over activities
-affecting the quality of identified structures, systems 'and components, to an extent consistent with their importance to safety.
~
The program takes into account the need for special controls, proce'sses, equipment, tools, and skills to attain the required ~
quality and the need for verification of qualitv by inspections, evaluations or tests.
B.
RESPONS IBILITIES Compliance with the requirements of the Operational Quality Assurance Program is the responsibility of all personnel involved with-activities affecting operational safety. Individuals responsible for establishing and executing the Operational Quality Assurance Program are delineated in Section I, " Organization", of the program.
Operational Quality Assurance shall regularly review the status and adequacy of the quality assurance program.
C.
IMPLEMENTATION Establishment of -an effective Operational Quality Assurance Program is assured through consideration of and conformance, where applicable, with the below listed ANSI Standards and federal documents. Implementation of this program is assured through Quality Assurance procedures derived from Quality Assurance policies, goals and objectives.
l-1.
Title.-10 of the Code of Federal Regulations, Part 50, Appendix B, Quality Assurance Criteria
- for Nuclear Power Plants 2.
ANSI N18.7-1976, Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants 3.
~ ANSI N45.2-1971,- Qality Assuranca Pr_ogram Requirements fo_r Nuclear Power Plants 4
4.
ANSI N45.2.1-1973, Cleaning of Fluid Systems and Associated Ccaponents During Construction Phase of Nuclear Power Plants ANSI N45.2.2-1972', Packaging, ' Shipping, Receiving, Storage and 5.
1 H
Handling of Items for Nuclear Power Plants it a'I-
.6..
ANSI N45.2.3-1973, Housekeeping During the Construction Phase of
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Nuclear Power Plants -
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Titles: Section 'II. QA Program
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Pages-2 of 5c F
Rev. No'.: - 0 J
Date:
September 10, 1980-7[
ANSI N45.2.4-1972, Installation, Inspection and Testing.
"'j-Requirements for Instrumentation and Electric Equipment-During the Construction of-Nuclear Power Generating Plants 8.-
ANSI N45.2.5-1974,-Supplementary Quality Assurance Requirements =
for Inst'allation, Inspection ~and Testing of Structural Concrete
- and Structural Steel During the Construction Phase of Nuclear Power Plants '
9.
ANSI N45.2.6-1973, Qualification of Ins pection,' Examination, and
- Testing Personnel for the Construction Phase of Nuclear Power Plants
~
10.
ANSI.N45.2.8-1975, ' Supplementary Quality Assuran'ce Requirements for Installation, Inspection and Testing of-Mechanical Equipment and Systems for the Construction Phase of Nuclear Power Plants
- 11. ANSI N45.2.9-1974, Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants 12.
ANSI-N45.2.10-1973,. Quality Assurance Terms and Definitions 13.
ANSI N45.2.11-1974, Quality Assurance Requirements for the Design of Nuclear Power Plants 14.
ANSI N45.2.12, Draf t 4, Revision 2,. (January 1, 1976),
~
Requirements for Auditing of Quality Assurance Program for Nuclear Power Plants -
- 15. ANSI N45.2.13-1976, ' Quality Assurance Requirements' for Control of Procurement of Items and Services for Nuclear Power Plants
- 16. ANSI. N18.1-1971, Selection 'and Training of Nuclear Power Plant
{
Personnel h;
- 17. - ANSI N18.17-1973, Industrial Security for Nuclear P_ower Plants is
!)
. 18. ANSI' N101.4-1972, -Quality Assurance for Protective Ccatings
[
App 11ed to' Nuclear Pacilities
'hk 19; Regulatory. Guide -1.8,' Revision.1, '(September,1975) Personnel lp
. Selection and Training '(Endorses ANSI N18.1-1971) y z20.1. Regulator y Guide" l.30,. August.11, 1972, Quality Assurance Requirements forEthe Installation, Inspection and Testing of -
f,
' Instrumentation and Electric Equipment (Endorses ANSI 2
N45.2.4-1972) y a-p
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Title:
Section II. QA Program 4
we Page:
3 of 5 Rev. No.:
0 Date:
September 10, 1980 s
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- 21. Regulatory Guide 1.37, March 16,1973, Quality Assurance Requirements for Cleaning of Fluid Systems and Associated j
Components of Water-Cooled Nuclear Power Plants (Endorses ANSI N45.2.1-1973) 22.
Regulatory Guide 1.38, March 16,1973, Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage and Handling of Items fo-Water-Cooled Nuclear Power Plants (Endorses ANSI N45.2.2-1972) 23.
Regulatorv C !de 1.39, March 16,1973, Housekeeping Requirements for Water-Cooled Muclear Power Plants (Endorses ANSI N45.2.3-1973) 24.
Regulato3y Guide 1.54, June,1973, Quality Assurance Requiremeats for Protective Coatings Applied to Water-Cooled Nuclear Power Plants.(Endorses ANSI N101. 4-1972)
- 25. Regulatory Guide 1.58, August 1973, Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel
. (Endorses ANSI N45.2.6-19 73).
26.
Regulatory Guide 1.64, Revision 1, (February,1975), Quality Assurance Requirements for the Design of Nuclear Power Plants (Endorses ANSI N45.2.11-1974) 27.
Regulatory Guide 1.74, Februsry,1974, Quality Assurance Terms and Definitions (Endorses ANS N45.2.10-1973) 28.
Regulatory Guide 1.88, August, 1974, Collection, Storage and Maintenance of Nuclear Power Plant Quality Assurance Records (Endorses ANSI N45.2.9-1974) 29.
Regulatory Guide 1.94, Revision 1 (April,1976), Quality Assurance Requirements for Installation, Inspection and Testing of Structural Concrete and Structural Steel During the
' Construction Phase of Nuclear Power Plants (Endorses ANSI N45.2.5-1974)
The plant Technical S acifications shall be the NOTES:
1)
E governing document when determining requirements to be imposed in all areas which are addressed in both technical specifications and the above noted guides and standards, 2)
Revisions to the above listed documents will be i
4 considered for applicability to the Maine Yankee Operational Quality Assurance Program upon written direction thereof by the Nuclear Regulatory Commission - Of fice of Nuclear Reactor Regulations - Quality Assurance Branch.
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Title:
Section II. QA Program Page: 4 of 5 Rev. No.: 0 Date:
September 10, 1980 l
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3)
ANSI Standard N18.7-1976 is the endorsing document for all other above referenced ANSI Standards. All such. endorsed ANSI Standards will be implemented to the degree of applicability indicated in ANSI N18.7-1976.
4Property "ANSI code" (as page type) with input value "ANSI N18.7-1976.</br></br>4" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process.)
This Program shall be applicable to those activities requiring quality assurance which occur commencing 90 days af ter acceptance of the Program by the Nuclear Regulatory Commission.
5)
Programmatic and organzational changes (other than those editorial in nature) made to Section I and II, respectively shall require Nuclear Regulatory Commission notification:
programmatic changes prior to implementation and organizational changes within 30 days following the effective date of change.
- Exceptions and alternatives to the provisions contained in this Standard / Guide are detailed in Appendix B.
D.
MANAGEMENT EVALUATION The Vice President, YNSD, directs a thorough evaluation of the established Operational Quality Assurance Program by assigning the Nuclear Safety Audit and Review Committee the task.of reviewing for caspliance with and evaluating the effectiveness of the quality assurance program.
E.
TRAINING 1.
The Plant Manager i: responsible for the indoctrination and tra.ining of plant staff personnel performing activities effecting operations or requiring quality assurance, and for ensuring that, where required by the Technical Specifications, operators are formally licensed or qualified.
2.
The Manager of Nuclear Support is responsible for the indoctrination and training of Maine Yankee personnel other than MY plant staff personnel performing activities affecting operations or requiring quality aesurance.
3.
The indoctrination and training programs shall provide the following:
a.
Instruction as to the purpose, scope, and implementation of quality assurance manuals, instructions, and procedures.
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Title:
Section II. QA Program Pages. 5 of 5 Rev. No.: 0 Date:. Sept ember 10, 1980 a
b.
Training and qualification.in.the principles and techniques of the activityJbeing performed.
c._
Maintenance of personnel proficiency by retraining,
~
reexamining,' and/or recertifying.
d.
_ Documentation of the training sessions including content, attendance, dates and results.
- 4.
-The Vice President-Yankee Nuclear Services Division is responsible for the indoctrination and training of _YNSD personnel, to an approved training program,' when performing ?
activities affecting operations or requiring quality assurance.
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Title:
Section III. Design' Control-
.Page:
~1 of 3-
'Rev.,No. :~0
.Date ~ September 10, 1980 Lo 4
~ III. DESIGN CONTBOL -
~
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SCOPE j;
,. This section of the Operational Quality Assurance Program establishes
~
measures' to assure that the design of and. changes to = structures,
systems, and components covered by the Operational-Quality Assurance
. Program are controlled.-
B.
RESPONSIBILITIES
'l.
The Operational-Quality Assurance Department shall be I
responsible for:
Providing for Surveillance of the implementation of design a.
control.
-b.
Review of engineering drawings and specifications to assure
~
that appropriate - design control practices, checks, and reviews are included, c.-
Review of design bases'for inclusion of quality
~
requirements.
2.
The Plant Engineering Department shall be responsible for:
The ' design and Leontrol of design activities 1(including a.
design :interf aces) for the change. of structures, systems,
or components including the requirement for l' dependent n
review.
P b.
. Identification, documentat on, and control of deviations i
from specified design requirements and/or quality standards, c.-. - Delineation.of acceptance criteria for inspections and tasts..
3.
' The: Plant Operations. Review Committee shall be responsible for:
. Review of.all proposedL plant design changes and a.'
recommending' their approval or disapproval to the Plant 1 Lf Manager.
-t ib.:
Determination of whether proposed. changes involve -
j :.
~ unreviewed e safety questions.
d '/
q 3 4. :. <TheIPlant Manager:shall be{ responsible for: -
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a.
- Review of the' recommendations ofi the ' Plant Operations -
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~ Review Committee'.-
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- Section III. Design Control-Page:
2 of 3
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Date: September 10, 1980 i -
b..
Review and approval of proposed plant changes.
'5.
The Nuclear Safety Audit and Review Committee shall be responsible for the review of design changes.
6.
The Yankee Nuclear Services Division shall be responsible for:
Establishment of approved policy for processing engineering a.
design ' changes.
b..
Independent engineering review of proposed design changes to verify the adequacy of designs andito assure the quality and consistency with safety and licensing requirements.
C.
IMPI.EMENTATION 1.
Satisf action of this criterion shall' be assured through the implementation of the Maine Yankee and Yankee Nuclear Services
' Division actions listed below:
Correct translation of applicable regulatory requirements a.
and design bases into specifications, drawings and written-documents, b.
Application of suitable design controls to such act'.vities
. as reactor physics; seismic, stress, thermal, hydra 21ic, radiation, and accident analyses; compatiblity of materials; and accessibility f or inservice inspection,
. maintenance and repair.
~
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- Design reviews to assure that design characteristics can be c.
controlled, inspected and tested, d.
Performance of proper selection and accomplishment of design verification or checking process such as design reviews, alternate calculations, qualification testing or test programs. When a test program is used to verify the adequsey of a design, a qualification test of a prototype l-unit under the most -adverse design conditions shall be used.
Subjection of design and specification changes to the same e.
- design controls and approvals that were applicable to the original' design unless designated in writing to another responsible organization.
I f.
Documentation of errors and deficiencies in the design j
process that adversely.~ affect safety classified structures, i-systems, and components; performance of corrective action I
to preclude repetition.
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Title:
Section III. Design Control E
me rage:
3 of 3 4
Rev. No.: 0 Date: September 10, 1980 a
Review of standard "off the shelf" commercial or previously g.
approved materials, parts, and equipment that are essential
'j to the safety functions of structures, systems, and components, for suitability of application prior to 4
selec tion.
f h.
Selectica of suitable materials, parts, equipment, and processes for saf ety classified structures, systems, and
- componen t s.
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' Titl'e: 1 Section IV.' Procurement Document Control Pages -1:of 2
.Rev. No.: 0 Date ~; September - 10,'1980 m
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PROC Elfr DOCUMM COMROL -
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A.,
SCOPE-b
-This: section of the. Operational. Quality' AssurancelProgram establishes.
~
the ' measures. necessary to' assure that applicable - requirements
- j'
.necessary to < assure adequate quality, are: suitably included or g
referenced in the dociaments for procurement of material, equipsent <
C.
and services.:
i
' B.. RESPONSIBILITIES 7
1:
- 1... The Operational Quality Assurance Department shall' be l
~
respons,ible for:
i
'a.
Surveillance and/or audit of procurement document control, including-the preparation, review,',and approval of purchase p-requests for material, equipment, and services covered ~by
}-
the Operational Quality Assurance Program.
i.
b.
~ Review of procurement documents initiated ~ by Maine Yankee i
to assure that applicable' requirements necessary to assure.
i adequate quality are? suitably included or referenced in the documents for procurement 1 of material, equipment, and l-services.
k 2..
Maine Yankee -sha' ll be responsible for:
, 2,
.a.
The preparttion, review, issue, and control o,f purchase documents.
l b.
Preparation. of details as to how purchase documents are
~
prepared, reviewed, approved, issued, and controlled.
3.-
The Plant Engineering Depart:hent _ shall be responsible for:
4
'a.
Preparation of engineering specifications whi::h detail the technical;and quality requirements for material,~ equipment
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4 and services.
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.b.-
Providing technical and quality requirements for'materiil,
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equipment', and service purchases.
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C. 'IMPLE ENTATION-q t
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71.f [Satisf action of. the ' criterion shall be assured through the -
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. implementation of the Maine Yankee actions ' listed below:.
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'a.
Documentation of the review and approval of procurement
documents prior to release and -availability of this-0 documentation for verification. -
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Title:
Section IV. Procurement Document Control Page:
2 of 2 l
Rev. No.: 0 Dat e:
September 10, 1980 l
b.
Identification of the vendor's quality assurance i
requirements applicable to the items or services procured, l
Identification in the procurement documents of the c.
documentation to be prepared, maintained, and/or submitted to the purchaser prior to use, such as:
i 1.
drawings, specifications, procedures i
2.
inspection and fabrication plans 3.
inspection and test records 4.
personnel and proe 2 dure qualifications 5.
chemical and physical test results of material P
6.
the company's right of access to the vendor's facilities and records for surveillance te procurement s pecifica tions,
d.
Review and approval of changes and revisions to procurement documents at least -aquivalent to those for the original document.
Control of procurement documents for spare and replacecent e.
parts at least equivalent to that used for the original e o,ai psent.
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Title:
- Section V. Instructions, Proc. & Drawings Page:
1 of 2 Rev. No.: 0 Date:
September 10 1980 a
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V.
INSTRUCTIONS, PRO DURES, AND DRAWINCS-A.
SCOPE' b'j:
This. section of the Operational Quality Assurance Program establishes the measures for prescribing and accomplishing activities requiring
~
' quality assurance in accordance wi,th approved drawings, instructons,
. or.procedutes.
B.
RESPONSIBILITIES
. Persons ~ preparing and ; approving documents are responsible for assuring that specifications ~, ' instructions,. procedures and drawings include appropriate qcsntitative or qualitative : acceptance criteria for determining that activities have been satisfactorily accomplished; assuring that the applicable criteria of 10CFR50 Appendix B and/or ANSI N18.7 are specified; and assuring that the documents are kept. current. In addition, the following departments -
have the distinct responsibilities delineated below.
1.
The Operational Quality Assurance Department shall be responsible for:
a.
Providing for surveillance of. instructions, procedures, and drawings.
b.
Review and apptoval of all Plant Operational Quality Assurance procedures.
2.
Maine Yankee shall be responsible for the preparation, review, approval, maintenance, and implementation of all instructions and procedures associated with Maine Yankee activities.
3.
The. Yankee Nuclear Services Division shall be responsible for:
Updating and control of original drawings and special a.
. process. procedures and distribution of copies thereof.
4..
The Plant Operations Review Committee shall be responsible for reviewing procedures affecting nuclear safety prior to their approval by the Plant Manager.
C.
IMPLEMENTATION I
1.
Satisf action of this criterion shall be assured.through the Unplementation of the Maine Yankee and/or Yankee Nuclear u
Services Division actions listed below:
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Title:
Section V. Instructions, Proc. & Drawings :
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-2 of 2 Rev. No.:
'O Dates-September 10, 1980 s
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_ a.
. E stab 1'ishmentJof provisions which clearly delineate the sequence of actions to be accomplished in the preparation, 3
review, approval, and control of instructions, procedures,
]f and-drawings.-
' b '.
Review of inspection plans; ' test, calibration, special.-
process, maintenance' and repair procedures; drawings and specifications; and changes thereto.
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Title:
Section VI. Document Control l
Page:
1 of 3 Rev. No.: 0 Date:
September 10, 1980
.J VI.
DOCUMENT CONTROL
.i A.
SCOPE 1
This section of the Operational Quality Assurance Program establishes the measures for controlling documents, including revision thereto, which affect quality activities.
B.
RESPONS IBILITIES 1.
All participating departments shall establish document control measures which provide for the following:
Identification of departments responsible for preparation, a.
review, approval, and control of documents.
b.
Identification of documentation to be used in performing ac tivity.
c.
Coordination and control of interf ace documents, d.
Establishment of distribution lists.
e.
Action to be taken for obsolete or superseded documunts.
In addition, the f,11owing departments have the unique responsibilities delineated below:
[
2.
The Operational Quality Assurance Department shall be responsible for surveillance and/or audit of documsnt control systems at Maine Yankee and vendors.
3.
Maine Yankee shall be responsible for:
4 Controlling the issuance of operating, maintenance, repair, a.
refueling, and change documents.
b.
Distribution and maintenance of all approved and/or revised documents assuring quality at the location where the activity is performed.
A system of review, approval and distribution of Maine c.
Yankee Quality Assurance documents.
The Yankee Nuclear Services Division shall be responsible for:
4.
a.
Controlling the issuance of engineering drawings, General Specifications, welding and nondestructive examination procedures.
B
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1 Rev. No.: 0
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September 10, 1980 b.
Revision and distribution of welding and nondestructive examination procedures.
i c.
Maintenance and distribution of General Specifications and controlled drawings.
5.
The Vice President - Manager of Operations shall be responsible for establishing the means for the control and distribution of the Operational Quality Assurance Program, and revisions ti,ereto.
C.
IMPLEMEETATION 1.
Satisf action of this criterion shall be assu-ed through the Laplementation of the Maine Yankee and/or Yankee Nuclear Services Division actions listed below:
a.
Review and approval of document changes by the same organizations that performed the original reviaw and approval or by other responsible organizations delegated by Maine Yankee.
b.
Inclusion of approved changes in instructions, drawings, and other applicable documents prior to placing the system in cpexeting status.
c.
Provision of availability of documents at the location where the activity is to be performed prior to commencing the work.
d.
Establishment, revision, and distribution of a master list or equivalent to identify the current revision number of instruction, specifications, drawings, or other quality assurance documents.
e.
Control of documents identified as follows:
1.
Design specifications 2.
Design, manuf acturing, construction, and installation drawings 3.
Operational Quality Assurance Program, maintenance, and operating procedu:es 5.
Manuf acturing, inspection and test instructions l-
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Title:
Section VI. Document Control Page:
3 of 3 Rev. No.: 0 Dat e:
September 10, 1980 s
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Test documents 7.
Design change requests 8.
Nonconformance reports 3
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Title:
Section VII. Control of Purchased Mat' 1, E =-wS Equip. & Services Page:
1 of 2 Rev. No.: 0 Date:
September 10, 1980 VII. CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES i
A.
SCOPE This section of the Operational Quality Assurance Program establishes measures to assure that purchased material, equipment and services, whether purchased directly or through contractors and subcontractors, conform to the procurement documents.
B.
RESPONSIBILITIES 1.
The Operational Quality Assurance Department shall be responsible for:
a.
Provide for evaluation of vendor quality assurance programs.
b.
Provide for maintenance of a listing of qualified vendors based upon (a).
c.
Surveillance of plant or vendor material and/or services control.
d.
Receipt inspection of material and equipment.
2.
Maine Yankee shall be responsible for:
a.
Control of material and equipment.
b.
Evaluation of purchased services during and/or af ter completion of the service.
C.
IMPLEMENTATION 1.
Satisf action of this criterion shall be assured through the Unplementation of the actions listed below:
a.
Evaluation of vendors based on one or more of the following:
1.
Vendor's capability to comply with the applicable criteria of 10CFR50 Appendix B and/or ANSI N18.7.
2Property "ANSI code" (as page type) with input value "ANSI N18.7.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
Review of vendor's previous records and performances.
3.
Surveillance of vendor's facilities / services and QA program to determine his ability to produce the item to the purchase specifications.
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Title:
Section VII. Control of Purchased Mat'1,-
Equip. & Services 7
l' Page 2 of 2-Rev.LNo.: 0
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Dat e:
September 10, 1980
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b.
Documentation and maintenance of the results of vendor
~
evaluations.
c.
Planned vendor surveillances which provide for:
I 1..
Specification of processes to be witnessed or verified, the surveillance method and documentation required, and personne1 ' responsible for performing the survelliance.
2.
Assurance that. the vendor comp 1ies with the quality requirements by surveillance of in-process work.
d.
Transf er of the following records from the vendor to Maine Yankee:
1.
Documentation that identifies the purchased material and the specific procurement requirements met by the item.
2.
Documentation that identifies any deviation from procurement requirements including a description of those deviations dispositioned " accept as is" or
" re pair".
Review and acceptance of vendor documents by a responsible e.
quality assurance individual.
f.
Receipt inspection of vendor furnished' material to ' assure:
1.
Material is. identified' and conrorms with receiving documentation identification.
t 2.
Material and documentation are inspected in accordance '
with predetermined instructions and are determined acceptable. prior to use.
3.
Ins pection records or certificates of conformance atesting to material acceptability are on-site prior to use, v
4.
Items are. identified as to their inspection status prior. to' release for controlled storage, -installation or further work.
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Evaluation of the vendor's. effectiveness to' control. quality
.is performed ~ at intervals consistent.with the importance, complexity and quality of. the iten.
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- TitlesSection VIII. Identification & Control' j
~ of Mat'1, Parts,7 6 Components.
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o-m Dates. September 10, 1980'
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l VIII.IDENTIFICATI0tt AND ColtrML OF MATERIAL,' PARTS,' AND COMPONENTS I
~A.
! SCOPE, This section~ of the Operational Quality Assuratice Program establishes' w
the' measures for. identification and - control necessary ? to prevent..the use of incorrect orL defective material, ' parts, and components.
.B.
RESPONSIBILITIES -
1.
' The Operational' Quality ' Assurance department shall be responsible ~ fort-
'a.
t Surveillance, audit and/or ins'pection of the control and
~
issuance of materials, parts, and components covered by the F
Operational Quality Assurance Program.
b.-
Review :of. vendor Quality Assurance programs for-J
' traceability;of materials through the use..of heat number, part number,lor serial ntsaber, either on the item or on records traceable to the items.
2.-.
Maine Yankee lshall be responsible fort A
Preparation', review and approval of documents-for the a.
identification and control of materials, parts, and components.
b.-.
Maintenance of traceability 'of materials, parts, and components received, stored, installed, and used at the Plant.
I_ PTE)ENTATION C.
M 4
1.
! Satisfaction of this eriterion.shall be ' assured through ~the i
implementation of -the actions -listed belos:
t Traceability-of -the~ identification' of materials and parts
- a..
' to the appropriate 'doctamentation Lsuch as / drawings,
! specifications', purchase orders, manuf acturing and
- f inspection documents, deviation reports, andj physical and
.i chemical mill test reports.
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Identification' of thehitem in a location and with a method e
'j which does not: affect its fit, functionLor. quality.--
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Documented verification.of Jcorrect identification o'f'
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iD z aaterials,c parts,l and " components prior ~ to release for use.
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Title:
Section 'IX. Control of-Special Processes T
.. Pagesl-I of 2-
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-Dater. September 10, 1980 4.
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' IX. : COWERDL OF SPECIAL PROCESSES.
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' A. ' SCOPE l
l
- This. sec' tion of the Operational Quality A'ssurance Program establishes l,
lthe measures. necessaryito assure that'special processes, including
. welding, heat treating, and _-nondestructive testing, are controlled and.l accomplished by qualified personnel in' accordance lwitti applicable.
~
codes,. standards, specifications,- criteria and other special -
Y requirements..
- B.
RESPONSIBILITIES :
-1.
The Operational Qualit'y Assurance Department sh'all be responsible for:
a.
Providing surveillance, audit and/or. inspection. of the control'of special processes.
b.
Providing performance and/or evaluation of certain nondestructive tests in accordance with Yankee Nuclear Services Division Welding and Nondestructive Examination Procedure s"'.
Providing training, qualification, and requalification of c.
Maine Yankee personnel in nondestructive testing (liquid penetrant examination).
V d.
Review of.special process documents provided by vendors.
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'J 2.
The Yankee Nuclear Services Division 'shall be responsible for:
i Preparation of documents for velding, heat ' treating, and a.
nondestruetive examinaeions.
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. Maine iYankee shall; be. responsible' fcr:
3.
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a; Assurance :that ciaintenance 'an'd change work involving special' processes 'are = performed by qualified personnel in accordance with approved. documents..
b.
- Control of material used in-special. processes by plant personnel.-
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. c., ; Review and[ approval' of special. process documents provided
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Title:
Section IX. Control of Special Processes I
SummWS
'Page 2 of 2 Rev. No.: 0
' ~
Date: ' September 10, 1980 a
C.
IMPLEMENTATION 1
j 1.-
Satisf action of :this' criterion shall be assured th' ough the.
r Laplementation of Maine Yankee and/or Yankee Nuclear Services-I Division actions listed below:
Qualification records of documents, equipment, and a.
personnel. connected with special' processes in accordance with applicable codes, standards, and specifications.,
.b.
Special processes accomplished in accordance with written process. sheets or equivalent with recorded evidence of verification.
. Maintenance and updating of qualification records of c.
special process documents, equipment, and personnel.
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- iitle Section X. Insoection Page 1 of 2 Rev. No.: 0 l
Date:
September 10, 1980 s
l X.
INPSECTION A.
SCOPE a
1-This section of the Operational Quality Assurance Program establishes measures for inspection of activities requiring quality assurance to verify conformance'with approved procedures, drawings, specification and instructions.
B.
RESPONSIBILITIES 1.
The Operational Onslity Assurance Department shall be responsible for:
Review of engineering specifications for inclusion of a.
inspection requirements and acceptance criteria.
i b.
Review of documentation pertinent to the Inservice Inspection Program.
c.
Surveillance of inspection activities and personnel.
d.
Incorporation of mandatory witness points for plant activities.
e.
Incorporation of mandatory witness points for vendor / service group activities.
f.
Writing and approving inspection instructiions.and check lists.
o 2.
Maine Yankee shall be responsible for:
a.,
Assuring that activities requiring quality assurance meet predetermined requirements.
~b.
Providing qualified personnel and necessary equipnent for examinations to assure quality work.
C. ' IMPLEMENTATION
' 1.
Satisf action of this' criterion shall be assured through the implementation of ~ the actions listed below:-
Independence' of pers'onnel performing-the inspection from a.
the personnel performing the. activity being inspected.-
b.-
Use of instruction or check lists which incorporate the details' list +' in Section XVII Item c ol.a.
Use -of necessary ' drawings and soecifications when c.
- performing ~ inspection operations.
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' Rev. No.t- 0
- Dat e:
September 10, 1980
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Inspection' of repairs ~ and replacements in accordance with'-
- the original design and inspection requirements lor acceptable alternatives.
Surveillance of processing methods,. equipment, and
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l personnel when dir( ct inspection is not possible.
Qualification of inspectors in accordance with applicable -
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codes,. standards, and company training programs; and maintenance of qualifications 'and.' certifications.
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Review of maintenance' documents by qualified personnel knowledgeable. in quality. assurance' to determine the need i
for inspection,-identification of inspection personnel, and r1 documenting inspection results.-
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Title:
Section XI. Test control Page:
1 of 2 j
Rev. No.:
0-Date:
September 10, 1980 J
s XI.
TEST CONTROL A.
SCOPE This section of the Operational Quality' Assurance Program establishes the measures for a test program to demonstrate that structures, systems, and components will perform satisf actorily in service.
B.
RESPONSIBILITIES.
1.-
The Operational. Quality Assurance -Department shall be responsible fort a.
Providing surveillance of the. control of the test program.
b.
-Surveillance:of the documentation generated during the test
(
pro gram.
2.
The Plant Engineering Department shall be responsible for:
Preparation o review of specifications, requirements, and a.
acceptance criteria for testing following plant changes, b.
Development of test documents, performance of tests, and documentation, evaluation, and approval of test results.
3.
The Plant shall be responsible for:
Provision of qualified l personnei and' calibratpd-equipment a.
for testing.
4.
' The Plant Operations Review Committee shall review all propcsed tests and experiments that affect nuclear safety.
5.
The Nuclear Safety Audit' and Review Committee shall be responsible for r.tviewing proposed tests or experiments not
~
described in the uafety analysis report which involve.a. change-in.the technical specifications or an unreviewed safety question as defined in.section 50. 59, 10CFR.
'C.
IMPLE)ENTATION-1.
'Satisf action 'of.this criterion shall be assured through the
. implementation _of.the actions ~ listed below:
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-Title:
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Dates. September 10, 1980 t'b' r
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.a.
Assurance that. changes, repairs, and replacements are.
tested in accordance with the original design and testing I
requirements or.' acceptable alternatives.
b.
Review of written test documents for incorporation or reference of;the following:
- 1. -
Requirements and acceptance lipits contained in.
. applicable design and procurement documents.
2.-
Instructions for performing the test.
' I 3.
- Test prerequisites, such'as:
Calib[ated'nsturmentation a.
4 t o b.
Adequate and appropriate equipment Trained, qualified, and licensed / certified c.
personnel d.
Completeness of item to be tested 4
Suitable and controlled environmental conditions e.
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Provisions for data collection and storage s
4.
Mandatory inspection hold points for witness by owner, contractor or inspector, when applicable.
5.
Acceptance and rejection criteria.
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Method of documenting test data and results.
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Title:
Section XII'. Contro1 ~ of Measuring &
Test Equipment 4l:
Pages' 1 of 2 Rev. No.: 0 s
Dat es, September 10,'1980' XII. CONTEDL' 0F MEASURING 'AND' TEST EQUIPENT p
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' This 'section of ' the.0perational Quality Assurance Prograu established the mes'sures' for the control, calibration and periodic adjustments.of
' tools, gages, -instruments, and other measuring and test devices used -
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to. verify, conformance to established requirements.
B. ~ RESPONSIBILITIES 1..
' The Operational Quality. Assurance Department shall be
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responsible. for:,
i a'.
Surveillance and/or audit of the established progran for
.j the control of measuring and. test equipment.
e(
- Review of the -implementing documents for control of b.
- measuring and test equipment.
2.
The Plant shall' be responsible fort.
a.-
Development of the implementing documents for control of measuring and test equipment including identification and calibration.
b..
Provision'of calibrated. tools, gages and instruments necesr,ary to perform required measurements and tests.
2
- c. ' Maintenance'of calibration-records.
p d.-
LPreparation a'nd review of specifications for measuring and test equipment, such that1 all applicable requirements are satis fied.
- C. ' IME 12ElfrATION '.
1.
- Satisf action of:this criterion shall-be assured through the
' implementation of the actions listed below:
s
.a.,
Identification: and traceability of measuring and ' test
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- equipment to' the-calibration ~ test data, y
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' b.
Labelling or tagging'~of. measuring and test equipment to
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T indicate due date for calibration.-
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Title:
..Section XII.: Control ~ of ' Measuring &
.Te st Equipment Pages' 2 of 2
- Rev. No. : 0 L
Date September 10, 1980 L
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- Calibration = of! measuring and test equipment at specified intervals based on required accuracy,' purpose, degree of l
. usage, ' stability characteristics, and other conditions af fecting the measurement.'
d.
Documentation of measures taken to determine the validity; of previous inspections-performed when measuring and test,.
equipment is found to be out of calibration.
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Use-of calibration standards having ~an uncertainty (error)L'
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equal to or better-than the equipment being calibrated.,
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'g Calibration : ctandards ' limited by the " state-of-the-ar t" may '
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have a greater acceptable uncertainty.
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- f.
Documentation and maintenance of the status of aL1 items 3
under: the calibration system..
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Traceability of reference' and transf er standards to nationally recognized standards; or, decumentation of the basis for calibration where natioEl standards are none xis te nt.-
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Title:
- Section 'XIII.
- Handling, storage & Shipping -
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'Page:
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September 10, 1980~
4 L XIII. HANDLING, STORAGE AND SHIPPING i
- i. ;
T A SCOPE; 1
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This_'section~ ofltheLOperational Quality Assurance Program establishes -
V
. measures to, control-the~ handling,' storage,. shipping, cleaning and -
preservation of. material-'and. equipment - to prevent damage or:
~! det erioration'..
B.'; RESPONSIBILITIES w
'1.'
The Operational Quality' Assurance Department shall be y;,., f responsible for:
2 y'
'a.- ' Providing' surveillance, audit ;and/or inspection of the handling, storage ands shipping ~ of materials, ~ parts, and components.'
b '.
- Providing review of handling,. storage, and shipping
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' documents.
Providing review of Engineering and Plant specifications to' c.
assure thav proper handling,' storage, and shipping -
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requirements have 'been1specified.-
k 2.
The. Plant shall. be responsible.for:
-Development of the.. implementing documents for handling, a.
storagel~and: shipping of materials and eq6ipmept.
b.
Provisions' of suitable facilities and equipment for f
- handling,1 storage, ' nd shipping of materials.
a i.
Inspection and test of special' handling tools.and equipment..
- c..
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- 'IMPTEMENTATION~
'C.
T atisf action. of :this criterion shall b' e assured: through the
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,. implementation.of thefactions;1isted below: -
a'. ? Specification:- and ' accomplishment-of: special handling,.
preservation, storage,i cleaningi packa'ging,i and shipping requirements /by qualified individuals'in.accordance with.
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- predetermined; work and inpsection instructions. -
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Preparationof instructions?in accordance with. design and y
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- 4 jpecification' requirements which contro1Lthe cleaning,-
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-handling; storage,; packaging,' shipping [and ' preservation of :
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_ "safetyf classified materials,; cos.ponents and systems-to
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- conditions'such as temperature;or.' humidity.
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Title:
Section XIV. Inpsection,; Test &-
{
Operating Status
~Page:7 1 of 1 j '
Rev. No.: :0
- Date: > September-10, 1980
' ~'
f XIV.IINSPECTION, TEST AND OPERATING STATUS'-
~
- A.= S00PE l
This 'section of the Operational Quality Assuance Program establishes the measures for indicating the~ status of items undergoing ins pections and-tests.'(via tags, labels,' etc.), to prevent the unintentional bypass of required tests.
In' addition, thisEsection establishes measures ' for ' indicating the operating status of components and -systems to prevent their inadvertent. operation.
- ( -
'B.
RESPONSIBILITIES
'1.'
'The' Operational Quality Assurance Department shall be responsible for the surveillance 'of inspection,-test and
~
operational status of components and systems and their. repair.
2.
The Plant shall be responsible for:
Ensuring indication of the status of operating equipment or a.
systems to be removed from service for maintenance, test, inspection, repair, or change.
b.
' Designation of personnel who are responsible for directing the status change of equipment and systems.
C.
IMPLE MENTATION 1.
Satisf action of this criterion shall be assured through the Laplementation of the actions listed below:
a.
Notification of -affected organizations -for changes in the inspection, test and operating status of structures, syst ems, and. component s.
b.
Procedural control to prevent the inadvertent bypcasing of required inspections, tests and other critical operations.
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Title:
Section XV. Nonconforming Matl's, Parts & Components Page: 1 of 2 Rev. No.: 0 ~' Date: September 10, 1980 XV. NONCONFORMING MATERIALS, PARTS, AND COMPONENTS A. SCOPE i This section of the Operational Quality Assurance Program establishes the measures to control materials, parts, or components which do not conform to requirements, in order to prevent their inadvertent use. B. RESPONSIBILITIES 1. The Vice President - Manager of Operations shall be responsible for: a. Review a'nd approval of all nonconformance reports. 2. The Operational Quality Assurance Department shall be responsible for: a. Surveillance of the control, evaluation, and disposition of nonconforming material, parts and components. b. Review of nonconformance reports, c. Surveillance for repetitive nonconforming materials. d. Establishment of feedback system between Maine Yankee and vendor representatives in regard to nonconforming material. 3. The Plant Engineering Department shall be responsible for: a. Review of nonconforming items which cannot be corrected by vendor action. b. Preparation or approval of implementing documents for repair and/or rework of nonconforming items, c. Preparation of documents to be 'followed in the review and resolution of nonconforming items, services, or activities. 4. The Plant shall be responsibic for a. Writing unplementation documents for the identification, documentation, and corrective action for all material, installation, testing, operation, and/or surveillance noncon formances. I i b. Establishment of measures to provide for the documented control of nonconforming materials, parts, and components.
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Title:
- Section XV. -Nonconforming Mat 1's, Parts - & Components l Page:. 2 of 2 Rev.~No;:-:0 Date:. September 10, 1980 O g- ' C.; I)fLE)ENTATION }: j D1. . Satisf action of-this criterion shall be assured; through the implementati' n.of the actions listed' below: o Identification, disposition; inspection.and segregation of' a.- . nonconforming items. p b. Identification of those individuals. or groups delegated the
- responsibility.and authority for the disposition and-written : approval o f. nonconforming - items.
3- . Inspection' and test 'of reworked or repaired items which c. require reinspection and retest' to ' original methods 'or . methods equivalent thereto. d. Inclusion of nonconformance reports dispositioned " accept as is" or " repair" as part of the ' inspection records furnished to the plant. ' Periodic analysis of nonconformane reports to show quality e. . trends with-the results reported to management for review arid assessment. 2. The identification, description, disposition, inspection and signature approval.of the disposition Lfor nonconformance shall' ~ be documented ~ in a nonconformance report. gu-F 4 ? 1 7 9 4 7 \\ -w g 0= :. L -.~ r 1,
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Title:
Section XVI. Cerrective Action Page: 1 of 2 Rev. No.: 0 Date: September 10, 1980 l XVI. CORRECTIVE ACTION j 'i. l A. SCOPE This section of the Operational Quality Assurance Program establishes measures to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. B. RESPONSIBILITIES 1. The Operational Quality Assurance Departme..c shall be responsible for: a. Surveillance and/or audit of plant activities involving the identification, review and correction of conditions adverse to quality, b. Surveillance and/or review of documentation of corrective action. 2. Maine Yankee shall be responsible for: a. Identification of caures of conditions adverse to quality. b. Preparation of recommendations to prevent reoccurrence of a de ficiency. c. Implementation of the corrective action. d. Documentation of corrective action taken. 3. The Plant Engineering Department shall be responsible for: a. Review of conditions adverse to q'2ality which involve design deficiencies to determine the cause of the condition. b. Recommendations or corrective action to preclude repetition of design deficiencies. 4. The Plant Operations Review Committee shall be responsible for: a. Review of conditions adverse to quality and recocmerding corrective action. f b. Recommendations involving repetition of operating t de ficiencies. 4 ~ a-
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Title:
Section XVI. Corrective Action i Page: 2 of 2 -
- l Rev. No.: 0 Date:
September 10, 1980 s C. IMPI.EMENTATION 1. Satisfaction of this criterion shall be assured through the implementation of the actions listed below: a. Initiation of corrective action following the determination of a condition adverse to quality to preclude recurrence, b. Follow-up revi tws to verify proper implementation of correcti e s e tions and to close out the corrective action f documentacion. c. Reporting of significant conditions adverse to quality, the 'j cause of the conditions, and the correction action implemented to the cognizant levels of management for review and assessment. -i M e ? li
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. Tit 1 : Section XVII. Quality Assurance Records' e 'Page: 1 of 2 Rev. No.: 'O Date:--September,10, 1980 l.. v . XVII. QUALITY ASSURANCE RECORDS ,A'.- SCOPE l 1. ~ This'section of the Operational Quality Assurance Progam establishes the measures' for maintenance of ' records which' f provide ~ documentary evidence of-the quality of' items and;the . activities -aff ecting quality. Requirements shall be established' for~ identification, transmittal, retrievability and retention of quality assurance records including' duration, location, protection and assigned responsibility. 1-2.. The quality assurance records shall include plant history; . o perating. logs; principa1' maintenance; design change activities; reportable occurrences; nonconformance reports; results of reviews, inspection, tests, audits and material analyses; monitoring of work performance; qualification of personnel, documents a'nd equipnent; drawings;' specifications; procurement documents; calibration documents and reports; and corrective action reports. B.' RESPONS IBILITIES 1. The Operational Quality Assurance Department shall be ' responsible for: a. Surveillance and/or audit of quality assurance record review, c.ontrol.and retention. .h. ' Maintenance of audit, vendor evaluation, surv'eillance and inspection records.of quality assurance activities generated by the Operational Quality Assurance Department personnel or their designates. 2. Maine Yankee shall be responsible for: q Writing. implementation documents for the establishment and a.- maintenance of Operational Quality Assurance records. b. Designating individuals and' establishing requirements for l the control of plant design, procurement, and operational .) records involving quality assurance. .i
- r c.
MaintenanceL of' qualification / certification records for ~ Maine Yankee personnel. d.= Provision of facilities to prevent deterioration or loss of ll{ documentation.- 6 i L *...
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Title:
Section XVII. Quality Assurance Records Page: 2 of 2 e j Rev. No.: 0 ^ j Date: September 10, 1980 l Provision of a system for the review, approval and l e. j retention of plant prepared documents such as reportable 1 occurrences, technical reports, required records and the l meeting minutes of of ficial committees. l
- i f.
Control and distribution of the Operational Quality Assurance Program and revisions thereto. C. IMPLEMENTATION 4 1. Satisfaction of this criterion shall be assured through the implementation of the actions listed below: a. Specifying the details required for inspection and test records including the following as applicable: 1) Description of the type of observation. 2) Evidence of completion and verification of manuf acturing, inspection, or test operations. 3) The date and results of the inspection or test. 4) Information related to conditions adverse to quality. 5) Inspector or data recorder identification. 6) Evidence as to the acceptability of the results. b. Providing for record administration, receipt, storage, E preservation, safekeeping, retrieval and final disposition. i c. Construction, location and security of record storage facilities to prevent destruction of the records by fire, flooding, thef t, and deterioration by environmental conditions such as temperature or humidity. Duplicate records shall be stored in a separate remote location when the type of document is not included in the record storage facility. J Y. -.
-Title: Section XVIII. Audits N =-adt 'Page: 1 of 3 i 4 Rev. No.: O ~ Date: September 10, 1980 q a XVIII. AUDITS f A. SCOPE This section of the Operational Quality Assurance Program establishes the measures for a comprehensive system of planned and documented audits to verify compliance with all aspeces of the Program and to assess the effectiveness of the Program. ,i B. RESPONSIBILITIES 1. The Operational Quality Assurance Department shall be responsible for: Providing approved audit check lists for surveillance of 14 a. activities encompassed by the 18 criteria of 10CFR50 Appendix B and ANSI N18.7. b. Providing for training of audit personnel. Scheduling and coordinating of the formal Internal Audit c. Program. d. Review and approval of the implementing documents for Internal Audits. Preparing information regarding the Internal Audit Program e. for review by the Nuclear Safety Audit and Review Committee. f. Performing random informal surveillance of plant activities. g. Provide for evaluations of vendors. h. Identifying program discrepancies and deficiencies. i. To verify correction of discrepancies discovered during audits. j. Making recommendations to preclude possible audit discrepancy repetition. 2. The Manager - Nuclear Support shall be responsible for evaluation of and recommend corrective action for Internal Audit discrepancies. 3 The Plant shall be responsible for: A f .2:
- c. s.sy,
Title:
Section XVIII. Audits Nb=-wS Page: 2 of 3 Rev. No.: 0 fj Date: September 10, 1980 s Documentation of the discrepancy response concerning any lj a. ~ outstanding item resulting f rom an audit at the plant. b. Implementation of corrective setion to be taken as agreed upon by ti.a Manager - Nuclear Pupport. The Nu' lear. Safety Audit and Review Committee shall be 4. e responsible for: a. Review of the Operctional Quality Assurance Program to determine its overall effectiveness. b. Reporting results of Program reviews and recommendations resulting theref rom to Maine Yankee Vice President / Manager of Operations and YNSD Vice President. i C. IMPLEMENTATION 1. Satisfaction of this criterion shall be assured through the haplementation of Maine Yankee documents. 2. The implementing documents shall provide for the following: { a. Documentation of audit results and review with management having responsibility in the area audited. b. Necessary action to be taken by responsible management to correct deficiencies revealed by the audit, c. Reaudit of deficient areas until corrections
- have been accomplished to preclude recurrence of the deficiencies.
d. Inclusion of an objective evaluation of quality-related 3 practices, procedures, instructions and the effectiveness of implementation in the audit. e. Inclusion of an objective evaluation of work areas, activities, processes and items and the review of documentaton in the audit. f. Performance of audits in the below listed areas where the j requirements of Appendix B to 10CFR Part 50 and ANSI N18.7 are being implemented.
- i 1)
Operation, maintenance and repairs. h 2) The preparation, review, app. oval, and control of [ designs, specifications, procurement documents, j instruction, procedures, and drawings.
Title:
Section XVIII. Audits d =mwS Page: 3 of 3 Rev. No.: 0 Date: September 10, 1980 l ,1 3) Receiving and plant inspections. 4) Indoctrination and training programs. 5) Implementation of operating and test procedures. 6) Calibration of measuring and test equipment. 7) Security E) Emergency Plan 9) Health Physics 10) Corrective Action g. Scheduling of audits regularly on the basis of the status and safety importance of the activities being performed. N t 3 N i bm' o
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Title:
Appendix A. Qualification Requirements Page: 1 of 1 Rev. No.: 0 1 Date: September 10, 1980 s I QUALIFICATION REQUIREMENTG FOR THE DIRECTOR, OPERATICriAL QUALITY ASSURANCE DEPARTMENT 4 s The Director,' Operational Quality Assurance Department must meet the below listed qualification requirements: 1. Have a. Bachelor's degree in Science or Engineering, or the equivalent in practical experience. 2. Must have developed a high level of competence in the field of quality assurance or related technical areas associated with nuclear stations. 3. Must be innovative and have the ability to plan an effective overall quality assurance program for the Company. 4. Must have the ability to effectively coordinate the implementation, monitoring and modification of the quality assurance program. 5. Must exhibit qualities of leadership and communications ability, both oral and written. N i i O!.
G
Title:
Appendix B. (Exceptions) Page: 1 of 10 1 Rev. No.: 0 Date: September 10, 1980 APPENDIX B d (Exceptions) The sub-categories of this Appendix summarize the exceptions noted in p' Section II of the Maine Yankee Operational Quality Assurance Program. 4
- 4 Appendix B Sub-Category Standard / Guide Title i
B-1 ANSI N18.7-1976 Administrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants B-2 ANSI N45.2.3-1973 Housekeeping During the Construction Phase of Nuclear Power Plants B-3 ANSI N45.2.10-1973 Quality Assurance Terms and Definitions B-4 ANSI N45.2.12 Requirements for Auditing of (Draft 4 Quality Assurance Programs for Revision 2-1976) Nuclear Power Pl'nts a B-5 ANSI N45.2.2-1972 Packaging, Shipping, Receiving, Storage and Handling of Items for Nuclear Power Plants .i e i Ii il p, '
Title:
Appendix B. (Exce ptions) Sub Cat. B-1 Page: 2of10 1 Rev. No.: 0 Date: September 10, 1980 l ANSI N18.7 - 1976, Administrative Controls and Quality Assurance for the Phase of Nuclear Power P,lants EXCEPTION: The following exception is taken by Maine Yankee. ANSI standards not ref erenced in ANSI N18.7-1976, but which are referenced in an ANSI standard endorsed by N18.7-1976 shall not be considered as applicable 8 to the Maine Yankee Operational Quality Assurance Program. ALTERNATIVE : Maine Yankee may use the noted standards as guides, as necessary. M en l i l i I I l m
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1 Appendix'B.'(ExceptionsiSub' Cat. B ' ~ - Page: i3 of '10 S ' ~ 'Rev. No.':' -0 .Date:.-September 10v-1980; ~ [ANSIN45.2.3-1973, Housekeeping During -th'e Construcion Phase of Nuclear Power ' ~
- Plants
.A.- - EXCEPTION: - Subsection ~ 2.1 - Planning'. ~ i Maine Yankee ' takes; exception to the^ five-zone requirements specified in the: subject. standard. i- ' ALTERNATIVE : ' Maine Yankee shall establish as a minimum a three-zone program as follows:- Zone III ~ Zone III criteria shall be applied to major portions of the -reactor coolant system lwhich are opened for inspection, maintenance or repair. 1. 'Acc *ss control over personnel shall be required. 2. Cleanliness'shall.be maintained, comensurat'e with.the work being . performed, so as to preclude the entry of foreign mat'erial to the Reactor Coolant System. -3. A documented cleanliness inspection shall be performed immediately ~ prior to; closure. NOTE: The Zone III requirements may.be expanded for-cert *ain maintenance / repair activities if ' deemed appropriate by plant 1 mana gement. In such instances applicable sections' of Zones I & II shall be specified. Zone'IV Zone _ IV criteria shall be applied to the radiation control areas of the pla nt.' 1 . l.. : Standard ' janitorial' and work practices shall be utilized to maintain .a' level o' f cleanliness comensurate with company policy in the areas .- of Housekeeping,'. Plant and l Personnel Safety and Fire Protection. i ~ 72.'. Additional-housekeeping. requirements shall be implemented as required ~ -.'t. 'for'the control of radioactive contamination. 4 ~ 3. LSmoking.and eating shall-be : controlled consistent with good health-physics practices and.to' maintain cleanliness. lf x t + r 4 b 3 d. l ' 3: t 5'
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Appendix B. (Exceptions) Sub Cat. B-2 N =-we Page: 4 of 10 Rev. No.: 0 -Date: September 10, 1980 1 ANSI N45.2.3-1973 (Cont.) Zone V i' Zone V criteria shall be applied to the remainder of the plant. 1. Standard janitorial and work practices shall be utilized to maintain a level of cleanliness commensurate with company policy in the areas of Housekeeping, Plant and Personnel Safety and Eire Protection. i B. EXCEPTION: Subsection 3.2 - Control of Facilities Maine Yankee takes exception to the control of tools, equipment, materials and supplies used in Zone III. ALTERNATIVE: Maine Yankee shall verify control for Zone III as indicated in Exception
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Appendix B. (Exceptions) Sub Cat. B-3 Page: 5 o f 10 Rev. No.: 0 Date: September 10, 1980 .s ANSI N45.2.10-1973, Quality Assurance Terms and Definitions EXCEPTION: Subsection 2 - Terms and Definitions Maine Yankee takes exception to the definitions of " Certificate of Conformance" and " Certificate of Compliance". ALTERNATIVE: Maine Yankee shall reverse the definitions of the above terms so our Program will be in compliance with the implied definitions in the ASFE B&PV Code and Maine Yankee specifications. E -e s f ii -- ~ _. _ _.
As Titlet Appendix B. (Exceptions) Sub Cat. B-4 Page: 6 of 10 Rev. No.: 0 Date: September 10. 1980 i ANSI M45.2.12 Draft 4, Rev. 2-1976, Requirements for Auditing of Quality Assurance Programs for Nuclear Power -i Planti 4 EXCEPTION: Subsection 4.2.2 Team Selection Maine Yankee takes exception to the requirement for a " Lead Auditor". ALTERNATIVE : Team Selection - In selecting personnel for auditing assignments,
- ensideration shall be given to special abilities, specialized technical training, prior pertinent experience, personal characteristics, and educati on. One or more auditors comprise an audit team.
Auditor responsibilities include establishing the pace of the audit, assuring communications with the organization being audited, participation in the audit performance, and preparation and issuance of reports. N J I
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Appendix B. (Exceptions) Sub Cat. B-5 Page: 7 of 10 Rev. No.: 0 l Date: September 10, 1980 t ANSI N45.2.1 1972, Packaging, Shipping, Receiving, Storage & Handling of Items for Nuclear Power Plants A. EXCEPTION: Subsection 3. 7.1 & A3. 7.1 - Containers Maine Yankee takes exception to the specific requirements for containers. ALTERNATIVE: Containers shall be of suitable construction to assure material is received undamaged. JUSTIFICATION: Containers shipped by closed carrier, stored inside and not subjected to a wet envirt sent do not require weather resistant fiberboard, therefore, this is an unnecessary expense. Additionally, numerous vendors utilize shipping containers that do not comply with the specific requirenents of this section, i.e., flaps overlap. The acc'eptance criteria for a shipping container should be established based on the capability of the container to maintain the component / material in a safe condition. Technology has advaced beyond the standard. B. EXCEPTION: Subsecolon 3.7.2 - Crates and Skids Maine Yankee takea exception to the requirement that skids and runners shall be used on boxes with a gross weight of 100 pounds or more. ALTERNATIVE: Skids or runners shall be used on with a gross weight of 100 pounds sva-or more if practical. JUSTIFICATION: Storage methods and container design frequently are such that l skids are not feasible. runners or n [ L... ~
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Appendix B. (Exceptions) Sub Cat. B-5 j/ Page: 8of10 Rev. No.: 0 Date: September 10, 1980 s 'l ANSI N45.2.2 (Cont. ) C. EXCEPTION: Subsection 5.2.1 - Shipping Damage Inspection Maine Yankee takes exception to the requirement that a preliminary visual inspection or examination be performed prior to unloading. ALTERNATIVE: Maine Yanke'e shall perform those required inspections af ter unloading. In special instances, pre-unloading inspections shall be performed. JUSTIFICATION: Post unloading inspection is adequate to determine any damage that may have been incurred during shipping and handling. D. EXCEPTION: Subsection ' 5.2.2 - Item Inspection 4 Maine Yankee takes exception to the requirement, that "The inspections shall be performed in an area equivalent to the level of storage requirements for the item". ALTERNATIVE: Maine Yankee shall perform receiving inspection in a manner and in an environment which does not endanger the requisite quality of the item; however, receiving area environmental controls may be less stringent than storage environmental controls for that item. When inspections are performed in receiving areas with environmental controls less stringent than storage area environmental controls, a time limit shall be established on a basis for retention of items in the receiving area. Retention time shall be such that deterioration is prevented and applicable manufacturer recommendations are addressed. J,USTIFICATION: Receipt inspection activities are for a much shorter duration and therefore should.not be subjected to the same stringent requirements as required for storage. t m
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Appendix B. (Exceptions) Sub Cat. B-5 .-l Page: 9 of 10 Rev. No.: 0 Date: September 10, 1980 ANSI N45.2.2 (Cont.) E. EXCEPTION: Subsection 5.2.3 - Special Inspection Maine Yankee takes exception to attaching special inspection procedures to the item or container. ALTERNATIVE: Special inspection procedures shall be readily available to personnel performing inspections. JUSTIFICATION: Procedures are subject to less abuse and more stringent controls when maintained on file and not attached to the item. Inspection status is maintained by tagging and procedure control. F. EXCEPTION: Appendix A-3 Subsection A3.5.1(1) - Caps & Plugs Maine Yankee takes exception to the requirement that non-metallic plugs and caps shall be brightly colored. ALTERNATIVE : Non-metallic plugs and caps shall be of a contrasting color. JUSTIFICATION: The purpose of utilizing brightly colored plugs and caps is to assist in assuring obstructions are not inadvertently placed in operating components or systems. By using plugs and caps of a contrasting color this objective can be achieved. G. EXCEPTION: Appendix A-3 Subsection A3.9(1) - Second Group, Markings Maine Yankee takes exception to the requirement that container markings shall appear on a minimum of two sides. ) ALTERNATIVE : I Containers shall be adequately marked to provide identification and retrievability. Lu
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Appendix B. (Exceptions) Sub Cat. B-5 Page: 10 of 10 Rev. No.: 0 Date: September 10, 1980 a ? ANSI N45.2.2 (Cont.) JUSTIFICATION: Containers are tagged to provide identification and inspection status. Employment of two tags on small containers adds bulk and confusion and does not provide for better identification or traceability. H. EXCEPTION: Appendix A-3, Subsection A.3.9(4) - Second Group, Marking Maine Yankee takes exception to the requirement that container markings shall be no less than 3/4" high container permitting. ALTERNATIVE: Container markings shall be of a size which permits easy recognition. JUSTIFICATION: Markings were intended to provide identification and instructions. The criteria should be that the markings clearly provide the same. I. EXCEPTION: Appendix A-3 Subsection A.3.9(6) - Second Group, Marking Maine Yankee takes exception to the information required for cont'ainer marking. ALTERNATIVE: Marking shall be adequate in each case to provide identification, traceability and instructions for special handling, as applicable. JUSTIFICATION: The information required is excessive. Cluttering a container with excessive markings only reduces the main objectives, maintaining identification and establishing special controls. e m.-
. Append x C. Ma ne Yankee Clas si fications i i ,/
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Paget 1 of 7 Rev. No.: 0 .c Date: September 10, 1980 s MAINE YANKEE CLASSIFICATION OF STRUCIURES, COMPONENTS AND SYSTEMS t. SAFETY - CLASS I. STRUCTURES Vapor Container 2 II. ELECTRICAL SYSTEMS AND COMPONENTS 'l Electrical and Instrumentation systems and components designed in accordance with IEEE Standard 279, " Criteria for Protection Systems for Nuclear Power Generating Stations" and IEEE Standard 308, " Criteria for Class IE Electric Systems for Nuclear Power Generating Stations" have been classified as safety class, and are listed below: A. 4160 Volt Switch gear (Engineered Safety Features Buses) B. 4160 - 480 Volt Transformers (Associated with Engineered Safety Features) C. 4000 and 460 Volt Motore (Associate with Engineered Safety Features) D. 480 Volt Switch gear (Engineered Safety Features Buses) E. 480 Volt Motor Control Centers (Associated with Engineered Safety Features) F. 125 Volt DC Batteries (Associated with Engineered Safety Features) G. Battery Chargers (Associated with Engineered Safety Features) H. Inverters, 125 Volt DC to 120 Volt AC (Vital Instrument Buses) I. Vital Instrument Bus Panels J. Regulated Instrument Buses Panels -(240/120 Volts AC Single Phase) K. 125 Volt DC Power Panels (Associated with Engineered Safety Features) L. Transformers, dry type, 280-120/240 Volt (Associated with Regulated Instrument Buses) M. Cable Trays (Associated with Engineered Safety Features) N. Containment Penetration Assemblies 0. Power Cables (Associated with Engineered Safety Features System) P. Instrumentation and Control Cables (Associated with Engineered Safety Feature System)- Q. AC Control Room Lighting R. Diesel Generators S. Diesel Generator Control Panels T. Heat Tracing for Boric Acid Injection U. Reactor Protective Systems V. Engineered Safety Features Actuation Systems i O
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' Appendix C. Maine Yankee Classifications ~
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? ' - Rev.:No.:. 0 3 'Date: ' September 10, 1980 ~ t .SECTION II NOTES: L1 t. f . l'.. For thos'e -eluctrical and instrumentation' systems ' designated above, Quality Assurance electricalland instrumentation prcgram requirements are_ applicable only to those portions of 'systemsudefined in Section IV a's necessary ' to = perform the system ' safety function. 2. , Instrumentation components included.within: each instrumentation system include power supply,. sensors, relays, wiring and final operating device i(solenoid, relay,- etc.) as necessary to perform the-system safety function.. 3. Electrical' components' included within each elect-ical system include power ! sour,ce,. breaker, control circuit, cable, ' relaying and operating device (motor, solenoid, heater, relay, etc ) as necessary to. perform ~ the system safety function. ~ 4. Certain components are excluded from the QA program requirement
- if they meet the criteria described in Section III.
III. ELECTRICAL AND INSTRUMENTATION SYSTEM COMPONENT EXCLUSION CRITERIA 1. Any component of an electrical or. instrumentation system (Section II) is excluded from the QA Program requirements if it meets the following criteria: A failure.of the: component by the electrical. shorting, o' pen a. circuiting, grounding or mechanical failure would not render the a system incapable of performing its intended safety function b. . A ~ failure of the fluid pressure boundary of the component would notl ren' der the system incapable of ' performing its intended safety function. ' It is not. used to operate or control a device required by c. . Technical Specifications. - 2. - Small spare parts having no -traceability, such as commercial off-the. . shelf items, may be purchased as non-safety-related and then ~ qualified.for'use in equipment requiring Quality Assurance. Examples (' aof such items are resistors,. capacitors, switches, indicators, coils, ( wire, cont.ectors, solid state devices and miscellaneous hardware. h <i1 l .-m
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Appendix C. Maine Yankee Classifications Page: 3 of 7 Rev. No.: 0 Date: September 10, 1980 l} _s t IV. WCHANICAL SYSTEMS AND COMPONENTS ~ Mechanical systems and components have been nuclear safety classified in accordance with ANSI Standard N18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants". Instruments, controls, motors, sensors, etc. associated with the nuclear safety classified components which assist _ the ccmponents in performing a safety function are in the same safety class as the gompenent to which they are associated excep.t as noted in Section II above. ) Corresponding component supports that provide a safety function are in the same safety class as the components for which they provide support. Component safety class designations are listed in the attached Table C.1 V. OTHER ITEMS REQUIRING QUALITY ASSURANCE 1. Fuel Assemblies 2. Boric Acid 3. Diesel Fuel Oil 4. Weld Rod 5. Chemicals a. Hydrogen b. Nitrogen c. Morpholine d. Hydra zine s e. Resins 6. Reagents Those reagents used in performance of analyses required by a. Technical Speci fications.
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Appendix C. Maine Yankee Classifications 1 %==*8 Page: 4 of 7 Rev. No.: 0 Date: September 10, 1980 l.
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{CHANICAL SYSTEMS AND COMPONENTS CLASSIFICATION LIST - SAFETY CLASS COMPONENT Reactor Coolant System Reactor Vessel 1 Full Length Control Rad Drive Mechanism Housing 1 Part Length Control Rod Drive Mechanism Housing 1 Steam Cenerator (tube side) 1 (shell side) 2 Pre ssurizer 1 Reactor Coolant Piping, Fittings, and Fabrication 1 Surge Pipe, Fittings and Fabrication 1 Safety Valves 1 Relief Valves 1 Valves to Reactor Coolant System Boundary 1 Reactor Coolant Punp Casting 1 Main Flange 1 Feedwater System 1 Auxiliary Feedwater Pumps 3 Demineralized Water Storage Tank 3 Feedwater Piping _(inside containment and outside containment to feed REG Isolation Valve) 2 Service Water System Service Water Pumps 3 i Valves and Piping 3 Containment Spray System \\ M i f.- s_u m
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Appendix C. Maine Yankee Classifications Page:. 5 of 7 Rev. No.: 0 Dates September 10, 1980 s .i TABLE C.a (Sheet 2 of 4) SAFETY CLASS COMPONENT ~ Spray Chemical Addition Tank 2 Containment Spray Pumps 2 Chemical and Volume Control ystem Regenerative Heat Exchanger 2 Letdown Heat Exchanger (tube side). 2 (shell side) 2 Reactor Coolant Puri.fication Demineralizers 2 Reactor Coolant Filter 2 Charging Pumps Centrifugal 2 Auxiliary Charging Pmmp 2 Seal Water Supply Fi'.'.ters 2 Seal Water Return Fil ter 2 Seal Water Heat Exchanger (tube side) 3 (shell side) 3 Boric Acid Storage Tank 3 Boric Acid Transfer Pumps 3 Boric Acid Filter 3 Boric Acid Mix Tank 3 Volume Control Tank 2 Letdown Flow Centrol Valves 2 Safety Injection System Refueling Water Storage Tank 2 Safety Injection Tanks 2 Low Pressure Safety Injection Pumps 2 Residual Heat Removal System Residual Heat Exchangers (tube side) 2 (shell side) 3 Radioactive Caseous Waste System 4 - i .i
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Rev. No.:.O M 'Q. L ;j i ,(I Date: September 10, 1980 6 ( r ,t r^ I . TABLE ' C.1 ::... ,c .(Sheet 3 of.4)'
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l SURETY. - CLASS ~ l< - COMPONENT Waste Gas Compressor 3 i~ k
- Waste. Gas Surge Tank 3
Gas Decay Drums. 3 e C f[ , Component doolina Water'Systes = d -' 3 .v } , Component Cooling Water Pump. 3. Component Cooling Water, Surge Tank Component Cooling Water Heat Exchangers 3 ' Main Steam System- ~ v Main 'Steani Piping '(from Steam Generator - ,'l.h~ up' Lto and. including non-retdrn, valves) - 2 e 2
- Safety valves
, ~ Atmospheric Dump Val.ve - .2 Steam Generator Blowdown System- ! Piping ~.(up to-and including isolation valve) 2 l '/ Emergency Diesel Generator ' System ' Diesel.' Fuel; Day Tank 3 Diesel'Ge'nerator Air Tanks 3 3 -- Diesel Engines - - L 'Startina Air System Air, Tanks. J ~ \\ ~ - 3\\ t 3 Piping and, Fit, tings 3~ ] 1' Valves 3 3-S Filters! .i: m19 1 5: .s .n I. -g e -g -) >0 .,3 ,t.1y n. 3 + Th i u, 3: r ) f t-i-. 3 3' --kN-hb s n G, .-_ g--ll Q.,w/ ~ o t-.
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Appendix' C. Maine Yankee Classifiestions- ..j; '.Rev.-No.: 0' ].' sDate: September 10, 1980 a 'l TABIE C.1 }' (Sheet 4 of 4)- .~! ~ SAFETY CLASS COMPONENT 4 f.' Spent Fuel Pool Cooling and' Cleanup Syst em 3 ' l-Spent Fuel Pool Pump 3 e Spent Fuel. Pool Heat Exchanger! Spent Fuel Pool Cooling Loop _ Valves 3 Spent fuel Pool Cooling Loop Piping: 3 2 *, Handling'EquNisnent for Fuel and Reactor Vessel Internals Fuel Transfer Tube Outer Sleeve 2-Expansion Joints-2 Fuel Transfer Tube and Flange ~ 2 p. Equipment and Floor Drainage' System ,3 < 2 I.-
- High Pressure Drain Cooler Primary Drain Tank -
3 Primary Drains.Degasifier 3 Primary Drain Pumps 3 i s'. 4. U )p n b llj:.p 1 1)
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