ML20235W365
| ML20235W365 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 06/28/1974 |
| From: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19255K400 | List: |
| References | |
| FOIA-86-42 NUDOCS 8710160172 | |
| Download: ML20235W365 (49) | |
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e GEORGIA POWER COMPANY i
DOCKET No. 50-424
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ALVIN W. V0 GILE HUCLEAR PLANT, UNIT 1 i
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_ CONSTRUCTION PET & FIT'
' Construction Permit No. CPPR-108
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The' Atomic Ener'gy Co=4ssion (the Corraission) having found that:
p A.
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The application for construction permit complies trith the require-ments of the Atomic Energy Act of 1954, as acended, and the rules 1
and regulations.of the Cottmission, there is reasonable assurance i
' that the activities authorized by the permit trill be conducted 1n compliance with the rules and regulations of the Commission, and
. all required notifications to other agencies or bodies have been
'Q duly nade;
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B.. The Ceorgic Power Company (the applicant) has described the proposed design of the Alvin W. Vogtle Nuclear Plant, Unit 1 (the facility),
including, but not limited to, the pr.incipal architectural and engineering criteria for the design anPhas identified the cajor features or components incorporated therein for the protection of the health and safety of the public; Such further technical or design inforr::ation as may be required' C.
to complete. the safety analysis, and which can reasonably be lef t
' for later consideration, will be supplied in the final safety.
, analysis report; 1.
D.
Safety features or components, if any, which require research and -
. development have been described by the applicant and the applicant has identified, and there vill be conducted, a research and development program reasonably designed to resolve any safety questions associated trith such features or components; E.
On the basis of the foregoing, there is reasonable assurance that (i) such saf ety, questions vill be satisfactorily resolved at or before the latest date stated in the application for completion of construction of the proposed facility and (ii) taking into con-sideration the site criteria contained in 10 CFR Part 100, the Q
proposed facility can be constructed and operated at the proposed location trithout undue risk to the health and safety of the public; f.
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FOWLER 06-42
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The applicant is, technically qualified"to des'ign and construct the s;
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proposed. facility;
- G.; The applicant.is financially qualified to design and' construct the proposed facility; 3.
The issuance of a pemit for the. construction of the facility will. '
not be. inimical to the comon defense and security or to the health 1
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and safety of the public; and l
s I.
After seighing the' envirencental, economic, technical and other benefits 'of the ' facility. against environmental costs and considering available alternatives, the issuance.of a construction permit,-
subject to the conditions for protection of the environment set forth herein, is in accordance with 10 CFR Part 50,~ Appendix D, of
- the Commissien's regulatioits and all applicable requirements of 1
said Appendix D have been satisfied.
y 2.
rsuant to Section 103 of the Atomic Energy Act of 1954, as ame.nded (the Act), and Title 10, Chapter I, Code of Federal-Regulations Part 50, " Licensing of Production and Utilization-Facilities", and pursuant
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to the zatia1 niau-s a the ite e saeer and ucensins 3-rd dated s
May 24, 1974, and June 27, 1974, the Atomic Energy Comnission (the Com nission) hereby issues a construction pernit to the applicant for a utilization facility designed to operate et 3411 negnaatts thernal as l
described in the application-and amendnentrthereto (the application)
I filed in this catter by the applicant and as r. ore fully' described in the cvidence received at the p:311c hearing upon that application'..The faci-lity, known as the Alvin H. Vogtle Nuclear Plant, Unit 1, will be' located 1
on the appli, cant's site in Burke County, Georgia.
3.
This permit shall be deeced t6 contain and be subject to the conditions specified in Sections 50.54 and 50.55, of said regulations; is. subject
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to all applicable provisions of the Act, and. rules, regulations, and orders of the Commission now or hereaf ter in effect; and is subject to the conditions specified or incorporated below:
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A '.' The' earliest date for the completion of the facility is October 1979, and the latest date for completion is April 1981.
B.
The facility shall be constructed and located at the site as described in tf.e application, in Burke County, Georgia.
l C.
This construction permit authorizes the app 11 cant to construct the facility described in the application and the hearing record, in accordance with the principal architectural end engineering cri-f -.
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teria and environmantel protection commitments set forth therein.
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Antitrust conditions as follows :
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- (1) As used herein:
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(a) " Entity" means any' financially responsible person, private or public corporation; municipality, county, cooperative, l
.i association, joint stock association' or business trust,
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' owning, operating or proposing to own or operate equipment
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or facilities within the Stcte of Georgia (other than Chath'as, Effingham, Fannin, Towns and Union Counties) for
- the generation, transmission or distribution of elec.tricity, pro'vided that, except for municipalities, counties, or rural electric cooperatives, " entity" is restricted to those uhich are or will be public utilities under the laws of the State of Georgia or under the laws of the United States, and are or will be providing retail electric service under a contrac't i
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or rate schedule on ' file with an6 subject to the regulation of the Public Service Co:=:21ssion of the State,of Georgia or any regulatory agenc'y of the Un'ited States, and, provided j
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electric cooperatives, " entity" is restricted to those further, that as to nunicipal1 ties, counties or rural which provide electricity to the public at retail within the State of Georgia (other tha_n Chatham, Effingham, Fannin, Towns and Union Counties) or to responsible and legally qualified organizations of such municipalities, counties l
a and/or cooperatives in the State of Georgia (other than l
Chatham, Effingham, Fannin, Towns and Union Counties) to
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the extent they may bind their members.
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-(b) " Applicant" means Georgia Power Company,.any successor, l
'1 assignee of this license, or assignee of all or substantially all of Georgia Power Company's assets, and any affiliate or subsidiary of Georgia Power Company to the extent it engages f
in the ownership of any bulk pouar supply generation or transmission resource in 'the State of Georgia (but specifically
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not including (1) flood rights and other land rights acquired
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.in the State of Georgia incidt.nca3 to hydroelectric l
generation facilities located in another state and (2) facil-ities located west of the t.hrsw.d of the stream on that part of the Chattahoochee River snrving as the boundary between the Sta,tes of Georgia and Alabama).
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(2) Applicant recognizes that it is often in the public interest for those engaging in bulk po.ser supply and purchases to
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interconnect, c.cordinate for reliability and economy, and
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engage in bulk power supply transactions in order to increase 9
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X interconnected system reliabil'ity cnd' reduce the costs of electric power.
Such arrangements must provide ~ for applicant's costs. (including a reasonable return) in conneetion therewith and. allow other participating' entities full access to the bene-i fits available from interconnect'ted bulk power supply operations f
and must provide net benefits to applicant.. In entering into such arrangements neither applicant nor 'any other participant..
should be required to' violate the principles of sound engineering practice'or forego a reasonably contemporaneous' alternative arrangement with another, developed in good faith in arms
. length ' negotiations.(but not including arrangements between applica'nt and its affiliates or ' subsidiaries which impair entitieis' rights hereunder more than they would be impaired " vere:
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such arrangements made in good faith between applicant and a non-affiliate or non-subsidiary) which affords it, greater bene-1' fits. Any such arrangement must provide for adequate notice i
and joint planning procedures consistent with sound engineering.
j practice,- and must relieve applicant from obligations undertaken by it in the event such procedures are not followed by any,,
participating entity.
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Applicant recognizes that each entity may acquire some or all of its bulk power supply from sources other than applicant.
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In the implementation of the obligations stated in the succeeding.,
paragraphs, applicant and entities shall act in accordance with the foregoing principles, and these principles are conditio~s to each of applicant's obligations herein undertaken.
1 (3) ' Applicant shall interconnect with any entity which provides, or vhich has undertaken firm contractual obligations to pro' vide, some or all of its bulk power supply from sources other' than
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- kpplicant on terms to be included in an interconnection' agree -
ment which shall provid for appropriate allocation of the costs of interconnection facilities; provided, however, that if an entity undertakes to negotiate such a firm coarractual obligation, the applicant shall, in good faith, negotiate with 1
such entity concerning any proposed interconnection. Such interconnection agreement shall prcvide, without undue pref-erence or discrimination, for the folicaing, acong other things, insofar as consistent with the operating necessities of applicant's' and any participating entity's systems:
j (a) maintenance and coordination of reserves, including, where appropriate, the purchase and sale thereof,
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>l (b) emergency support, G,
l(c) maintenance support,
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- (d)Iecoriomy energy exchanges, (e) purchase' and sale 'of firm and non-firm. capacity and energy,
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"(f) economic' dispatch of power resources within the State of Ceo.rgia,.
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d, however, that in no event'shall such arrangements -
irepose a higher percentage of reserve requirem~ents on' the par-3.,
. ticipating entity than that maintained by applicant. for sinilar
. resources.
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- - (4) Applicant shall sell full requiracents power' to any entity.
e Applicant shal1~ sell parpial requirer:.ents power to.any entity.
Such sales shall be made pursuant to rates on file with.the ' '
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Federal Power Cocaission,- or any successor regulatory agency, and subject to. nasonable. terms and conditions.
(5). (a) Applicant shall transmit ('?ti ay.snission service") ' bulk power over its ' system to. any' entity or entities with which it is interconnected, pursuant to rate schedules on file a
with the Federal Fower Cc=cissien which will fully cenpen-sate applicant for the use. of its system, to the extent that
- such arrangements can be accoccodated from a functional engineering. standpoint' and to the; extent that applicant has
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' c surplus. line capacity or reasonably available funds 'to finance new construction for this' purpose..To the extent i
the entity or entities are able, they shall reciprocally
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provide transmission service to applicant.
Transmission.
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. service vill be provided under this subparagraph for the delivery of power to an entity; for its or its r.emberst con-sumption and retail distribution or for' casual resale to another entity for (1) its consumption or (2) its retail a
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dis tribution. Nothing contained herein shall require the applicant to transnit bulk power so as to have the effect of oaking ~ the Tennessee Valley Authority ("TVA") or its distributors, directly or indirectly, a source of power I
supply outside the area determined by the TVA Board of
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Directors by resolution of Iby 16, 1966 to be the area for which the TVA or its distributors were the primary source
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~6-j of power supply on July 1,1957, the date specified in the Revenue Bond Act of 1959,16 USC 831 n-4.
7' (b) Applicant shall transmit over its system from any entity or entities with which it is interconnected, pursuant to rate.
schedules on file with the Federal Power Cocsission which j
'I vill fully compensate applicant for the use of its system, bulk, power which results frord any such entity having excess
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capacity available from self-owned generating resources in,
the, State of Georgia, 'to the extent such excess necessarily res,ults from economic unit sizing or from failure to fore-cast load accurately or froci such generating resources bec'oming operational earlier' than the planned in-service date, to the extent that such arrangements can be 4
accoc:nodated from a functional engineering standpoint',
and to the extent applicant has surplus line capacity available.
(6) Up'on request, applicant shall prov(de service to any entity purchasing partial require =ents service, full requirecants -
service or i. transmission service from applicant at a delivery
. voltage appropriate for loads served by such entity, coc=en-surate with applicant's available trans=ission facilities.
n, Sales of such service shall be bagg. pursuant to rates on file l
4 with the Federal Power Co:::.ission or any successor regulatory
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agency, and subject to reasonable ter=s and com'itions.
(7) Upon reasonable notice applicant shall grant any entity the opportunity to purchase an appropriate share in the ownership of, or, at the option of the entity, to purchase an appropriate share of unit power from, each of the following nuclear the same
.. generating units at applicant's costs, to the extent Natch 2, Vogtle 1, Vogtle 2,
.are. constructed and operated:
Vogtle 3, Vogtle 4, and any other nucicar generating unit con-
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structed by applicant in the State of Georgia uhich, in the-application filed with the USAEC or its successor agency, is scheduled for commercial operation prior to January 1,1989.
An entity's request for a share e.ast have regard for the econonic size of such nuclear unit (s), for the entity's load size, grouth and characteris tics, and for decands upon applicant's l
l systen from other entities and applicant's retail customers, all in accordance with cound engineering practice. Executory agree-nents to accomplish the foregoing shall contain provisions l
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reasonably s'pecified_ by applicant requiring the entity to
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consumate and pay for such purchase by a t early date or dates certain.
For purposes of this provision, " unit power" shall-I 1
nean capacity and associated energy from a specified generating unit'.
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(8) To effect the foregoing conditions, the following steps shall f-
' be taken:
'(a) Applicant s; hall file with the. appropriate regulatory author-ities,and thereaf ter maintain in force as needed an -
app lropriate transmission tariff available to. any entity; f
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'(b) Applicant shall file with the appropriate regulatory author -
l ities and' thereaf ter maintain in - force as needed an f,.
appropriate partial requirenants tariff available to any entity; applicant'shall have its liability limited to the
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' partial requirements. service actually contracted for and the entity shall be made responsible for the security of' the bul'k power supply resources a.cquired by the; entity ' fren I
sources other t,han the applicant; (c) Applicant shall acend the' general terms and conditicas of its
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current Federal Power Comission tariff and thereaf ter twin-tain in force as needed provis,$ons to enabic any entity to receive bulk pou~er at transmission voltage at appropriate rates;-
(d) Applicant shall not have the unilateral right to defeat. the
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intended access by each entity to alternative sources of I
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, ' bulk power supply provided by the conditions to this, license;-
but applicant shall retain the right to seek regulatory approval -of changes in its tariff s to the end that.it he
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adequately compensated for services it provides, specifically
. ' including _ but not limited to, the provisions of Scction 205 c
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of the Federal Power Act;
.c (e) Applicent shall use its best efforts to amend any outstand-ing' contract to which it is a party that contains provisions which are inconsistent with the conditions of this license; (f) Appliccnt af firms that no consents are or vill become necessary from applicant's parent, affiliates or subsid-inries to enable applicant to carry out its obligations hereunder or to enchic the entities to enjoy their rights l
hereunder; (O
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. (g) Ali provisions of these conditic s shall be subject to and
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States and of the State of Georgia, as applicable, and with j
i=plenanted in accordance with the laws of. the United i
rules, regulations and orders of agencies of both, as applicable.
E.
Tnis facility is subject to the following conditions for the protec-I l
tion of the, environment:
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(1) The applicant shall take the necessary mitigating actions, includ-
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ing those applicant com=iteents se=narized in Section 4.5 of' the l
Final; Environmental Statement, during construction of the station and associated transmission lines to avoid unnecessary adverse environmental impacts f rom construction activities; (2)' A control program shall be. established by the applicant to pro-~
i vide for a periodic review of all construction activities to I
assure that those activities conform to the environmental con-l j
ditions set forth in thi,s permit;
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(3) Behore engaging in a constructf on' activity tihich may result in f
a sigt.ificant adverse environmental impact that was not evalu-
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ated or that is significantly greater than that evaluated h i
the Final Environmental Statement,.-the applicant shall ' provide vritten notification to the Director of Licensing.
(4) If u2 expected har=ful effects or evidence of unexpected irre-(
s versible damage are detected during facility construction, the I
- l. applicant shall provide an acceptable analysis of the problem and a plan of action-to eliminate or significantly reduce the
. harmful effects or damege.
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l (5) 1he plant shall be designed such that:
(a) Tne plant discharge stream is continuously nonitored for
, total residual chlorine concentration.
(b) The total residual chlorine concentration within 5 feet of the diffuser ports vill be less then 01 ppm when all four units are in operation.
I (c) All the cells in the intake structure vill normally be used during operation of the intake punps.
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'(d).The dif.fuser design will'be based on 6" diameter ports.
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[(6) The construction program and practices shalk.~ine'orporate't
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following ieatures:
(a)'. Rate of pumpage during dewatering will be' low enough to; prevent siltation in Beaverdam Creek.
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-(b) The Environmental Protection Agency guidelines (Water Quality -
, Considerations for Construction and Dredging ' Operation, EPA,-
Southeatst' Region,.' April 1971). for the operation of retention basins will~ be followed in order to minimize the potential
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. adverse effects. on Beaverdam Creek as' a' result of erosion E,
during construction.
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..- The retention basins will-be' drained between storms' when (c).
. the. turbidity of' the impounded water has decreased to
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acceptable levels.
(7) Prior to. construction of the intake structure, the applicant shall submit the resules of the aquatic nonitoring programs..
gd and an evaluation'~of the environmental impact. of the intake'.
canal and' intake structure which will satisfy the staff that '
ffect on'the
.h' impingement will not have a significant adverse e adult population of resident and anadromous fish in the
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- Savannah River.
This permit is subject to the limitation that a license authorizing'-
operation of the. facility will not be issued by the' Com:'ission unless 4.
g final safety
.(a) the applicant submits to the Commission the comp
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time to time;l (b) -the Commission finds that~ the final design.provides reasonable' assurance that the health and safety of the public will?
not 'he endangered by the operation' of. the facility in' accordance with procedures' approved by it in connection with the issuance o
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licensei (c) the Com:
be in accordance with 10 CFR Part 50, Appendix D, of the Commission's
' regulations and all applicable requirements of said' A
- and the execution of an indemnity agreenent as required by Section 170 j
of the Act.
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This per: tit is effective as of. its date of issusace and. shall expire on-
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FOR THE ATO IIC ENERGY COltGSSION
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A. Giambusso, Meputy Director for Reactor Projects Directorate of Licensing Date.of Issuance:-
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' JU!i. _ 2 8 1974-
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_CEORCIA POWER'COMPAt!Y.
- DOCKET MO.'50-425' c
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ALVIN W. VOGILE NUCLEAR PLANT, UNIT 2
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CONSTRUCTION PERMIT.
s Construction Permit No. CPPR-109
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The. Atomic Energy Comission (the f. omission) havitig found that:
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A.
The application for construction. permit complies 'with the: require-
, ments.of:the Atomic Erergy'Act of 1954, as amended, and the rules-
",and regulations of the; Commission, there is reasonable. assurance -
m that the activities ' authorized by the permit will be' condueted in.
compliance with the' rules and regulations of the Co= mission,' and
!all; required notifications to other agencies. or bodies' have been '
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duly made;
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. ', i The Georgia Power Company (the applicant) has -described the proposed e
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design' of. the' Alvin U. Vogtle Nuclear Plant, Unit ' 2 (the facility),
1 Lincluding, but'not limited to,.the prdncipal architectural and in engineering; criteria-for' the. design enrTins identified the.cajor features or components -incorporated. therein for the proteetien of.
the health and' safety of the public;
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So, h' further technical or design information as may be C.
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'. required, to comp 1ete the safety analysis, and uhich can reasonably 4
be lef t for later consideration, vill be. supplied in the final 4
safety analysis' report; "D. " Safety.. features or components, if any, which require research and.
development have been described by the applicant' and the applicant a
has identified, and.there vill be conducted, a research and development program reasonably. designed to resolve any safety questions' associated.with such features or components; E.
On the basis of the foregoing, there is reasonable assurance that-2
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'(1)'such safety questions will be satisfactorily resolved at or L
before the latest date stated in the application for completion of construction 'of the proposed facility and (ii) taking into con-sideration the site criteria contnined.in 10 CFR Part 100, the 1
proposed facility can be constructed and operated at the proposed
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tocation without u= doe risu.to the nea1th nna safety of the Pob11c; p
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1 The applicant is technica11y' qualified to design and construct the
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proposed facility; 1
1 The applicant is financially qualified to design and construct G.
the proposed facility; t
The issuance of. a pernit for the construction of the facility will R.
not be inimical to the common defense and security or to the health and' safety o'f the,public; and i
1 Af ter weighing the environmental, economic, technical and other 4
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benefits of the facility against environmental cost's and considering f
available alternatives, the issuance ~ of a construction. permit, subject te; the conditions for protection of the environment set-1 j
forth herein, is in accordance with 10 CFR Part 50, Appendix D, of j
the Cozmission's regulations and all applicable requirements of said Appendix D have been satisfied.
Pursuant to Section 103 of the Ato::'ie Energy Act of 1954, as acended j
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(the Act), and Title 10, Chapter I, Code of Federal Regulations, Part' 50, " Licensing of Produccion and Utilization 7acilities", a:d pursuant
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. to the Initial Decisions of the Atomic Safety and Licensing Board dated
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May 24~, 1974,- and June 27, 1974, the Atomic Energy Cor:tission (the Com--
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mission) hereby issues a construction percit to the applicant for a utilization facility cesigned to operate E 3411 negcuatts thercal as described in the applic. tion and acendments thereto (the application) filed in this matter by the applicant and as core fully described in the evidence received at the public hearing upon that application.
The faci-lity,.known as the Alvin U. Vogtle Nuclear Plant, Unit 2, vill be lo'cated on the applicant's site in Burke County, Georgia.
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3.
This perrdt shall be deemed to contain and be subject to the conditions f
specified in Sections 50.54 and 50.55, of said regulations; is' subject l
to all applicable provisions of the Act, and rules, regulations,, and orders of the Commission now or hereaf ter in effect; and is subje,ct to i
.the conditions specified or incorporated belo:n 1
A.
The earliest date for the completion of the facili.ty is October l' 80, and the latest date for completion is April 1982, i
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B.
The facility shall be constructed and located at the site as described in the application, in Burke County, Georgia.
4 C.
This construction permit authorizes the applicant to construct the facility described in the application and the hearing record, in accordance with the principal architectural and engineering cri-(
teria and environmental protection co=mitments set forth charcin.
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Antitrust conditions es. follows :
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~(1)'As used herein:
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(a) " Entity" means any financially responsible person, private.
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or public corporation, municipality, county, cooperative, association, ' joint stock association or business trust, I
owning, operating or proposing to own'or operate equipment
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-or facilities within the State of Georgia (other than..
Chatham, Effingham, Fannin, Towns and Union Counties) for the generation, transmission or distribution of electricity,:
provided that, except for municipalities, counties, or. rural electric cooperatives, " entity" is restricted. to those which are or vill be public utilities under the laws-of the State of Georgia or under the laws of the United States, and are or will be providing retail electri'c service under a contract or rate schedule on file with and subject to the regulation a
of the Public Service Cornission of the State. of Georgia or
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. any regulatory agency,of the United States, and, provided, further,. that as' to municipalities ~, counties or rural
.,, 3 electric cooperatives, " entity" is restricted to those
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which provide electricity to the public at retail within j
the Gtate. of. Georgia (other than Chatham, Effingham, Fannin, Towns and Union Counties) or to.-responsible and legally qualified organizations of such municipalities, counties and/or cooperatives in the State of Georgia (othat than Chatham,.Effingham, Fannin, Towns and Uriion Counties) to.
the extent they may bind their members.
f (b) " Applicant" neans teorgia Power Company, any success assignee of this license, or assignee of all or substantia'11y all of Georgia Power Conpany's ' assets, and any affiliate or subsidiary of. Georgia Power Company to the extent it engages in the ownership of any bulk power' supply generation or
. transmission resource in the State of Geprgia (but specifically not including (1) flood rights and other land rights acquired
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, n.p.
in the State of Georgia incidental to hydroelectric generation f acilities. located in another state and (2) facil-
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I ities located vest of the thread of the stream on that part of the Chattahoochee River serving as the boundary between l
the Sta,tes of Georgia and Alabama).
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(2) Applicant ree-ognizes that it is often in the public interest l
for those engeging in bulk power supply and purchases to interconnect, coordinate for reliability and econopy, and
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engage in bulk power supply transactions in order to increase 4
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o interconnected system reliability and reduce the costs of Such arrangements. nust provide for applicant's electric po er.
costs (including a reasonable return)-in connection therewith i
'and allow othac participating entities full access. to the. bene-fits: available from interconnected bulk power supply operations 1
and cust provide net, benefits to applicant.
In entering into.
such arrangements neither applicant nor any other participant should be required to violate the' principles of sound engineering practice 'or for, ego a reasonably. contemporaneous alternative arrange =ent with' another, developed in good faith in arms
, length negotiations (but not including arrangements between applicant and its affiliates' or subsidiaries which. impair entities' rights hereunder core than they would be impaired were such arrange =ents made in good f aith between applicant and a-non-affiliate or non-subsidiary) which affords it greater bene-fits. Any such arrangement cust provide for adequate notice and ~ joint planning procedures consistent with sound engineering practice, and,cust relieve applicant from obligations undertaken by 'it in the event such procedures are not followed by. any
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- participating entity,
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Applicant recognizes that each entity may acquire some or all of its bulk' power supply from sources other than applicant.
f In the implementation of the obligEions stated in the succeeding paragraphs, applicant and entities shall act in accordance with the foregoing principles, end these principles are conditions to d
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..)eachofapplicant'sobligationshereinunertaen.
- (3) Applicant shall interconnect with any entity which provides, or j
i which has undertaken firm contractual obligations to provide,
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sone or all of its bulk power supply from sources other than applicant on terns to be included in an interconnection agree-l een'. which shall provide for appropriate allocation of the costs of interconnection facilities; provided, however, that if an entity undertakes to negotiate such a firm contractual
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obligation, the applicant shall, in good faith, negotiate with Such such entity concerning any proposed interconnection.
interconnection agreenent shall provide, without undue pref-erence or discrimination, for the following, among other things, insofar as consistent with the operating necessities of applicant'n' and any participating entity's systems:
(a) maintenance and coordination of reserves, including, where appropriate, the purchase and sale thereof,
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(b) emergency support,
, c) maintenance. support,
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'(d) ~ economy energy exchanges,
- (e) purchase and sale of firm and non-firm capacity and energy,
.j (f) economic' dispatch of power resources within the State of
- provided, hauever, that in no event shall.such arrangements Impose a higher percentage of reserve requirements on the par-j
,, L ticipating entity than that maintained by applicant for similar l
resources.
(4) Applicant shall sell full requirements power to~ any entity, j
Applicant shall sell partini requirements power to any entity.
Such sales shall be nade pursuant,to rates on file with ' the Federal Power Cocnissibn, or any successor regulatory agency,,,
and subject to reasonable terms and conditions.
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(5)- (a) Applicant shall transmit (" transmission service") bulk
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. power over its system to gnpentity or entities with which it.is interconnected, pursuant to rate schedules on file j
with the Federal Power Commission which vill. fully compen; -
sate applicant for the use of its systen, to the extent that l
l' such arrangements can be acco=modated from a functional.
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engineering standpoint and to the extent that appl 1 cant has surplus line capacity or reasonably available funds to j
finance new construction for this purpose. To the ' extent '
the entity or entities are able, they shall reciprocally, Transmission provide transmission service to applicant.
service vill be provided under this subparagraph for the delivery of power to an entity for its.or its members' con-sumption and retail distribution or for casual resale to another entity for (1) its consumption or (2) its retail
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dis tribution. Nothing contained herein shall require the to transmit bulk pouer so as to have the effect of l
applicant making the Tennessee Valley Authority ("TVA") or its distributors, directly or indirectly, a source of power supply outside the area deternined by the TVA Lonrd of Directors by resolution of May 16, 1955 to be the area for which the TVA or its distributors were the primary souree (O
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'of p'over supply on July l',1957, the date specified in the P.evende Bond Act of 1959,16'USC 831 n-4.
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. ' entities with which lit is interconnected, pursuant to rate j
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, vill fully' compensate applicant for the ?use of its systen, 1
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- bulk power which results f ron any such entity having excess [ '
capacity available: frou self-owned generating. resources in-the state of Georgia, to the extent such excess necessarily -
- results from economic unit si-ing or from failure to fore-i f
cast load accurately or 'fron such generating resources l
becosing operational earlier than the planned in-service
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date, to the extent that such arrangements can be' l
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acco==odated from 'a functional engineering standpoint,-
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. applicant shall provide service to any entity,
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. purchasing partial requirements service, full requitecents R
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service or transmission serv'.* ce fro 3 applicant at 'a delivery c-voltage appropriate for loads ' served by-- sue'n entity, co~n- -
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'surate with applicant's available? transmission facilities.
1 Sales of such service shall be made pursuant to rates on file with the Federal Power Commissien or any successor regulatory-
~j agency, and subject to reasonable" Terns and conditions.
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-(7) Upon reasonable notice applicant shall grant any entity the
- l. opportunity to purchase an appropriate share 1n the ownership
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of, or, at. the option of the entity, to purchase an appropriate-1
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share of unit power from, each of the following nucleer j
generating units at applicant's costs, to the extent' the same j
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- are co'nstructed and operated:
Hatch" 2,. Vogtle 1 Vogtle 2, j
yogtle 3, Vogtle 4, and any other nuclear generating unit con-structed by applicant in the State of Georgia which, in the
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scheduled for commercial operation prior to January 1,1989.
I An entity's request for a share cust have regard for the econonic size of'such nuclear unit (s), for the entity's load-
' size, growth and characteristics, and for demands upon applicant's system from other entities and applicant's retail customers,~ all in accordance with sound engineering practice. Executory agree-l ments to accomplish the foregoing shall contain provisions L
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reasonably specified by applicant requiring the entity to consucnate' cnd pay for such purchase by an early date or dates certain. For purposes of this provision, '" unit power" shall '
mean capacity and associated energy from a specified generating unit.
l (8)' To effect the foregoing conditions, the following steps shall be taken:
- (a) Applicant 'shall-file with the appropriate regulatory author-ities and thereaf ter maintain in force as needed an appropriate transmission tariff available to any entity; (b) - Applicant shall file with the appropriate regulatory author.
ities and thereaf ter maintain in force as needed an-appropriate partial requirements tariff available to any-entity; applicant shall have' its liability limited to the partial requirements service actually contracted for and the entity shall be made responsible for the security of the bulk power supply ~ resources acquired by the entity from
' sources other than the applicant;
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(c) Applicant shall amend the general tercs and conditions of its current Federal Power Cot:nission tariff and thereaf ter nain-tain in force as needed provisions to enable' any entity to l
receive bulk power at transmission voltage at appropriate j
F rates;
,j l (d) /.pplicant shall not have the unilateral right to defeat 'the intended access by each entity to alternative sources of l
bulk power supply provided by the conditions to this license; but applicant cha_11 retain the right to seek regulatory approval of changes in its tariffs to the end that it be I
adequately co:npensated for seivices it provides, specifically
. including, but not limited to, the provisions of Section 205 of the Federal Power Act; q
(e) Applicant shall use its best efforts to anend any outstand-ing contract to which it is a party that contains provisions which are inconsistent with the conditions of this license;,'
(f) Applicint af firms that no consents are or vill become necessary f rom applicant's parent, affiliates or subsid-iaries to enable applicant to entry out its oblisctions hereunder or to enable the entities to enjoy their rights hereunder; l
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(g) All provisions of these conditions shall be subject to and implemented in accordance' with the laws of the United States and of the State of Georgia, as applicable, and with i
rules, regulations and ' orders of agencies of both, as -
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applicable.
E.
This facility is subject to the following conditions' for the protec-tion of the environ =ent:
h (1) The applicant'shall tata the necessary mitigating actions,'includ-l ing tho'se applicant cocaitments s"m ariced in Section 4.5 of 'the Final Environmental Statement, during construction of the station
,l and associated transmission ' lines to avoid unnecessary adverse,
environmental impacts from construction activities;
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I (2) A control program shall be established by the applicant to pro-vide for a periodic review of all construction activities to assure. that those activities conform to the environmental" con-ditions set forth in this permit; O.
cn sef-e ensasa a a caetructie :ctivity *ich ma7 rau1t im -
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a significant adverse environmental impact that was not evalu-ated or that is significantly greater than that evaluated in the Final Environmental Statement, the applicant 'shall provide written notification to the Dirececr of Licensing.
(4) If unexpected harnful effects or evidence of unexpected irre-versible damage are detected during facility construction, the applicant.shall provide an acceptable analysis of th'a problem and a plan of action to eliminate or significantly reduce the
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harmful effects or damage.
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(5) The plant shall be designed such that:
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l total residual chlorine concentration.
(b) Tne total residual chlorine concentration within 5 feet. of,
the diffuser ports will be less than 0.1 ppm when all four units are in operation.
(c) All the ec11s in the intake structure will normally bc used during operation of the intake pumps.
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'(d) The ' diffuser design will be based on 6" diameter ports.
. (6) The construction program and practices -shall incorporate.th'e following' features:
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. (a)c Rate 'of pumpagb. during dewatering vill.be low enough to '
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(b) The Environmental Protection Agency guidelines- (Water juality
- Considerations for Construction and Dredging Operation,- EPA,
. Southeast-Region,. April 1971) for the operation of retention-
~ basins will be followed in order to minimize. the potential
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1ady'erse' effects. on Beaverdam-Creek as.a result of erosion during construction.
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.-(7) Prior to construction of the intake structure, the applicant
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shall submit the results of the aquatic conitoring. programs S
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and an-evaluation of the environmental impact of, the intake-E c
f canal and intake structure which will satisfy the-staf f that impingement; will not. have a significant adverse effect; on the d
'adulti population of resident and GEadronous -fish.in the
~Swannah River.
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This> permit is subject' to the licitation that a license authorizing operation of L the facility will not be issued by the Co ission unless
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(a) the applicant submit;s' to the Commission the complete final safetr
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.. time to time; (b) :the Commission finds that the final design provides l reasonable assurance that. the health and safety of the.public will not be. endangered by the operation of the facility in accordance with procedures approved by it in connection with the issuance-of said license; (c) the Commission finds that operation of the facility will be in accordance with 10 CFR Part 50, Appendix D, of the Co=nission?s regulations and all applicable requirceents of said Appendix D were
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satisfied, and (d) the applicant.subnits ' proof of financial protection p'.f and the' execution of an indemnity egreement as required by Nction 170
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FOR TIE AT0!GC DIERGY ColcrISSION..
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A. Giambusso, Deputy Director for Reactor.. Projects c !.'.
Directorate of Licensing l
i Date df Issuance:
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.JUN 2 6 G74
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Chapter l-Eclear Regulatory Commission
{ 50.34 f
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(4) The information described in minimum information
- to be included 3
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paragraphs (aX1) and (2) of this sec-shall consist of the following:
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hd a tion shall be submitted as a separate (1) A description and safety assess-4 tions document prior to any other part of ment of the site on which the facility
\\ sn.Y% #l the license application as provided in is to be located, with appropriate at.
)riate i 2.101 of this chapter. "
design. Special attention should be di-f 1@ J.).'T* '.3 W e the ucted paragraph (b) and in accordance with tention to features affecting facility f
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19p11 (b) Except as provided in paragraph rected to the site evaluation factors
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tv-te (d). any person who applies for a class identified in Part 100 of this chapter,
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pera.
103 construction permit for a nuclear Such assessment shall contain an anal-m al in.
l power reactor on or after July 28,1975 ysis ar.d evaluation of the major strue.
- E' "-Q ;' i shall submit the document titled "In' tures, systems and components of the d'
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D.
Re.
formation Requested by the Attorney facility which bear significantly on the
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- nfor.
General for Ant.itrust Review" at least acceptability of the site under the site I
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.M such nine (9) months but not more than evaluation factors identified in Part b
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=and thirty six months prior to the date of 100 of this chapter, assuming that the i
I crr.t-submittal of any part of the applica-facility will be operated at the ulti-M-
ion.
tion for a class 103 construction mate power level'which is contemplat-9
P'""E' ed by the applicant. With respect to
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(c)iReserved) operation at the projected initial
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3-43s, (d) Any person who applies for a power level, the applicant is required L
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class 103 construction permit for a nu-to, suBmM information prescribed in G1 clear power reactor pursuant, to the paragraphs (aX2) through (8) of this 9
fl at 35 provisions of 5 2.101(a-1) and Subpart section, as well as the information re-
.d.e 4 P of Part 2 of this chapter shall
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submit the document title "Informa-quired by this paragraph, in support
.g; 7 FR of the application for a construction tion Requested by the Attorney Gen-
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i eral for Antitrust Review" at least permit.
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nine (9) months but not more than (2) A summary description and dis-
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thirty six months prior to the filing of cussion of the facility, with special at-truc-part two or part three of the applica. tention to design and operating char.
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tion, whichever part is filed first, as acteristics, unusual or novel design gJ N~ C' specified in 12.101(a-1) of this chap-features, and principal safety consider-d as
- ter, ations.
(e) Any person who applies for a (3) The preliminary design of the fa-0 l'
class 103 construction permit for a cility including:,
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uranium enrichment or fuel reprocess-(1) The principal design criteria for O
ing plant shall submit such informa- ' the facility.' Appendix A, General "8J I
11 n as may be requested by the Attor-Design Criteria for Nuclear Power i
j ids 0 tor ney General for antitrust review, as a Plants, establishes minimum require-
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'tlon
, A; g,g, separate document as soon as possible ments for the principal design criteria i
. _ :9. *Y and in accordance with l 2.101 of this for water cooled nuclear power plants 3
db chapter.
aimilar in design and location to plants i
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g of (Sec.102. Puth L 91-190. 83 Stat 853 (42 for which construction permits have N. J 71ec-j3W7 iing U.S.C. 4232); s*c. 201, as amended. Pub. L previously been issued by the Commis-1 1400 93-438, s8 Stat.1242, Pub. L 94-79,80 Stat, alon and provides guidance to appll-
,. 5 mis-i 413 (42 U.S.C 6441n cants for construction permits in es.
the j'
(39 FR 34395. Sept.25,1974 as amended at tablishing principal design criteria for D,#'
pen-I 42 FR 23s87.Llay 5,1977; 42 FR 25721, May other types of nuclear power units; 19.1977; 43 FR 49775, Oct. 25,1979; 44 FR 4
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. Oct. 22,1Frg)
-tion
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.The applicant may provide information p
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1 50.34 Contents of applications; technical required by this paragraph in the form of a
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ma, informaSon.
discussion, with specific references, of siml-d
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t N88 larttles to and dMferences from, facilities of p'/7 6
(a) Preliminary safety analysis almilar design for which appucations have
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,rnis.
9'4 the-wport Each application for a con-previously been filed with the commission.
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struction permit shall include a pre-
- Oeneral design criteria for chemical p
Uminary safety analysis report. The processing factittles are being developed.
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g (11) The design bases and the rela. the quality assurara program for a
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tion of the design bases to the princl. nuclear power plant or a fuel repro.
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- .(J pal design criteria; ceasing plant shall include a discussion fMg
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1 (111) Information relative to materi. of how the applit able requirements of a
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als of construction, general arrange. Appendix B wiU be sajisfied.
~j ment, and approximate dimensions, (8) An identificatie of those struc-
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ance that the final design will conform facility, if any, which require research s*
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to the design bases with adequate and development to confirm the ade-
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quacy of their design; and identifica-Yp
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.(4) A preliminary analysis and evalu. tion and description of the research 1
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of structures, systems, and compo-be conducted to resolve any safety b )l s
3 nents of the facility with the objective questions associated with such strue.
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J-of assessing the risk to public health tures, systems or compaments: and a l
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and safety resulting from operation of schedule of the research and develop.
1' da the facility and including determina. ment program showing that such t
tion of (1) the margins of safety during safety questions wiu be resolved at or J
normal operations and transient condi. before the latest date stated in the ap.
p tions antidrated during the life of the plication for completion of construe.
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facility, and (11) the adequacy of strue, tion of the facility, tures, systeams, and components pro-(9) The technical quaRfications of i
7 vided for the prevention of accidents the applicant to engage in the pro-
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and the unitasation of the conse-posed activities in accordance with the 1
d quences of necidents. Analysis and regulations in this chapter.
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evaluation af ECCS cooling perform.
(10) A discussion of the applicant's -
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ance following postulated loss-of-cool. preliminary plans for coping with
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'L ant accidents shall be performed in ac-emergencies. Appendix E sets forth
< m, cordance with the requirements of items which shall be included in these r
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't t 50.46 of this part for facilities for plans.
3 dQ which construct.lon permits may be (11) On or after February 5,1979, 1
4' 6 F,~*d-Q,%
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issued after December 28,1974.
appUcants who apply for construction l,
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- (5) An identification and justifica. permits for nuclear powerplants to be 1.Wtp'e'm.h.,M '(i bles, conditions, or other items which potential har,ards to the structures, i
g tion for the selection of those varia. built on multiunit sites aball identify l
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are determined as the result of pre-systems and components funportant to l
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N. h liminary safety analysis and evalua. safety of operating nuclear facilities
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y' tion to be probable subjects of techni-from construction activities. A discus-cal specifications for the facility, with sion shall also be included of any man-lq p,i ?/
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1 Mh>2d u,y y bp special attention given to,those. items agerial and administrative controls cpg which may significantlyithfiue'nce the that will be used during construction g
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an appilcation for a construction (b) Final safety sacApris report.
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permit fDed prior.to January 16,1969. Each application for a license to oper-I W
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(6) A prelkninary plan for the appil-ate a faculty shall include a final g
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cant's orgagemunn, training of person. safety analysis report. The final safety g
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net, and condmet of operations.
analysis report shall include informa.
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('l) A description of the quality as-tion that describes the faellity, pre.
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design, fabrication, construction, and on its operation. and presessts a safety
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M,,e 41 testing of the structures, systems, and ' analysis of the structures, systems, 3
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W components of the facility. Appendix and components and of the facility as
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+7 B, " Quality Assurance Criteria for Nu.
a whole, and shall include the follow-3
'l clear Power Planta and Puel Repro. Ing:
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V cessing Plants." acts forth the require-(1) All current informatkan,,ruch as I
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ments for quality assurance programs the results of environmental and me-
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V' for nuclear power plants and fuel re-teorological monitoring
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- :,63.-; j ;Q' processing planta. The description of which has been developed since issu.
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systems which may contain radioactivity safe operation. Nuclear power plants ag q o,,g
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l and handling, radioactive waste, and other a
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shall tee designed to assure adequate safety fuel reprocessing plants include structures 7 safeL{
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systems, and components that prevent [, 4 J,
under normal and postulated accident con-
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mitigate the consequen f postulated l
ditions. These systems shall be designed (Il cidents that could cause
,'a with a capability to perrnit appropriate peri-i due risk to g odic inspection and testirg of components health and sa' fety of the public. This appen.
'y important to safety. (2) with suitable shlend-dix establishes quality assurs.nce require.
2gt ing for radiation protection, (3) with appro-ments for the design, construction, and r
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priate containment. confinement., and futer. eration of those structures, systems, M*"'
ing systems. (4) wit.h a residual heat remov-components. The pertinent requirements I*
al capability having reliab!11ty and testabi-this appendix apply to all activities aff i g lity that reflects the importance to safety of ing the safety r-lated functions of th l
decay heat and other residual heat removal, structures, sycems, and components; th d
bricating, handling, shipping, storing, eleactivities in I# f and (5) to prevent altnificant reductico in fuel storage coolant inventory under acci.
ed ing, erecting. Inst &Hing, inspecung, te of th -
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Prevention of criticality in P
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/uel storspe and handlina. Criticality in the and F
fuel storage and handling system shall be ance,,used in this appendix. " quality assur.
As pon8 '
genisst.
I' prevented by physical systems or processes, mmprises all those planned and sysW evality.
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( F preferably by use of geometrically safe con.
tematic actions necersary to provide ade.
- Jormsf figurations, quate confidence that a structure, systein, satlora t
Critedon 63-Afonitoring fuel and apost, or cornponent will perform satisfactorily in gens tu 5
storspe. Appropriate systems Shall be pro.
service. Quality assurance includes quallty alsatfor J
vided in fuel storage and radioactive waste control, which comprises those quality as.
Finatl*r systerns and associated handling areas (1) to surance actions related to the physical char.'
signed t detect conditions that snay result ip loss of acteristics of a material, structure, compo, j
tive est residual heat removal capability and exces. nent, or system which provide a means to assuren
~.
l-sive radiation levels and (2) to initlate ap-control the quauty of the material, strue. j activitle
'g propriate safety actions.
J V
ture, component, or system to predeter.
5 P'ff0f" g
6 CriteHon 64-Monitoring radioactivity re.
tulned requirements.
levtis D' leases. Means shall be provided for anonitor.
A y T{
ing the reactor containment atmosphere,
- 2. OncAxtrartois I
to peric spaces containing components for recircula.
3 tion of loss-of coolant accident fluids, efflu.
The applicant' shall be respons!bie for *
,g ent discharge paths, and the plant environs the establishment and execution of the Thes y
for radioactivity that may be released from quality assurance program. The app!! cant est praz J
nortnal operations, including anticipated anay delegate to others, such as contractors, I
operational occurrences, and from postulat. agents, or consultants, the work of estab.:
scMdd quality 4
I ed accidents, 11shing.nd executing the quality assurance Wh 2 (Sec.161, as amended, Pub. L 63.D, 68 program, or any part thereof, but shall This pn
,t h3
- '}
Stat. 948 (42 U.S.C'. 2201); pec, 201, as ty and duties of persons and organization retain responsibility therefor. The authort..
shan be
"" DCU 9
3 amended. Pub. L 93-438, 88 Stat: 1242, Pub.
accordar
- M.fG*- b{
L 94-79,89 Stat. 413 (42 U.S.C. 5841))
performing activities affecting the safety re. y
'I #
4:,
lated functions of structures, systems, and
",;4,.'d3 f 36 FR 3256, Feb. 20,1971, as amended at 36 cornponents shall be clearly established and
(
V.'*%
FR 12733, July 7,1971141 FR 8258. Feb.12, delineated in writing. These activities in.
f WW. 3 1970; 43 FR 50163. Oct. 27,19781 ciudt both the performing functions of at.
8]",g p
t talning quality objectives and the quality {-
J assurance functions. The quality assurance '
, % nat
%. gL z r
g' Aryrwntz B-QUA1.!TY ASSURANCr Cal
- functions are those of (a) assuring that an yhe Ous TERIA FOR NUC1Jr.AR Powra Pl. ANTS appropriate quallty assurance program is es.
8" jp. y t,."e.
AND Furt, RzrnocessrNo Pz. ANTS Lablished and effectively executed and (b)
" I I verifytng, such as by checking, auditing, and 7th E Introduction. Every app!! cant for a con.
Inspect n, that acMMes affectins W ;
affectins struction permit is required by the provl.
t under at slont of I 50.34 to include in its preliminary
'Wh!]e the term " applicant" is used in troHed c l:
safety analysis report a description of the these criteria, the requirements are, of priate e quality assurance program to be applied to jh ' '*
?'D N j.~
the design, fabrication, construction, and course, app!! cable after such a person has -
eondittor
"* b.
Ne received a licente to construct s nd op**sta a such as
.w CI testing of the structures, systems, and com.
nuclear powerplant or a fue) reprocessing that all ponents of the facility. Every applicant for plant. These criteria will also be used for ha e bet
~$. a, an operating license is required to include, guidance in evaluating the adequacy of into aco e.1 Y N N t in its final safety analysis report, informa, quality assurance programs in use by hold.
processe; v
b M.N [,
tion pertaining to the managerial and ed.
era of construction permits and otierat!ng II.
to attain
- P ministrative controls t.o be used to assure censes.
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' giants and.
a safety.related functions have been corrtetty - test. 'a'he program shall provide for ineaetri-
.t~
3 structurcs, performed. The persons and organizauona natfor' and training of personnel performing Gulated ac.
l' performing quality assurance funcuens activities affecting cuality as necessary to
?y; '.; M. f[f,M j s crevent er
,t,t
- r c -.. % -
snan have sufficient authority and organl-assure that suitable profletency is achieved k
'Q
- 'pr %" S t VM to the I
astional freedom to identify quality prob-and maintained. The applicant shall regu-
[*. -
< : g ' > (g ? y This tppen-lems; to initiate, recorncnerwi, or proude so-larly review the status and adequacy of the l
e Ice r3 quire-lutions; and to verify implementation of so-quality assurance program. Management of a
h,
&n, and* gp.
-- tutions. Such persons and cesanizations per.
other organizations participating in the
!qll.
h;C
elo i
.h W ystems, and a "* forming quality assurance functions shall quality assurance prograrn shall regularly F an g) h,' h *',,'.
'1,,,
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11rements of report to a management level such that this review the status and adequacy of that part 4
- 3a 1
(ties affect-required authority and organizational free-of the quality assurance prvitram which C) Cf those
[,
dem, hicluding sufficient todependence they are executing.
Rents; thtse from cost and schedule when opposed to 1N "W::. ? *. ' '
P.
i 1Ghasing, fa.
I safety consideradons, are provided. Because III. passon connot.
Qr -..
a tring, clein.
i of the many nriables invohred, such as the
,y & w; number of personnel, the type of activity Measures shan be established to asasar hp yh t.'
Eng. testing, g
(3, refueling, being performed, and the location or loca*
that applicable regulatory requirements and V
I'X Uons where activities are performed, the or-the design basis, as defined in 150.2 and as Ihl I E.'
I ' A ';.
I
,ality assur.
l ganizauonal structure for caecuting the in the license applicauon, for j8 h'/' d: '? '
specified QM ed and sys.
8 tuality assurance program anay take urious those structures, systems, and components "r. b '" "*
t rovide ad).
forms provided that the persons and organi. to which this appendix applies an correctly N'
E*
( ',', ' J'<*
tre, syst:m, g
sadons assigned the quality assurance func.
translated into specifications, drawings, pro-d i
,e' I W 'M. W.
factorny in tions have this required authority and orga* cedures, and instructions. These enessures 8b
@..! % 'V.$
alsational freedom. Irrespective of the orga*
shall include provisions to assnre that ap-k '
des quality I
P propriate quality standards are spedfled 4
^t dj' -
quality as, alsauonal structure, the hdividual(s) as-
'~
nM,6 /'V- ['O and inc udet in design documents and thal
,devfauo)ns from such standards are eon.
i ysical char, signed the responsibility for aswring effec
- are, 'eompo, t'
Uvs esecution of any portion of the quality 4'
O mans to t
assurance program at any lomtion where troUed. Measures shau also be established P @.c 7*
. rial, strue, setivttles subject to this appendix are being for the selection and review for suitabulty O'd i
9 predeter-performed shall have direct amaan to such of application of materials, parts, eenip.
L M'-
l 1
nevels of management as may be necessarY ment, and processes that are essential to the 4
l
{ ;;t to perform this function.
safety related functions of the structures, I
systems and components.
A@=
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it.eoALin asavaa m osaAM Measures shall be established for the C - @ r.~ ce t
' Identification and control of design 1Dier.
M
- - 8f the The app!! cant shall estabitsh at the earli. faces pnd for coordination among partici-p h
- "PPU#*^g ist practicable time, ansistent with the pating dealsa organizations. These measures 4,.
J schedule for accomplishing the activities, a shall include the establishment of proce-i M.
1T fD i
i.i!. with the requirements of this appendix, dures among participating design orvar*=-
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tuality assurance program which complies b
a
'4 tions for the review, approval, release, es-
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This program shall be documented by writ-tribution, and revision of documents involv.
"* d but a I
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6.,
ten policies, procedures, or instructions and ing design interfaces.
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thall be carried out throughout plant life in The design control measures shall prodde y
t ns
' safety re-tocordance with those poucles, procedures, for verifying or checking the adequacy of i
d te instructions. The applicant shall identify design,' such as by the performance of i
p*j I
d i
the structures, systems, and components to design reviews, by the use of alternate or
' * " " g gg.
gram and the tr.;Jor organistuena partici-simplified calculational methods, or by the
}
y ht he covered by the quality assurance pro-
.idues in.
, W W, Dating in the program, together with the performance of a suitable testing progisms.
O$anc2 The qualhy assurance program shaU pro-performed by individuals or groups other
. (-
- h,f4, dealsnated functions of these organizauona. The vertfring or checking process shall be
." Cunlity
.=
- D g an than those who performed the criptun]
b es-elde control over activities affecting the design, but who may be from the same orsa.
.4 M
fand tb) quality of the, identifled structures, systems, Ung,and 2nd components, to an extent consistent n!tation. Where a test program is used to 4
s.
g.
g'ith their importence to safety. Activ!Ues verify the adequacy of a specific design $ss-ture in lleu of other verifying or checktus
.; 7" affecting quality shad be nemmplished pg
'S,f (M*C i
ander suitably controlled esoditions. Con.
processes, it shall include suitable qualifnca-d:
) used b troUed conditions include the use of appro-tions testing of a prototype unit under the f are, of Drtate maulpment; suitable environmental most f.dverse design conditions. Design can, y
erson has conditions for accomplishing the activity, trol measures shall be applied to items such k
as the following: reactor physics, stress,
<perate a such as adequate cleanness; and assurance thermal, hydraulle, and accident analyses; M*
frocessing that all prerequishes for the stven activity rused fir have been sausfie<L The program shall take compatibility of materials; accessibiuty for
,. 3,*,
inservice inspection, maintenance, and uscy AI le account the need for special controls, repair; and delineation of acceptance crite-
, J.S.'s*
by hold-es, test equ!pment, tools, and skills ria for inspections and tests.
e' p^D
. httlug13*
Altain the required quality, and the need e-b
, Mrtitcation of quality by inspection and Design changea, including field changes, I
sh&U be subject to design control measures q
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commensurate with those apphed to the ment requirements shah be available at the 1I
'e a
lk3 69 original design and be approved by the orga.
,.y nuclear powerplar,t or fuel reprooseslas '
Oj,,j #g nisation that performed the cristnal design gp, plant site prior to installation or use of ve.
j utdess the appIlcant designates another re-s5 *
. material and equipment. This '8-~
sush -
sponsible organlaation.
g ak i
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evidenee shall be retained at the ausd -
"J 7[* I *l, sv. raocUntaatwT soccassrr smarraot powerplant or fuel reprae==sh g plant agtely 4
i A -
O Measures shaU be estabihhsd to assure ' le requirements, such as code 6
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8 M. ;.) h,'.
I that. applicable regulatory requirements, specifiendons, met by the purchased maiset. v
- ,.i ed design bases, and other requirements which al and equipment. The effectiveness of the
'es/ '!
fMl U}
are necessary to assure adequate quality are
'*1 suitably included or referenead to the docu< control of quality by contro:ters and sub. ' J ssr 'i d.
contractors shall be assessed by the massi j 4i ments for procurement of matarsal, equip.
{
cant or designee at intervals consistent thh '..
srt
^
f3 ment, and services, whether petisased by a.
'%l..
the importance, complexity, and quanuty tall -
Il the applicant or by its contractors or sut>
thf.
the product or services.
I l' contractors. To the extent necessary, pro.
)
curement documents shall require contrao.
VIII. InnsertrICATton Ano contact ce q
gast,
g
'{.
. tors or subcontractors to provide a quality.
asarsatAsA FAars, Asro consponsNTs j
,,, '. l
,4
.g assurance program consistent with the per*
sect '
tinent provisions of this appendis-Measures sh&B be staMished tw ' h 80 '
Identiftendon and control of anaterg
' ept.
'= Y Ou,;i,
- v. rwersDCTIows, PaocsDUmsa, aNS maAfrINos parts, and components, including perusty g!
i i U- -[
poo Activities affecting quality shara be pre-fabricated assembHes. These measures shst ' ! *
- 8 y*:,/-*t scribed by documented lastructions, proco-assure that identificadon of the item h ;
the-o
=>
dures, or drawings, of a type appsspriate to maintained by heat number, part nuathar -
I"' -
- d ' '
g],'h,9,
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the circumstances and shaB be acccen-serial number, or other appropriate maamt l
4 1,
- plished in accordance with theme instruc-either en the item or on records treesable le J
tions, procedures, or drawings Instructions, the itam, as required throughout fahrtes.
a g4, j
procedures, or drawings shallinclude appro- & lost erection, instaDadon, and use of the -
i
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p,j.
priate quantitative or qualitative aseeptance Item. These identification and control mess.
(7*y
%p,4 t.
9
, gi criteria for determining thathmportant ac-ures stC. be designed to prevent the use of ~ '-
4 tivttles have been sausfactorar accom* tacorrect or defective material, parta, and plished.
componesta.
.s M-
. fa by,,' f i VI. DoccuswT cowman, Ex. cowTaoL or ersc1AL PRocansas h'
~h Ej f
~
Measures shau be estahlinhad to controg Measures shaU be estaMished to assuse i
. ttes !
. ' ', I the issuance of documenta, such as instruc. that special proceses, including welding, med tmh Mons, procedures, and drawings, including best tresung, and nondestructin testing.
d.
i changes thereto, which prescribe mU acuvi-am controHed and acconnplished by gust y
- sary, 4.
-. 'l.'
des affecung quality, These measures shau fled peraGanel using qualifidd proesdures 4 b
I"'4, '
assure that documents, including chand,es, menordasse with 4oUcable codes, standach..
3 I
? f are reviewed for adequacy.end approved for specifications, em cria, and other special n.
,I release by authorised personn4 and are dis, quiresnents.
Met y# E'
}t the tributed to and used at the locaden where a*
andi.1
.n-the prescribed acurity is performed.
L amancrtow W
j.
Changes to documents shall be review 3d and approved by the sanne aromalaations A program for inspecuon of activities af. %j* 'l ha Qg, 5 t -
4*
e ad that performed the original review and ap-facting quality shall be estabilshed and es. d 88"a"s s, i s
A ;,],g{
proval unless the applicant designates an-ocuted by or for the organisauen perforup d 4 1t w
other responsible organisatio L '
ing the settvity to verify conformance with ",
" I' the documented instrucUens, proceduren (
& ([; s- (,,
vit cosrraos or FUsenAsso asarmartAL, g""
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scorrunwT Ano saavuus
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- p'* ' "h, Measures shall be estabilshed to assure ' activity being inspected. Examinations 1.
Mt viduals other tnan thoec who performed the j
- l'
. oY that purchased material, equipement, and measurements, or tests of material or prog. V by u I
serviesa. whether purchased diracuy or ucts proessmed shan be performed for each label-
,QI through contractors and subccatractora, work operation where necessary to assure -
smear a-conform to the procurement earnaments. quality. If inspection of prwaaad material P'ffC lef g"'
/. [~.E!t
' Thest measures shall include provtalons, as or products is, impossible or disadvanta-88'*f
.t fe:7'N'/yC7,'
9* d'! O7 i,
appropriate, for source evaluation and selee. geous, indirect control by moniti,rtna proe.
h 2
tion, objective evidence of quaDty furnished
- j*
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by the contractor or subcontractor. Inspec-ensing rnethods, equipment, and personnel fkatl e
- qe,,- d ",[",%' 81 1-1 e,
tion at the contractor or subcontractor shall be provided. Both inspection and proc.
passe oss monitoring shall be provided when coe, nece
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source, and examine.tlon of producta upon trol is inadequate without both. If manda.
of si Q$$,N.)3 ;.;
rtan and equ pment conform to the procum-wnneuing or inspecung by the appucann
'Mr5 delivery. Documentary evidence that mate-tery inspection hold points, which requi,,
than, ;
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a Chop er 1-Nuclear Regweetory Commission Port 50, App. B
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En:rgy
{le at th>
designated representative and beyond which components of the nuclear power plant or
'h' 'N e)j..g[., '
I
[rocIssing eork shall not proceed without the consent fuel reprocessing plant, such as by tagging g$.
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a-e af such of its designated represent.ative are re-valves and switches, to prevent inadvertent
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McIntary quired, the specific hold point.s shall be indl.
operation.
I 4
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cated in appropriate documents.
.a { h _4 l a '7.' ';..
xv. NoNCoMroRMINO liATERIALs. WAMs, Os s
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'dards, tr A test progTam shall be established to Measures shall be established to control 8
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assure that all testing requered to demon. materials, parts, or components which do
- (
e h V.1' D' strate that structures, systemas, and compo* not conform to requirements in order to G)cfthe 4T%-
nents will perform satisfatorGy in service is prevent their inadvertent use or installa.
i and sub.
f I P M.
M appil.
ldentilted and performed in accords.nce with Lion. These measures shall include, as ap.
h# k' p' 4 P Dnt with written test procedures whAch incorporate propriate, prucedures for 1&r'tif'estion, doe.
I D"i.r
.antity gf the requirements and acceptance limits con-umentation, segngation, disposition. and ik,j.
i%f8
- O. '
a m l
A' tained in applicable design documents. The notification to affected organizations. Non.
(%e V
test program shall include, as appropriate
- conforming items shall be revier ed and ac.
W V.A,l f I ' 5 or proof testa priot to ins:alladon, preopera-cepted, rejected, repaired or reworked in ac.
jp i 8.1tc ['[.,*
i i sju.,T
'.i arrs tional tests, and operational tests during nu.
cordance with documented procedures.
rt' t*
I clear power plaut or fuel repeacessing plant c s o 4 h
.f r the
@I
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, 'f.@T I
naterials, h_
operation, of structures, synerds, and com.
2r1. conazCTIVE ACrtoE
'~
ponents. Test procedures shall include pro.
9 l' / :)' p%* 3
'. 8 partially visions for assuring that all prerequisites for Measures shall be established to assure
{
u tres shell the given test have been met. that adequate that conditions adverse to quality, such as 4
i
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iteln is test instrumentation is wrmllable and used, failures,\\ f-malfunctions, deficiencies, devi.
r ntstnber.
and that the test is perforsned under suit.
atl6ns, defective materlat and equipment, i
o anans, able environmental condKlona. Test results and nonconformances are promptly identi.
f 'p
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7./f,.
I fr ceabl> to shall be documented and evaluated to fled and corrected. In the case of significant j4 I f;brica*
assure that test requirernents have been sat.
conditions adverse to quality, the measures
{p.,
f
,y rol mess.
is determined and corrective action taken to (i
T.O lufled.
shall assure that the cause of the condition 4 (f the h*
Ett.coNTaoL or usAseRDE AND TEST preclude repetition. T!'e identification of
,,.vj +
ae use gf srts, and setrrrusar the significant condition adverse to quality, f'
.*!e, Measures shall be established to assure me came,of the condition, and the correc.
p i
tive action taken shall be documented and stensurty and testing devices used in activi. reported to appropriate levels of manage.
- g..g.
l i
that tools, gages, instrumensta, and other
- ment, gq j
eenssure ties affecting quality are properly con, j
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j p11. emm AsWRANCE REconDs a,
j
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trolled, calibrated, and ndjusted at specified
,s s
- tasting, periods to malntain accuracy within neces.
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5y quall-
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stry linitts.
Bufficient records shall be maintained to
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furnish evidence of activities affecting qual.
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titt, aAxottsc, sTomass ants satrrtwo Ity. The records shall include at least the
- 9
>ecial re-Measures shall be establistaed to control following" Operating logs and the results of y
..rk
- n the handling, storage, shlagning, cleaning reviews, inspections, testa, audits, monitor.
g 0 !
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ano preservation of material and equipment Ing of work performance. and materials 3
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j In accordance with wart and inspection analyses. The records shall also include thles af, Instructions to prevent *=a9= or deteriors. closely.related data such as qualifications of l
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tion. When necessary far partleular prod. personnel, procedures, and equipment. In.
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e t and eX.
rfirm.
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acts, special protective environments, such spection and test reoords shall, as a mlnl.
M i
[ce with P,
48 inert gas atmosphere, gaucific moisture mum. identify the inspector or data record.
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A,1 etntent levels. and temperature levels, shall er, the type of observation, the results, the I ;h l
t t
- tres, b specified and provided acceptability, and the action taken in con.
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st-
- gygty, nection with any deficiencies noted. Records i
p y Indl,.
j Rtv. tasescTson Turt. asm oesasTINo STATUS sha)) be identillable and retrievable. Coc.
p h
j y g tions.
W hasures shall be estsMished to indicate, sistent with applicable regulatory require.
,p
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n'g i
or prod.
b the use of markings surh as stamps, tags, ments, the applicant shall establish require.
y..
- r gor each labels. routing cards, er einer sultable ments concerning record retention, such as
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4 assure heans, the status of inspecsaons and testa duration, location, and assigned responstbul.
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j naterial h
ormed upon individual items of the nu-ty.
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poMr plant or fuel reprocessing plant 4
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measures shall prwide for the identi.
fl nnel
. gon of items which have satisfactorily A comprehensive system of planned and
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No M. 'E '
d prpo.
3assed required inspectlens and tests, where periodic audits shall be carried out to vertfy O con.
to preclude inadvertent bypassing compliance with all aspects of the quality b
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such inspections and tests. Measures assurance program and to determine the ef.
t pd b
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Irequire also be established for indicating the lectiveneas of the program. The audtta shall
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- f. q fating status of struaures. systems, and be performed in accordance with the writ.
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ten procedures or' check lists by appropri. analysis report and submitted as t*rt cf N 4..
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stely trained personnel not having direct re-final safety analysis report.
M'h
- sponsibilities in the areas bctng audited.
The potential radiological hazards to t
' 7DY'k' ),
$f Aud!t results shall be documented and re.
public associated with the operation of g
viewed by management having responsibill. search and test reactors and fuel fadlitiesf I
" 3G!,ls5 h w*tsv.~a r & @. M (
ty in the area audne1 Pollowup action,in. censed under 10 CFR Parts 50 a.ad To g, }
' b.
f 9nM cluding reaudit of deficient areas. shall be volve considerations diff ertat thr.n those g M.'sfl;.h e taken where indicated.
sociated with nuclear power Opetoes. Conne.
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(35 FR 10499, June 27,1970 as amended at 4"f" 8 h
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'ggq5i power reactors and the degree to which
'i I830 Sept.17.1971; 40 FR 3210D'
'.'A,ge{.4[.[, y..d, L[d E
compliance with the requirements of this 4 q.
w
- "t'oa "ad **ct'an$ II. nl. xv. and v as no.
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APPENDICES C-D-(Reservea) osary will be determined on a case-byg y,
basis.8 9
4 Notwithsta.nding the above paragraphs, g
,e t
A
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?? *s.As
' t AyrzNDtx E-EuzaczNcv PLANNING AND & case of an operating license authorizing ;
only fuel loading and/or low power oper. '
y g
- 4. N M PREPAREDNESS FOft PRODUCTION AND ations up to 5% of rated power. no NRC or
~
I Uyn.xzATION Facrt.mts' PEMA review, findings, or determinations e
53 "
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h Table c/ Cbntents concerning the state of offsite emergency a
(*p preparedness or the adequacy of and the es.
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I. Introduction pability to implement State and local offatte N t
g, -
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II. The Preliminary Safety Analysis Report emergency plans, as defined in this Appen.
III.The Final Safety Analysis Report dix, are required prior to the issuance og g
t.
IV. Content of Emergency Plans such a license.
[
7 V. Implementing Procedures q
II.THE Partrurwaar EartTY AmaLTais 4
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. Each applicant for a construction permit The Preliminary Safety Analysts Report
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-Y'i is required by 5 50J4(a) to include in the a
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shall contain sufficient informailon to 1 4
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preliminary safety analysis report a discus, ensure the compatibility of proposed emer. T 4
M slon of preliminary plans for coping with b
- J 1%
emergencies. Each applicant for an operat. gency plans for both onsite areas and the 2
EPZs. with facility design features, site P.
ing license is required by i 50.34(b) to in.
layout, and site location with respect to clude in the finsJ safety analysis reporg t
'i 3a such considerations as access routes, sur.
i 9.e si plans for coping with emergencies.
rounding population distributlans, land use,
[MgM; '"h 4 d This appendix establishes minimurn te.
and local jurisdictional boundaries for the da
.pq quirements for emergency plans for use in s,.f.,
attalning an acceptable state of emergency
_ g y' fp., # 'f' preparedness. "These plans shall be de-
'EPZa for power reactors are discussed in '
W
'm Pmp b[ g h.hg lo' v 4 3
scribed generally in the preliminary safety NUREO-0396; EPA 520/1-78-018. " Planning
&.Q-}.f y %a s [pMln-k i,,
Basis for the Development of State and l%
V,. N i NRC staff has developed two regulatory Local Government Radiological Eanergency 4 'k+A*d; M J [f guides: 2.6, "Emersency Planning for Re.
Response Plans in Support of IJaht Water 6a
- *. 4 A
-MMr-search Reactors," and 3.42. " Emergency Nuclear Power Plants." Decet:ber 1978. The
{',, 's%. d"4'g **h.,,.'ih*% ' !f"i a "o Planning in Puel Cycle Pacilities and Plants size of the EPZs for a nuclear power plant
+
I4 *i '
Licensed Under 10 CFP Parts"50 and 'J0;"
shall be determined in reladen to loral gi.g-
- fA(.
and a joint NRC/PEMA report NUREG-emergency response needs and capabilities i
, M
,s 0654; FEMA-REP-1. " Criteria for Prepara. as they are affected by such conssitDns as 4.
g
'G.,,d7,*y. -
gM tion and Evaluation of Radiological Emer. demography, topography, land characteris.
.3 i
-'a h
i, gency Responce Plans and Prt paredness in tics, access routes, and jurisdiceh==1 bound-p, j
. A R.[,, -
Support of Nuclear Power Plants for Inter-artes. The size of the EPZa also may be de-U'sD M'4 [N",l im Use and Comment." January 1980, to termined on a caseby. case basis for gas-M provide guidance h* developing plans for cooled nuclear reactors and for reactors J%*
WQ,t*
ccping with emergencies. Copies of these with an authorised power levelless than 260
~.
5,,,
U % s.y#
documents are availab'a at the Commis-MW thermal. Generally, the plumne expo-A' sion's Public Document Room, 1717 H sure pathway EPZ for nuclear power plants 1
b, e,4 i);,. -
- Street, NW,,
Washington, D.C.
20555, with an authorized power level grester than 8"
Copies of these documents may be pur.
250 MW thermal shall consist of an area
. y'y '
chased from the Government Printing about 10 miles (16 km) in radius and the in.
i.ap sf N '
l'.,.
M X ')
Office. Information on current prices rnay gestion pathway EPZ shall consist of an h. y(%y'?/
be obtained by wTiting the U.S. Nuclear area about SC miles (80 km) in radius.
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p
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- t Regulatory Comrcission, Washington, D.C.
- ' Regulatory Guide 2.6 will be used as
/ i G p[%[,,[.%y, '
20555, Attention: Publications Sales Man-guidance for the acceptability of research and tut reactor emergency [ esp 1mme plans.
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VNP I
M S J.A CHAPTER 17 m
QUALITY ASSURANCE i
17.0 INTRODUCTION
This chapter describes the quality assurance program (QAP) 10 d
'. developed by. the applicant, - GeorgiaL Power' Company, to provide assurance that the design, construction, preoperational testing, and operation of the Alvin.W. Vogtle-Nuclear Plant (VNP) conforms with applicable regulatory requirements, and l11 with the design bases specified in the license application.
This program represents a. management-control plan for the conduct of work by the major participating' organizations', which are the Georgia Power Company. (GPC), Southern Services,.Inc.
(SSI), Bechtel Power _ Corporation (BPC),. and Westinghouse q
. Electric Corporation ()D.
The quality assurance programs for-SSI,;BPC, and H.are deMcibed in separate appendices to this chapter.
The VNP quality. assurance program described in 'section 17.1 shall be -in force throughout design, construction, and preoperational testing of the plant, and: shall be applicable to j
those structures, systems, and components identified as-safety.
10 related and listed.. in section.17. 3.
The VNP quality assurance j
program f or plant operation will be described in section 17.2 and will be issued-in the Final Safety Analysis Report (FSAR).
1 The quality assurance program applies to the' activities j
affecting the quality of safety-related items including J
designing, purchasing, fabricating, handling, shipping, q
storing, cleaning, erecting, installing, inspecting, and testing. - The VNP quality assurance program, as described herein, complies with Appendix B of 10 CFR 50, " Quality Assurance Criteria for Nuclear Power Plants and Fuel 3
Reprocessing Plants" (October 11, 1971), and complies with AEC l11 Regulatory Guide 1.28, " Quality Assurance Program Requirements (Design and Construction)," and ANSI N45.2-1971, " Quality I
Assurance Pro'Jram Requirements for Nuclear Power Plants."
1 The. general duties and responsibilities of the primary j
organizations participating in the design, construction, and 10 I
preoperational testing of the VNP are:
A.
Georgia Power Company - Applicant and plant owner, j
construction manager, and operator of the VNP.
B.
Southern Services, Inc. - Administers for GPC, the contract with BPC for architect-engineering services,
);
17.1-1 11/26/73 Amendment 11 4
I
~
wa
l VNP and administers the supplier shop inspection program.
(See appendix 17C.)
C.
Bechtel Power Corporation - Provides architect-engineering services and the major portion of supplier shop inspection services under contract to SSI.
(See appendix 17A.)
D.
Westinghouse Electric Corporation - Supplier of the nuclear steam supply system (NSSS).
(See appendix 17B.)
A more detailed listing of the division of responsibility is contained in section 17.3.
DEFINITIONS Definitions used in this section are in accordance with ANSI N45.2.10-1973, " Quality Assurance Terms and Definitions."
The following additional terms and definitions also apply:
A.
Monitor:
To watch over, observe, or examine a work operation.
Results of the observations and 10 examination may be recorded; however, sign-off
'O responsibility is not included.
B.
Quality Assurance Lis+- fo-M.EM.:
A tabulhtion of those items in the VNP which are saf ety-related.
(See definition below.)
This tabulation is included in section 17.3.
C.
Review:
To examine any form of documentation for the purpose of establishing acceptability to the requirements of the function represented. by the reviewer.
Reviews may range from a thorough investigation to a spot check.
Reviews are not generally hold points, but signoff is required 14 on the documents or records traceable to the documents.
l D.
Safety-Related Item:
Those items that contribute to l-the prevention or mitigation of the consequences of l
10 postulated accidents which could cause undue risk to the health and safety of the general public; 141 generally, those items required to effect a safe shutdown, and maintain the integrity of the nuclear 10 process and containment barrier.
E.
Surveillance:
A broad term pertaining to and including both monitoring and witnessing.
1/14/74 Amendment 14 17.1-2 L-_
I
.(
a VNP
)
17.1: OUALITY - ASSURANCE DURING DESIGN AND CONSTRUCTION 17.1.1-ORGANIZATION 1
The' organization chart for the VNP. Project' (figure 17.1-1) j
- depicts. how' the ma jor, involved organizations interrelate with 1
f the EGPC f or the Vogtle Project. - It also indicates the lines of j
authori.ty. of' these organizations and the communication and j
functional lines among the organizations.
Organization charts "specifically, for the GPC Con 2truction and Preoperational-10 Testing-Programs are shown in figures.17.1-2 and 17.1-3.
17.1.1.1-Georcia Power Company
-GPC, as-the applicant, is' responsible for the implementation of.
l
.L~
the Quality Assurance' Program for the VNP.. The GPC Quality Assurance Engineer develops the.GPC' VNP Quality. Assurance.
3 Program. - The.GPC designated Executive Vice-President has I
specific responsibility for the Quality Assurance Program for j
the fVNP, and is the final authority on decisions affecting the i
Program.. Policy approval of the GPC Quality Assurance Manual l11 l
is. noted by the signature of the *GPC Executive Vice-President on the authority page.
4
\\
17.1.1.2-Ouality Assurance committee l
1
. A. Quality Assurance Committee (QAC) has been organized i
utilizing management of GPC and SSI, and acts as the advisory group to the designated GPC Executive.Vice-President.
The 10 primary purposes'of this committee are' to gauge the ef festiveness of the VNP Quality Assurance Program, an( to l
recommend corrective measures' to the GPC Exectitive Vice*
i President where necessary.
The Committee is composed of the I
following GPC and SSI executives:
P'-
A.
Executive Vice-President (designated) - GPC
- Chairman l
B.
Chief Engineer - GPC will address electrical matters in the QAC 11 l
l C.
Chief Civil / Mechanical Engineer - GPC l
10 q
l D.
Quality Ass'urance Engineer - GPC I
l 4
l 3
17.1-3 11/26/73 Amendment 11
[
1 I...
)
[
- VNP 4
. 1 E.
Senior'Vice-President.- Engineering - SSI
?... Vice-President - Nuclear - SSI '
~
The specific duties.and,re' possibilities of the QAC are:
s
^
A.
Meet four' times a year or on call of any member.
10 (B.
Be' informed of VNP quality assurance activities through:their respective organizational channels, and
.through various correspondence from the GPC Quality
. 1 Assurance Engineer such as:
AEC Directorate of-l Regulatory Operations - (DRO) Inspection Reports; GPC
- j reports of 'AEC DRO inspections; GPC construction site audit reports perfor:ned by 'the Quality Assurance Engineer; GPC and SSI Design Audit reports,'and
' {
reports of special problems.
. j l
- C.
Review
- and concur with the QA audit reports of
)
major contractors; SSI, Bechtel, W, and major construction contractors.
D.
Suggest agen'da items fo'r each meeting based on
- p 9
findings from B,. and C above.
]
E.
Review
- and concur with required corrective action.
F.
Assure that all open items are corrected in a timely effective manner.
1 G.
Evaluate
- the performance of the,VNP Quality 1
Assurance Program.
1; H.
Record the proceedings of each meeting.
'10 I.
Maintain open-items list for accountability of unresolved business.
4 J.
Make recommendations for Quality Assurance Program l
improvement to the Chairman.
l
- Review, as applied to the QAC, does not require a signature from'each member.
Review, evaluation and concurrence functions 14 are evidenced by QAC member input to meeting agendas and by the meeting minutes which indicate member concurrence of reports and corrective actions.
ee 0
Af 1/14/74 Amendment 14 17.1-4
e ad VNP 17.1.1.3 ' Georgia' Power' Company Quality Assurance Engineer
(:
RAE) Office L
LThe GPCf 0AE, L manager. of this office, reports directly to the L
designated Executive:Vice-President of GPC who has-authorized him1 to manage the Quality. Assurance, Program and ensure its implementation -in accordance with policies approved by the Executive Vice-President,'and to. advise of the program's.
~
effectiveness.- The QAE has been given authority by the LExecutive.Vice-President-to-stop, in a timely manner,
. unsatisfactory work on the VNP ' site which is 'not being performed in accordance.with the provisions of the Quality Assurance. Program.
The job performance evaluation of the QAE is approved by _ the designated GPC Executive -Vice-President.
-Administrative support is'provided by the GPC Chief Engineer.
e 10 The QAE has a' present general' office staff consisting of five technical people' participating in.the administration of the Quality Assurance Programs for the Hatch and Vogtle Nuclear Plants..
- specific duties and responsibilities of the GPC QAE A.
Manages the GPC quality, assurance staff.
B..
Develops the GPC Quality Assurance Program to conform I
~*
to approved' policies.
C.
Maintains, controls, and approves the GPC VNP Quality Assurance Manual and changes thereto.
D.
Audits procurement documents for requirements for Quality Assurance Manuals, quality verification, and documentation.
E.
Reviews and concurs with Quality Assurance Programs of major contractors including changes thereto prior the start of work governed by such programs.
~
VI F.
Approves construction site contractor Quality
+
Assuranos Manuals and Quality Assurance Programs including changes thereto prior to the start of work governed by such programs.
G.
Audits or verifies accomplishment of delegated audits
-j' of the QA Programs of GPC, SSI, B, y, and suppliers of materials, equipment, or services to ensure
~*
compliance to approved QA Programs and procedures.
14 H.
Conducts a monthly audit of the plant site to ensure the execution of Quality Assurance Programs of the GPC and site contractors for construction and preoperational testing >
g[2>
17.1-5 2/4/74 Amendment 15
'l
']
1 VNP 1
I.
' Processes ~ correspondence from AEC' Directorate of i
Regulatory Operations.
)
J.
Informs management of quality assurance activities 1
through distribution of audit reports and other correspondence.
1 K.
. Keeps the designated Executive Vice-President' q
informed verbally on routine matters, but reports 14 significant items.imm'ediately, both verbally and in writing..In addition, major audit reports by the QAE are forwarded to the Executive Vice-President j
including summaries of audits by major contractors.
.l L.
Reports to AEC those significant deficiencies defined.
i in 10 CFR 50.55 (e),.after consideration and approval
- 1 of the GPC-designated Executive Vice-President.
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17.1-Sa 1/14/74 Amendment 14 l
l j
I VNP
\\
l 8
Qualifications for the GPC QAE personnel are:
A.
Quality Assurance Engineer - An engineering graduate with five years' of engineering or field construction j
experience.
B.
Engineer - Quality Assurance (General Office )
An engineering or science graduate with either two years' of practical experience in quality assurance work or related experience in engineering or construction.
C.
Engineering Assistants (General Office) - A two-year associate degree in one of the engineering or science 1
disciplines or two years' of quality control experience.
~
17.1.1.4 Ouality Assurance Field Representatives (OAFR)
Located at the plant site, and reporting to the QAE, the QAFR Group supervised by the Senior QAFR, provides an independent review and evaluation of the implementation of the Quality Control Program at the construction site from the commencement O
of construction through the preoperational testing of the facility.
The Senior QAFR has authority from the QAE to stop, in a timely manner, unsatisfactory work which is not in compliance with specifications.
The Senior QAFR staff will be assigned work in the civil, mechanical, and electrical engineering disciplines.
I specific duties and responsibilities of the QAFR are:
A.
Prepares annual schedule of audits to be performed on construction site organizations and activities (GPC and contractors).
B.
Performs planned and periodic audits of construction site organizations and activities (GPC and contractors).
11l C.
Provides QAE with weekly written activity reports.
D.
Maintains open-items list from AEC inspections and QAFR audits, and follows up until resolved and closed 10 out.
E.
Acts as construction site contact for AEC DRO personnel.
m-
4 VNP q
N.
F.
Prepares reports of all audits and other pertinent activities and provides them to QAE.
G.
Monitors GPC daily inspection reports.
Qualifications for the GPC QFAR personnel are:
i i
A.
Senior Quality Assurance Field Representative (site) 1
- An engineering or science graduate with three years' of related experience or with no degree and eight years' of related experience.
'10 B.
Quality Assurance Field Representative (site) - An i
engineering graduate or with no degree and five l
years' of related experience.
)
i C.
Engineering Assistants (field) - A two-year associats l
degree in a major discipline or a high school graduate with three years' of related quality assurance / quality control work or construction i
experience.
{
17.1.1.5 Vice-President for Enaineerino and construction l11 The vice-President for Engineering and Construction, reporting to the designated GPC Executive Vice-President, is charged with 9
the responsibility for ensuring that the VNP is designed and constructed so as to comply with the design bases specified in the license application.
Reporting to him are the Assistant 1u j
Vice-President and Manager of Engineering, the Assistant Vice-President and Manager of Construction, and the VNP Project Manager.
17.1.1.6 Vootle Proiect Manager l11 The Vogtle Project Manager reports to the GPC Vice-President of k.
Engineering and Construction, and is responsible for coordinating design and construction phases of the work within GPC.
In this capacity, the Project Manager ensures that GPC groups responsible for work on the VNP perform the required work in a timely manner.
The Project Manager is the interface 10 for GPC with BPC, SSI and W in the design and construction of the VNP and, as such, ensures that action or response requested s
by these participants is made by the proper groups within GPC.
The Project Manager keeps the Vice-President of Engineering and construction informed of project status by providing status reports which indicate problem areas, and makes suggestions as necessary.
17.1-7 11/26/73 Amendment 11 i
j
_______________D
+.
VNP 11 l 17.1.1.7 Engineering The GPC Engineering Department has responsibility for the review and approval of the prospective Bidders List, which consists of bidders whose experience or qualifications have,
been ' evaluated according to procedures described in subsection 17.1.7.-
10 The GPC Engineering Department also has responsibility for the review and approval 'of the evaluation. of. bid proposals and purchase recommendations from BPC.
This department is. headed by.the Assistant Vice-President and Manager of Engih9.ering.
Reporting.to this' position is the Chief Engineer, who manages the offices. of the Chief Civil / Mechanical Engineer. and the Chief Electrical Engineer.
11l.17.1.1. 8 Construction The GPC Construction' Department has responsibility for the
' 10, Construction Management for the VNP, and will not be performing physical construction activities.
This work will be assigned to individual contractors.
As th& Construction Manager, the jgl GPC Construction Departmont is responsible for coordinating O
Construction contractors, and for developing and implementing a field Quality. Control Program to control and ensure quality compliance by field construction activities.
This program, 10 organized and implemented by the Field Construction Group, is under the direction of -the GPC Project Superintendent.
The GPC Project Superintendent,. reporting to the Manager of Construction through the Superintendent of Generating Plant Construction, is responsible,for coordination of the work of the various site contractors and for the implementation' of the -
GPC field Quality Control Program.
Each site contractor's Project Superintendent 'is responsible for cost and schedule in his area of the project.
To ensure that the responsibilities.
14 for. cost and schedule remain with the contractor, every affort is made by the GPC Purchasing Dept. to award contracts on a lump sum or unit price basis.
The GPC Project Superintendent shall be responsible for conducting construction site activities -in accordance with the il, GPC QAM and the GPC VNP Field Construction Manual.
10lI implementing procedures and instructions, which are approved by The Field Construction Group is responsible for developing and l
11l the Project Superintendent and the QAE, to ensure that field v
1/14/74 Amendment 14 17.1-8
WP
' construction, erection,.and. installation conform with approved specifications, drawings, codes, and other requirements.
This group.will develop the forms, checklists, and other quality control documents necessary to control activities, and to demonstrate compliance.with specified requirements.
The Field 10' Construction Group is composed of an Engineering Supervisor for s
each of the civil, mechanical, and electrical disciplines.
The Engineering Supervisors have specific. responsibility for the development and. implementation of quality control procedures, and for ass'igning and supervising inspection activities related to their respective disciplines.
These quality control l14 functions are accomplished by two separate sections under each
. Engineering Supervisor, an Engineering Section and an 10 Inspection Section.
The Engineering Section assures that the latest approved
~
drawings, specifications, and procedures are available and being used for construction.
They check the various design documents to assure compatibility with the WP quality programs) program (including contractor quality assuranceand applicable industry co assurance Engineering Section implements the quality control procedures which cover document change control (including design change '
e notices and change notice requests).
They participate in corrective action procedures on deviations reported by the Inspection Section or other quality control personnel such as those employed by site contractors.
They also perform field ja surveillance of work in progress to assure that established procedures are producing quality work.
The Inspection Section performs the inspection activities i
required by the WP quality assurance program in accordance with established quality control procedures.
This it.cludes inspection of the actual work being performed by contractor craftsmen.
It also includes but is not limited _to a:tivities being performed by contractor quality control personael and the saaterial receipt, storage, and installation inspection of materials and equipment.
Inspectors document their findings
~
through the use of written reports in accordance with i
established procedures.
These reports are submitted by the inspector directly to. the Documents Control Supervisor, with copies to the Senior QAPR 'and to appropriate persons in the Engineering Section who must take action on any discrepant items noted.
All inspectors have individual immediate stop work authority which they may exercise any time they feel that quality is not being maintained.
The Office Supervisor and the warehouse personnel assigned to him are functionally responsible for quality control activities 10 related to the receipt and storage of materials and equipment.
17.1-9 1/14/74 Amendment 14 i
VNP k
They ~ rely on: the Engineering Supervisors and their cognizant engine 3rs for checking and certifying the technical and quality compliance of material and equipment with procurement requirements.
.c The Documentation Control Supervisor is responsible for the control and distribution of approved drawings, specifications, and construction. quality control procedures.
In addition, this of fice collects and verifies availability of paper, and selectively reviews, in. detail,. the quality assurance documentation required by documentation checklists.
10 Specific. duties ~of the Documentation Control Supervisor' include:
A.
Controls incoming quality assurance documentation at.
the plant site.
B.
Expedites delivery of documentation.
C.
Certifies that required documentation is complete and on file at the plant site.
17.1.1.9 Production 11
.i
. The GPC Production Department is responsible for coordinating the activities associated with construction assurance ~ testing, development and approval of procedures for preoperational tests,. directing and conducting these tests and system flushes, 10 and documentation of results.
These functions for all saf ety-related systems will be performed by following written.
procedures contained in the Production. Department Plant Procedures Manual and the Preoperational Test Procedures.
s l
I N
y l14,y 17.1-9a 1/t4/74 Amendment 14
l
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VNP-l i
- Tho Plant Superintendent is responsible to the Manager.of l
' Production, who ' reports. to the' Assistant Vice-President for LProduction, for conducting the construction assurance and "preoperational. test programs in a manner to reach the desired
. objective of proving that the plant meets the design'
'l z
requirements and is, ready.to. provide power to the system 'in a '
s safe and reliable. manner.
- Thel Documentation' supervisor is. responsible to the VNP P1' ant superintendent for reviewing and maintaining quality control
' documentation generated during testing...He isLassisted in this responsibility by.a Material Controls Assistant.
The Laboratory supervisor has the responsibility for preparing the. administrative procedures: involved with radiation l protection.
He is also responsible for-the maintenance of the 1 10 system. water quality.
y
- The Maintenance-Supervisor has the responsibility for supervision of the mechanical and. electrical construction
" assurance testing, and maintenance after the system has been accepted.
The' operations Supervisor is responsible for the operation of on equipment of the plant. during construction assurance and preoperational testing, with technical direction from contractor operations personnel as applicable.
j The Technica1' supervisor is responsible for coordination of the l
preoperational test program.
He assures = that construction -
r assurance testing documentation packages are complete, adequate assignments are made to conduct tests,. and that preoperational test results are adequately documented.
11 [ 17.1.1.10 ouality Assurance Interfaces for GPC The' fo11owing is a summary 'of the general interfacing
. rest insibilities between GPC and BPC, SSI, and E.
For specific l
responsibilities, see section 17. 3.
I A.
Design (with BPC) :
10 1.
From issue of design documents through k
construction and preoperational testing using 1
?
these do~cuments.
i L
I l
2.
From preparation of Design Change Notices to
]
~
issue of notices by field to BPC.
n.-
1 11/26/73 Amendment 11 17.1-10 u_-_
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VNP
- b. ' '
t sp K
3.
From preparation of as-built' documents'in field.
to issue to BPC by field.
4.
. From rece'ipt 'of revised
- design documents from BPC-(resulting from 2 and 3 'above) through use of '
- these revisions 'in construction and i
preoperational testing.
j B.
. Procurement (with BPC) :
1.
From receipt' of suggested bid list from BPC to
' approval.by:GPC Engineering.
2.
From. receipt of recommendation.to purchase from BPC to. approval - by GPC ' Engineering..
3.,.From receipt of requisition by GPC to issue of purchase order by GPC Purchasing.
-1 C.
-Inspection,(with ssI) : -
1.
From release of equipment for shipment through 10 constructive. and preoperational testing.
~p D.
Inspection (other than SSI):
1.
Fran' procurement of certain items by the field until release for shipment and through construction and' preoperational testing.
E.
Construction (with GPC Production):
1.
From start of construction through construction assurance testing and acceptance by GPC Production.
2.
From return of incomplete or incorrect items,
. (;
systems, etc., from Production to acceptance by GPC Production.
i F.
Preoperational Testing (GPC Production responsibility) :
l,-
1.
From construction assurance testing through preoperational testing.
1 17.1-11 11/26/73 Amendment 11l11 i
f3h*"
j
=
.,..n...<,..
VNP i
.1
- 17.1.2 QUALITY ASSURANCE PROGRAM
-10 iGeorgia Power Company and other companies participating in the design, construction, and preeperational. testing of.the Vogtle Nuclear Plant lare committed to a quality assurance program which' will' result in a safe and reliable plant throughout its 11.( design life and which will comply with the Quality Assurance Criteria'of 10 CFR 50,' Appendix B..
l ATQ-List.has been prepared to identify items to which the quality, assurance program applies..This Q-List, appearing in i
secti'on 17.3,. may be revised during the design and construction of VNP to meet the intent of regulatory requirements.
The quality assurance program is. supported by written policies and-procedures governing quality-related functions and
,'~
activities.
GPC has published a ' Quality Assurance Manua11 which contains or references the general procedures and ' instructions
, governing the activities of the.GPC and the interfacing procedures with participants in the design, construction, and preoperational testing of the VNP.
In addition, each participantfis required to develgp and/or implement a quality assurance - program commensurate with the activity to be performed.
'O For equipment, material, and/or services procured by GPC from BPC-prepared specifications the suppliers' quality assurance-
'10 program must be reviewed and accepted by BPC.. For safety-related materials and/or services procured for field construction by GPC from BPC-prepared specifications and recommendations, the suppliers' quality assurance program must be reviewed.and accepted by the GPC QAE prior to. start of manufacture or erection..
(see subsection 17.1.4).c ame
- accepted quality assurance programs off site contractors become j
an -integral part of the GPC quality' assurance program by
' reference in the GPC VNP Quality Assurance Manual.
j j
The GPC VNP Quality Assurance Manual sets forth the authority,
)
organizational arrangement, and policies which govern the VNP
)
quality assurance program.
This manual contains or references i
general procedures for design, construction, and preoperational
)
testing applicable to VNP.
Detail procedures are referenced,
~
where appropriate, in the VNP Quality Assurance Manual, and are prepared, approved, and controlled by the organization
-responsible for implementing them.
The GPC VNP Quality
' Assurance Manual references applicable portions of the following documents:
A.
GPC Quality Assurance Office Procedures L
11/26/73 Amendment 11 17.1-12 y
i 1:
4 c
VNP i.
9 B..
GPC. Engineering Procedures (Civil, Mechanical, an
. Electrical)
C.-
GPC VNP Field Construction-Manual = (General, Field
. Civil,1 Field Mechanical, and Field Electrical)-
10 t
-, SSI VNP Quality Assurance and SSI VNP Procedures' D.
Manuals
- E.
Bechtel-VNP, Project Reference Manual' 1
F.-
GPC' VNP-Startup Manual' (Preoperational Testing)
A tabulation of GPC procedures, presented in tables 17.1-1 and 13 17.1-2,Sprovidesfa cross-reference to the.10 CFR 50, Appendix B, criteria which each procedure is. intended to satis fy.-
These procedures are either contained or referenced-10'
'in the GPC VNPl Quality Assurance, Manual. ' The GPC Quality Assurance Office' Procedures and the GPC VNP. Quality Assurance Manual have been. released for use.
The~ GPC VNP Construction Procedures Manual is in the process of preparation, review, and refinement..'Mest of the. general procedures.'and a portion'of the discipline procedures in thit Manual.will be available for the scheduled: start of construction on July 1,1974'.
These e
h will constitute, for the most part, those procedures which will 33
~
be needed~at the commencement of construction activities and in establishing,the site OC program.
Additional' procedures will
. be ' prepared and; released as the need arises, however, no work will be allowedito begin unless it is governed by.a properly coordinated, approved procedure.
GPC -QA procedures-are-designed tb ' comply with 'thetfollowing Regulatory Guides ind. ANSI. Standards.
Regulatory Guides 1.28
" Quality Assurance Program Requirements (Design and Construction) (formerly Safety Guide 28)"
(6/7/72).
$g 1.30
" Quality Assurance Requirement for the
~~
Installation, Inspection, and Testing of Instrumentation and Electric Equipment (Formerly Safety Guide 30)" (8/11/72) x 1 '.'3 3
" Quality Assurance Program Requirements
~
(Operation) (Formerly Safety Guide 33)"
(11/3/72) s.-
17.1-13 1/14/74 Amendment 14
^
VNP
.hL 37M -
" Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclar Power Plants" (3/16/73)
-, 1.' 3 8,
" Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for Water-Cooled Nuclear Power Plants" (3/16/73)
~ - 1.39
" Housekeeping Requirements for Water-Cooled Nuclear Power Plants" (3/16/73)
,1.58
" Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel" (8/73)
ANSI Standards ANSI N45.2.9-1973 " Requirements for Collection, Storage, and Maintenance of Quality Asyurance Records for Nuclear Power Plants" (Draft 11, R,ev. 0 - March 1973) 14 l
. ANSI N45.2.ll " Quality Assurance Requirements for the
'O Design of Nuclear Power Plants" (Draft 2, Rev. 2 - May 1973)
ANSI N45.2.12 " Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants' (Draft 3, Rev. 0 - May 2, 1973)
AEC Extracts from ANSI N45.2.13 "Supp1=mantary Quality Assurance Requirements for Cvntrol of Procurement of Equipmenc Materials, and Services for Nuclear Power Plants" (Draft dated May 31, 1973)
While the above Regulatory Guider 3 and ANSI Standards will be used as guides and references for the development of GPC procedures, there are cases where full compliance will not be possible.. In the case of Regulatory Guide 1.58 (ANSI N45.2.6),
it is felt that there are not enough experienced personnel available to meet the requirements.
This shortage of experienced people is due primarily to the relatively short history of our particular industry.
The GPC-Construction Department presently.has been under development and in partial operation a training program for field engineers and inspectors.
This program has been developed based on our experience in the construction of Edwin I. Hatch Nuclear Plant and the contents of the regulatory guide.
It is felt that this v
1/14/74 Amendment 14 17.1-13a g9
VNP effort is a ret.sonable approach to qualifying personnel and is in compliance with the intent of the guide.
14 In other areas where complete compliance with the guides or standards is impossible, a similar approach will be used,
\\
I 17.1.2.1 Training and Indoctrination Training of personnel directly involved in quality assurance i
activities is accomplished primarily by indoctrinate on on the VNP Quality Assurance Program in specific areas relating to 11 their assigned duties.
The hiring qualifications for quality assurance personnel are set forth in paragraphs 17.1.1.3 and 17.1.1.4.
These personnel are given refresher training in
(
applicable technical areas such as nondestructive examination, cadwelding, and welding.
Quality assurance field personnel for VNP are presently obtaining on-the-job and classroom training
~
at the GPC Hatch Nuclear Plant.
11 3 In addition, a training program for GPC site QC personnel has been in the development stage for some time. This program will 11 ensure that personnel performing
- inspection are adequately trained in the performances of their assigned activities which
.'Q will be set forth in detail in the GPC VNP Field Construction
+.
i s
y e.
-- - - ~-_-_-___- -____ _ __ _ - _ - _ - - _ _ _ _ _ _ _ _ _
},
n..
L vNp Table 17.1-1 GPC VNP. QUALITY-ASSURANCE MANUAL' APPLYING THE-l' REQUIREMENTS OF 10 CPR 50, APPENDIX B
.I.
ORGANIZATION Section 2:.(Organization:and' Responsibility) -
Establishes the organizational arrangement within the.GPC for'the Vogtle Project, and the interfaces with SSI,.BPC,. and W.
II. -
QUALITY ASSURANCE PROGRAM Section 1 (Introduction) - Establishment of QAP.
Section 2 (Organization and Responsibility) -
Assignment. of QAP responsibilities within the GPC.
III.-
DESIGN CONTROL
'O - 10 Section - 3 (Engineering) - GPC's responsibilities in Design Control, and the interfaces with SSI, BPC, and W.
IV.
PROCUREMENT DOCUMENT CONTROL Sections 3'(Engineering).and 4 (Procurement and Vendor Inspection) - Sets.forth GPC's review of Procurement Documents and approval of the bid recommendation-.
V.
INSTRUCTIONS, PROCEDURES, AND DRAWINGS Contains or references the procedures which satisfy l
and implement 10 CFR 50, Appendix B.
V'.
DOCUMENT CONTROL Section 3 (Engineering) - Establishes requirements for the control of documents within the GPC General l
Office.
1'1l 11/26/73 Amendment 11 17.1-14 l%g&
u____.-____
)
i t
VNP i
l Table 17.1-1 (Continued):
i GPC.VNV QUALITY ASSURANCE MANUAL APPLYING THE REQUIREMENTS _ OF 10 - CFR ' 50, APPENDIX B Section 6 (Construction)
Sets forth the i
requirements and references the procedure' used by
.GPC site personnel in the control of documents.
Section 7_- (Construction Assurance and
-Preoperational Testing) - Contains requirements for the control of documents involved with construction i
assurance-testing and preoperational testing.
~
VII.
CONTROL OF PURCHASED MATERIAL, EQUIPMENT, LAND SERVICES.
Section 4 (Procurement and Vendor Inspection -
l Contains GPC's input and approval of Bidders List.
Section 6 (Construction) - Requires receiving inspection by site personnel of material, parts, and components
- 10 O
VIII.
IDENTIFICATION AND CONTROL OF MATERIAL, PARTS, AND I
COMPONENTS Section 6 (Construction) - Contains or references i
the procedures for.the identification and control of material, parts, and components at the l
construction site.
IX.
CONTROL OF SPECIAL PROCESSES l
l i-Section 6 (Construction) - Contains or references the procedures used by GPC site personnel to control the special processes performed by site
-contractors.
X.
INSPECTION Section 6 (Construction) - Contains or references L
the proceduras used by GPC site personnel in their inspections of equipment and cite contractors.
l 17.1-15 11/26/73 Amendment 11 l11 7
Y
A L.
'f VNP D!
x Table L17;1-1= (Continued)
GPC-VNP QUALITY ASSURANCE MANDAL APPLYING THE REQUIREMENTS OF 10 CFR 50, APPENDIX B _
1 Section 7_ (Construction Assurance and Preoperational, Testing)
Contains or references the procedures _ for inspection during construction P
assurance and preoperational testing.
z i
XI.
TEST CONTROL Section 6 (Construction) - Contains or references the procedures used by GPC site personnel ~ in the centrol of. tests performed by contractors.
Section 7 (Construction ~ Assurance and Preoperational Testing) '- Contains the means and measures taken for.the control of testina during construction assurange and preoperational testing.
l-V XII..
CONTROL OF MEASURING AND TEST 2QUIPMENT Section 6 (Construction) - Contains requirements for and references the procedure used for the control of measuring and test equipment.
Section 7 (Construction Assurance and Preoperational Testing) - Contains the requirements for and references the procedures used for the i
control of measuring' and test equipment.
- XIII.
HANDLING, STORAGE AND SHIPPING Section 6 (Construction) - Contains or references the procedures used in the storage of material and i
equipment at the construction site.
XIV.
INSPECTION, TEST, AND OPERATING STATUS Section 6 (Construction) - Contains or references the procedures used to maintain the inspection and e
operatina status of ' equipment and materials at the construction site.
ki n.-
11 [11/26/73 Amendment 11 17.1-16 y
o
4 VNP Table 17.1-1 (Continued)
-GPC' VNP 00ALITY ASSURANCE )RNUAL APPLYING THE REQUIREMENTS OF 10 CFR 50, APPENDIX B
'Section 7 (Construction Assurance and:
Preoperational Testing) - Contains.or references
~
the procedures used for 5nspection and operating status of structures, syitems, and components during construction assurance testing and preoperational testing.
XV. -
NONCONFORMING MATERIALS, PARTS, 'OR COMPONENTS Section 6 (Construction) - Contains or references the procedures used in the control and identification of nonconforming items.
'i Section 7 (Construction Assurance and Preoperational Testing) - Contains-or references the procedures used in the control and i
identification of nonconforming items during l
construction assurance and preoperational testing.
10 4
G.
H XVI.
CORRECTIVE ACTION 1
'Section 6 (Construction) - Contains the 4
requirements for corrective action on deficient
)
items or equipment.
j
(
XVII.
QUALITY ASSURANCE RECORDS 1
1 Section 6 (Construction) - Contains requirements I
- ~
for the generation of quality assurance records 4
during the construction of VNP, Also references procedures for the filing and storage. of site-generated and vendor-supplied quality assurance records Section 7 (Construction Assurance and Preoperational Testing) - Contains requirements for I
the generation of quality assurance records during l
)
the construction assurance, and preoperational l
testing of VNP.
I l
l 17.1-17 11/26/73 Amendment 11 l11 i
ZI)
]
1 1
VNP Table 17.1-1 (Continued)
GPC'VNP QUALITY ASSURANCE MANUAL APPLYING THE REQUIREMENTS OF.10 CFR.50, APPENDIX B 10 XVIII.
' AUDITS I
Section 3 (Engineering) - Defines the audit responsibilities of the QAE and the QAFR during the design, procurement, construction, construction assurance testing, and preoperational testing of VNP.
~
1 O.
i i
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i L
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11 l 11/26/73 Amendment 11 17.1-18 7f
r V...-
U.S. NUCLEAR REGULATORY COMMISSION R vialin 2 '
~
October 1976 REGQ.ATORY GUDE j
OFFICE OF STANDARDS DEVELOPMENT REQULATORY GUIDE 1.88 h&.2 MW%
COLLECTION. STORADE, AND MAINTENANCE OF NUCLEAR W
POWER PLANT QUALITY ASSURANCE RECORDS A. INTRODUCTION As a result of discussions with applicants for con.
Criterion XVil, " Quality Assurance Records," of struction permits and operating licenses following the i
Appendix B," Quality Assurance Criteria for Nuclear ssuance of this guide in August 1974, the NRC staff -
Power Plants and Fuel Reprocessing Plants," to 10 has recognized the existence of an acceptable alter.
CFR Part 50, " Licensing of Production and Utiliza.
native to the methods described in ANSI N45.2.9 tion Facilities," requires, in part, that consistent with 1974 for protecting quality assurance records from.
1 applicable regulatory requirements, the applicant es-the hazards of fire. In December 1975, the NRC staff tablish requirements concerning record retention, published Revision I to this guide. which identified such as duration, location. and assigned respon.
and incorporated this alternative. Commerys were in-
~
sibility. This guide describes a method acceptable to vited within 60 days of publication of Revision I for-j
{
the NRC staff for complying wit 4' the Commission's use in conjunction with early revision of the guide, q
t regulations with regard to collection, storage, and After consideration of all comments, no substan,tive maintenance of quality assurance records for all types changes have been made in the regulatory posiuon.
P of nuclear power plants. The Advisory Committee on Reactor Safeguards has beei consulted concerning It shodd be noted that NFPA No. 232 1970, this guide and has concurred in the regulatory *posi.
"Standarf, tot the Protection of Records," which was tion.
referenced m regulatory position C.2 of Revision 1,
- 8. Ol8CU8810N was reconfirmed by the National Fire Protection As-sociation at its 1975 fall meeting and is now Working Group N45 2.9cf the AmericanNational designated NFPA No. 232 1975. Ne substantive a
Standards Committec N45 Reactor I'lants and Their changes exist between these documents. Regulatory Maintenance, has prepared a standard that provides position C.2 has been revised to reference NFPA No.
~i general requirements and guidelines for the collec.
232 1975.
{
tion, storage, and maintenance of quality assurance i
records for nuclear power plants.This standard was C. REQULATORY POSITION approved by Subcommittee N45 2, Nuclear Quality Anurance Standards, of the American National The requirements and guidelines for collection, Standards Committee N45 and the fuD committee storage, and maintenance of nuclear power plant and its Secretariat. lt was subsequently approved and quality assurance records that are included in ANSI designated N45.2.91974' by the American National _
N45.2.91974 are acceptable to the NRC staff and Standards Institute on June 6.1974.
provide an adequate basis for complyms with the
- unes Indiente substandn chansa from preemus issue.
pertinent quality assurance requirements of Appen.
dix 8 to 10 CFR Part 50, subject to the following:
'ANSt N45.2.91974. *Requirernents for conection. Sto<nes an*
- 1. Subdivision 1.5 of ANSI N45,2.91974 states.
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"Other documents that are required to be included as y
Mechanical Ensineers, M3 Eut 47th Street. New York, New part of this standard are either identified at the point York toot 1.
of reference or described in Section 8 of this stan.
USNRC RECULATORY GVioE7 c...
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hrd." The specine applicability or acceptability of fire protection provisions' listed in Subdivision 5.6 of these listed documents has been or will be covered N45.2.9 1974. When NFPA No. 232 1975 is used, separately in other regulatory guides or in Commis-quality assurance records should be classified as '
sion regulations where appropriate.
NFPA Class I records (NFPA No. 232 1975,
- 2. Two methods for protection of quality as.
surance records from tbc hazards of Gre are described D. IMPLEMENTATION in Subdivision 5.6 of ANSI N45.2.91974. NFPA No.
2321975," Standard for the Protection of Records,"8 The purpose of this section is to provide guidance also contains provisions for records protection equip-to applicants and licensees regarding an implementa-ment and records handling techniques that provide tion schedule for utilizing this regulatory guide, protection from the hazards of fire. This standard, withm its scope of coverage, is considered by the
& cept N those cases in which the applicant NRC stsiT to provide an acceptable alternative to the proposes an acceptable alternative method for com-ply ng with the speelDed portichs of the Commis-
'NFPA No. 232 1975 is contained in Volume 10of the National sion's regulations, the methods described herein will l
Fire Codes published annually by the National Fire Protection be used in the evaluation of construction permit sub.
Association,470 Atlantic Avenue Boston. Massachusetts 02210.
mittals after issuance of this guidp.
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