ML19319D726
| ML19319D726 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, 05000303  |
| Issue date: | 08/10/1967 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML19319D724 | List: |
| References | |
| NUDOCS 8003240755 | |
| Download: ML19319D726 (34) | |
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Octo8er 3,i973 GUIDA:lCE FOR SUB ITTEL OF OUALITY ASSURAflCE PROGRA1 DESCRIPTIOf i
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OUALITY ASSURANCE GUIDAriCE FOR PSAR SUBf!ITTAL PURPOSE This document provides guidance relative to the information require-ments of Section 17 of the PSAR, Quality Assurance During Design and Con-struction. This guidance supplements the information presented under 17.1 of the Standard Format and Content of Safcty Analysis Reports for fluclear
. Power Plants, Revision 1, dated October 1972.
According to Regulation 50.34 " Contents of Application, Technical Information", the applicant is required to include in its PSAR a description of how the applicable requirements of Appendix B will be satisfied.
This document applies to the applicant and its principal contractors such as the architect-engineer, the nuclear steam system supplier, the con-structor, construction manager (if different frcm the constructor) and involves all quality' related activities during design, construction, purchase, fabrication, handling, shipment, storage, cleaning, erection, installation, inspection, and preoperational testing which affect safety related structures, systems, and componerts.
To fulfill the requirements of 50.34 and 10 CFR 50 Appendix B the infor-mation'and guidelines described herein, or acceptable alternatives, should be included in the PSAR to provide an adequate basis.for the findings required for the. issuance of a con.truction permit.
PSAR's which do not contain the information described in this document may require a longer review time and may be considerec' by the staff as incomplete.
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Organization 1.
The organization structure of individuals or groups performing QA related activities in engineering. design, procurement,
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source and construction inspection, testing, and auditing should be identified and described in the PSAR with a clear delineation of.their responsibility, authority, and relationship to corporate management.
2.
A clear delineation of those QA functions which are implemented within the applicant's QA organizations and those which are delegated to other organizations should be provided in the PSAR.
3.
The authority and independence of the individual responsible for i
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/7 managing the QA Program should be described in the PSAR. The V
individual's organizational location should be such that he:
(a) can direct and control the organization's QA/QC programi i
(b) can effectively assure the organization's c6nformance to quality requirements; (c) has corporate authority to perform designated-QA functions in the Engineering, Design, Procurement, Construction and Testing organizations performing quality affecting activities; and (d) is independent of influences and responsibilities i
for schedules and costs. An acceptable organizatio.1al structure would have this individual report to at least the same organizational level-as the highest line manager directly responsible for performing quality affecting activities,
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Those QA interfaces which demonstrate clear and effective lines of communication between the QA organizations of the applicant and the applicant's principal contractors should be id.'tified and described in the PSAR.
5.
The PSAR should describe those measures sinich assure:
verification of conformance to estaolished quality requirements a.
on safety related structures, systems, and components is 4
accomplished by those individuals or groups who do not have direct responsibility for performing the 5 ork being verified.
b.
designated QA individuals have the delegated responsibility and authority to stop unsatisfactory work or stop furthei processing g
of unsatisfactory material and that this authority is delineated in writing.
persons and organizations performing quality assurance functions c.
have sufficient authority and organizational freedom to:
t (1) identify quality problems (2) initiate, recommend, or provide solutions through designated channels.
(3) verify implementation of solutions.
j (4) control further processing, delivery or installation of a nonconforming item, until tE proper disposition of the deficiency or unsatisfactory condition has been approved.
6.
The qualification requirements for the position responsible for y
directing and managing the QA Program should' be described in the PSAR.
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-(3 C/ II.. Quality Assurance Program 1.
Those measures implemented by the applicant and principal con-tractors to assure the preparation of a QA Program which meets l'0 CFR 50 Appendix B and tiie intent and scope of this document should be described in the PSAR.
- 2. ~Those provisions which require management to regularly assess the scope, implementation and effectiveness of the QA Program to assure that they are meaningful and effectively complying with the corporate policy and with 10 CFR 50 Appendix B criteria should be described in the PSAR.
3.
Those positions or groups responsible for defining the QA Program
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content and changes thereto, and the management level responsible for the final review and approval of the QA Program should be-identified.
4.
Those provisions established for communicating to all responsible organizations and individuals that quality policies, manuals, and procedures are mandatory requirements which must be implemented and.
enforced should be described in the PSAR.
5.
To demonstrate the framework for the implementation of 10 CFR 50 Appendix B criteria, a listing of the QA Program procedures which describe tSe implementation of each of the is CFR Part 50 Appendix B criteria,.should be provided in the PSAR and identified to the applicable corresponding criterion.
In the event that certain required pro-
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- cedures are not established a schedule for their preparation should be provided-in'the PSAR.
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The safety related structures, systems, and components controlled by.the QA Program and the respective organization executing QA related functions on these items during the engineering, design, procurement inspection, and testing phases should be identified in the PSAR.
7.
The PSAR should describe those measures which assure:
the applicant will review and formally concur with its principal a.
contractor's QA Program and conduct, or delegate the responsibility to conduct audits of the program activities, b.
an adequate indoctrination and training program is established for those personnel performing quality related activities to pJ assure they are knowledgeable df the QA procedures and require-t
.ments and become proficient in iinplementing these proce'dures.
i The indoctrination and training program should include:
(1) personnel responsible for performing quality activities are instructed as to the purpose, scope, and implementation of i
the quality related manuals, instructions, and procedures.
(2) personnel performing quality related activities are trained and qualified in the principles and techniques of the activity being performed.
(3) appropriate training procedures are established.
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8.
Those quality related activities initiated prior to the submittal of
- the PSAR, such as design and procurement, should be identified, in 1
the PSAR. The QA Program which controls these activities and satisfies
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a requirements of 10 CFR Part 50 Appendix B and the Guidance on QA
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-Requirements During Design and Procurement (Grey Book)should also be i
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V 9.
Those provisions which control the transfer of QA responsibilities, duties, and records from the constructors and the nuclear steam system suppliers to the applicant during the preoperational testing phase up to fuel loading should be described in the PSAR. This description should include:
- a. ! the participation of both the applicant's corporate and operating plant QA personnel in the transfer.
b.
the mechanism of tagging and identifying systems, structures, and components which denotes the inspection and test status, c.
the types of procedures that should be established and invoked to assure the effective transfer, storage and control of records,
- 10. Those provisions which assure that quality related activities such as (s
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inspection and test will be done with appropriate equipment and under suitab'le environmental ' conditions should be described in the PS4R
- 11. Describe those provisions of the QA Program which assure that the applicable Regulatory Guide requirements are considered and that these requirements, or acceptable alternatives, are adequately implemented.
- 12. Within the PSAR the utility and principal contractors should commit to structuring the QA Program in accordance with the following AEC Regulatory Guides and ANSI Standards or describe acceptable alternatives.
a.
AEC Regulatory Guide 1.28 " Quality Assurance Program Requirements for Dssign and Construction".
- b. - AEC Regulatory Guide 1.30 " Quality Assurance Requirements for the Installation, Inspection ar2 Testing of Instrumentation and Electric Equipment".
- c. ' AEC Regulatory Guide 1.31 " Control of Stainless Steel Welding".
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d.
AEC Regulatory Guide 1.37 " Quality Assurance Requirements for Cleanino of Fluid Systems and Associated Components of Water-Cooled Nuclear
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- e. AEC Regulatory Guide 1.38 " Quality Assurance Requirements for Packaging, Shipping, Receiving, Storage, and Handling of Items for llater-Cooled fluclear. Power-Plants".
f.
ANSI N45.2-1971 " Quality Assurance Program Requirements for f!uclear Power Plants", Regulatory staff comments supplementary guidance, Section D of " Grey Book" (Gu'idance on Quality Assurance Require-ments During Design and Procurement Phase of ?!uclear Power Plants).
g.
ANSI N45.2.9 (Draft 11, Rev. 0 - January 17,1973) " Requirements for Collection, Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants", including Regulatory staff comments supplementary guidance, Section D of " Grey Book" (Guidance on Quality Assurance Requirements During Design and Procurement pQ Phase of Nuclear Power Plants).
h.
ANSI N45.2.ll.(Draft. 2,- Rev. 2 - May 1973) " Quality Assurance -
.e. :. 4 Requirements for Design of Nuclear Power Plants".
- i. ANSI N45.2.12 (Draft 3, Rev. 0 - May 2,1973) " Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants",
including Regulatory staff comments supplementary guidance, Section D of " Grey Book" (Guidance on Quality Assurance Require-ments During Design and Procurement Phase of Nuclear Power Plants).
J.
ANSI N45.2.13 (Draft May 31,1972) as modified by AEC in " Grey Book"; " Supplementary Quality Assurance Requirements for Control of Procurement of Equipment, Materials and Services for Nuclear Power Plants" including Regulatory staff comments supplementary guidance, Section D of " Grey Book" (Guidance on Quality Assurance
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,- v III. Desian Control 1.
The PSAR sho_ld describe those measures which assure:
a.
procedures are established to carry out design activities in a planned, controlled, and orderly nianner.
b.
the applicable regulatory requirements and design bases are correctly translated into specifications, drawings, written procedures and instructions.
c.
appropriate quality standards are specified and includea in the design documents and that deviations and changes from such standards are controlled, d.
suitable design controls are applied to items such as:
reactor physics, stress, thernial, hydraulic, radiction, n;d accident analysis; compatibility.of. materials; accessibility for. i.n-service,.
inspection, maintenance, repair; and specifying criteria for inspection-and test.
e.
interface controls, both external and internal, are procedurally described and controlled for all participating organizations.
f.
proper selection and accomplishment of design verification or checking method such as design reviews, alternate calculations, or qualification testing is performed. Where a test program is used to verify the adequacy of a design, a qualification test of a prototype unit under the most adverse design conditions will be used, g,
individuals or groups responsible for design verification or checking are other than those who performed the original design.
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design and specification changes, including field changes, are subject to the same design controls that were applicable to the original design.
1.
design documents and revisions thereto are d
-ibuted to responsible individuals in a timely manner and controlled to prevent inadvertent use of superseded material.
- j. errors and deficiencies which adversely affect safety related structures, systems and components in the design process are documented and that appropriate corrective action has been taken.
k.
design documents, design revieus, records, and changes thereto Q
are collected, stored, and maintained in a systematic and controlled manner.
1.
standard "off the shelf" commercial or previously approved materials, parts, and equipment (that are essential to the safety related functions of the structures, systems, and components) are selected and reviewed for suitability of application.
2.
The positions or groups responsible for design reviews and design verification activities and their authority and responsibilities should be identified and described in the PSAR.
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- IV. Procurement Document Control 1.
The PSAR~should describe those measures which assure:
- a.. procedures are established clearly delineating the sequence of actions to'be accomplished in the preparation, review, approval, and control of procurement documents.
b.
a review and concurrence of the adequacy of quality require-ments stated in procurement documents is performed by qualified personnel knowledgeable in the QA requirements. This review is to determine that all quality requirements are correctly stated, they 4
can be inspected and controlled, there are adequate acceptance and rejection ~ criterfa, and the procurement document -has been prepared in accordance with QA Program requirements.
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documented evidence of the review and approval of procurement c.
documents is provided and available for verification.
2 d.
procurement documents identify those 10 CFR Part 50 Appendix B requirements that must be complied with and described-in the supplier's - QA Program. This QA Program or portions thereof should be reviewed and concurred with by the buyer and qualified personnel knowledgeable in QA prior to implementation of activities affected by the manual.
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V procurement documents contain or reference applicable design e.
basis technical requirements including regulatory requirements, component and material identification, drawings, specifications, codes and industrial standards, including their revision status, tests and inspection requirements, and special process instructions, for such activities as fabrication, cleaning, erecting, packaging, handling, shipping, storing, and inspecting.
f.
procurement documents contain as applicable, requirements which identify the documentation to be prepared, maintained, submitted, and made available to the buying agent for review and/or approval, such as drawings, specifications, procedurcs, inspection and
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fabrication plans, inspection and tes. ecords, personnel and procedure qualifications, materials, chemical,'and physical test resul ts.
g.
procurement documents contain the requirements for the retention, control, and maintenance of records.
I h.
procurement documents contain the procuring agency's right of access to vendor's facilities and records for source inspection and audit.
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changes and/or revisions to procurement documents are subject to at least the same review and approval requirements as the original
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document.
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- j. ' purchase documents for spare or_ replacement parts of safety related structures, systems, and components are reviewed for adequacy of quality requirements by qualified personnel knowledgeable in QA. The e
o g h, review is to determine similarity, compatibility, _and inclusion of
.the quality assurance requirements and acceptance criteria-of the
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- XII. Control 'of !!easurino and Tr luipment 1.
The PSAR should descrice those measures which assure:
procedures describe the calibration technique, calibration a.
frequency, maintenance and control of all measuring and test instruments, tools, gages, fixtures, reference standards, transfer standards, and nondestructive test equipment which are to be used in the measurement, inspection, and monitoring of safety related components, systems, and structures.
b.
measuring and test equipment are uniquely identified and have traceability to the calibration test data, measuring and test instruments are calibrated and maintained al c.
specified intervals based on the required accuracy, purpose, the degree of usage, stability characteristics, and other conditions-affecting.the measurement.
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an investigation will be conducted and documented to determine the validity of previous inspections performed when measuring and 4
test equipment are found to be out of calibration.
calibrating standards have an uncertainty (error) requirement j-e.
of no more than 1/10th of the uncertainty of the equipment being calibrated. Greater calibrating standards uncertainty may be
-acceptable when limited by the " state of the art".
f.
records are maintained which indicate the complete status of all items under the calibration system.
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reference and transfer standards are traceable to nationally
. recognized: standards or where national standards do not exist provisions are established to document the basis for calibration.
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j s.d XIII. Handlino Storace, and Shiocina 1.
The PSAR should describe the measures which assure:
special handling, preservaticn, storage, cleaning, and a.
shipping requirements are determined and accomplished by qualified individuals in accordance with predetermined work and inspection instructions.
procedures are prepared in accordance with design and b.
specification requirements which control the cleaning, handling, storage, shipping, and preservation of materials, compor _nts and systenis, to preclude damage, less or deterioration from environments such as moisture and temperature.
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- XIV.
Inspection, Test, and Goeratine Status 1.
The PSAR.should describe those measures which assure:
a.
identification of the inspection, test, and operating status of i
' structures, systems and components is known throughout.
I-manufacturing and installation.
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- b. control of the use of inspection and welding stanips and status indicators including the authority for application and removal i
' of tags, markings, labels, and stamps.
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that any bypassing of required inspection, tests, and other
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critical operations is controllel thrcugh docunented measures _
f-d.
the status of nonconforming, inoperative or. malfunctioning structures, systems, or components are clearly identir'.ed to prevent' inadvertent use.
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' p' -V-XV. lionconforming I'aterials, Parts or Comoonents 1.
The PSAR should describe the measures which assure:
control of the identification, documentation, segregation, review, a.
disposition, and notification of affected organization of non-conformance of materials, parts, components, or services.
b.
documentation identifies the nonconforming item, describes the nonconformance, the disposition of the nonconformance, the inspection requirements and includes signature npproval of the disposition.
identification of the responsibility and authority for determining c.
and approving the disposition of nonconforming items.
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d.
nonconforming items are segregated from acceptable items and identified as' discrepant until properly dispositioned.for use..
acceptability of rework or repair of materials, parts, components, e.
systems, and structures is verified by reinspecting the item as originally inspected or. by a method which is at least equal ~ to the original inspection method and that inspection rework and repair procedures are documented.
f.
nonconformances concerning departures from design specifications
'and drawing requirements, which are dispositioned "use as is" and
" repair" are formally reported to the utility management.
9.
periodic analysis of these reports is performed and forwarded to management to show quality trends.
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the nonconformance reports dispositioned " accept as is" or " repair" l
are made part of the inspection records and forwarded with the hardware to the utility's file.
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XVI. Corrective Action 1.
The PSAR should describe those measures which assure:
i evaluation of nonconformance and determination of the need for a.
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corrective action is in accordance with established procedures.
b.
the cause of the no'nconformance is determined and that prompt corrective action to preclude the recurrance of those significant conditions adverse to quality is intended.
followup on corrective actions to verify proper implementation and c.
to close-out the corrective action documentation.
I d.
documented reporting to appropriate levels of management of.
significant conditions adverse to quality, the cause of the con-O.
ditions, and the corrective action taken.
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XVII. Quality Assurance Records 1.
The PSAP should describe the measures which assure:
records are maintained to provide documentary evidence of the a.
quality of items and of activities affecting quality.
b.
these records include the operating logs, results of review, inspections, tests, audits, and. monitoring of work performance and material analysis; the qualification of. personnel, procedures, and equipment; othe; documentation such as drawings, specifications, procurement documents, calibration procedures, calibration reports, I
and nonconforming and corrective action reports.
records will be identifiable and retrievaale.
c.
d.
requirements and responsibilities for record transmittals, retention and maintenancs subsequent to completion of work are consistent
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the inspection and test records contain the following:
e.
1 (1) a description of the type of operation.
(2) evidence o: completing and/or verifying a Lau,'acturing, 1
inspection or test operation.
(3) the results of-the inspection or test.
(4) information related to nonconformances.
(5) inspector or data recorder.
(6) acceptability.
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storage facilities are construc;ed, located, and secured, to prevent destruction of the records through fire, flooding, theft, and deterioration by temperature or humidity conditions.
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/~N V-XVIII. Audi ts 1.
The FSAR should describe those measures which assure:
the performance of audits is in accordance with preestablished a.
written procedures or check lists and conducted by appropriately trained personnel not having direct responsibilities in th0 areas being audited, b.
the audit results are documented and reviewed by management having responsibility in the area audited.
responsible management takes the recessary action to correct the c.
deficiencies revealed by the audit.
- d.. deficient areas are promptly reaudited until corrections have (O
'd been accomplished.
e.
audits include an objective evaluation of quality related-practices,e,,
procedures, and instructions; the effectiveness of implementation; and the conformance with policy directives.
f.
the audits include the evaluation of work areas, activities, processes, and items, and the review of documents and records.
g.
the following types of audits are performed:
(1) audits by the QA organizction to provide a comprehensive independent verification and evaluation of quality related procedures and activities to assure that they are meaningful and are effectively complying with the QA Program requirements.
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(2) external audits performed by the applicant and principal contractors on their suppliers performing activities or safety related structures, systems, and components. These audits must include verification and evaluation of their QA Program, procedures, and activities to assure that they are meaningful'and are effectively complying with all aspects of the QA Program and procurement requirements.
(3) audits performed by major contractors, subcontractors, a'nd vendors to verify and evaluate their suppliers QA Program, procedures, and activities to assure they are meaningful and are effectively complying with the QA Program and pro-h" curement requirements.
h.' audits"aFe' regularly scheduled on the basis of the -status and safety importance of the activities being performed, and that they are initiated early enough to assure effective quality assurance during the design, procurement, and contracting activities.
i.
analysis of audit data be performed and reports provided to management which indicate quality trends and the effectiveness of the QA Program.
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N A LYSIS EPORT W@EOM[1 3 AP sPM/
FLORIDA POWER CORPOR ATION
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TABLE OF CONTENTS g)
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1 Section Pg 1
INTRODUCTION A.
SUMMARY
Volume 1 Tab 1 1-1
1.1 INTRODUCTION
1-1 1.2 DESIGN HIGHLIGHTS.
1-2 1.2.1 SITE CEARACTERISTICS 1-2 1.2.2 POWER LEVEL 1-2 1.2.3 PEAK SPECIFIC POWER LEVEL 1-2 1.2.4 REACTOR BUILDING SYSTEM 1-2 1.2.5 ENGINEERED SAFEGUARDS.
1-3 1.2.6 ELECTEICAL SYSTEMS AND EMERGENCY POWER 1-3 1.2 7 ONCE-THROUGH STEAM GENERATORS 1-4 1.3 TABULAR CHARACTERISTICS.
1-4 1.h PRINCIPAL DESIGN CRITERIA 1-7 1.h.1 CRITERION 1 1-7 1.h.2 CRITERION 2 1-9
'.h.3 CRITERION 3 1-10 1.4.4 CRITERION h 1-10 1.h.5 CRITERION 5 1-11 1.4.6 CRITERION 6 1-11 1.h.7 CRITERION 7 1-12 1.h.8 CRITERION 8 1-13 1.h.9 CRITERION 9 1-13
<w 1.4.10 CRITERION 10.
1-lh Iq,)
1.h ll CRITERION 11.
1-15 1.4.12 CRITERION 12.
1-15 1.h.13 CRITERION 13.
1-16 1.4.14 CRITERION 14..
1-17 1.4.15 CRITERION 15.
1-17 1.h.16 CRITERION 16.
1-18 1.h.17 CRITERION 17 1-19 1.h.18 CRITERION 18.
1-20 1.h.19 CRITERION 19.
1-21 1.h.20 C3ITERION 20.
1-22 1.4.21 CRITERION 21.
1-22 1.h.22 CRITERION 22.
1-22 1.h.23 CRITERION 23.
1-23 1.h.2h CRITERION 24.
1-2h 1.h.25 CRITERION 25 1-2h 1.h.26 CRITERION 26.
1-25 1.4.27 CRITERION 27 1-26 1.5 RESEARCH AND DEVELOPMENT REQUIREMENTS 1-26 1.5.1 ONCE-THROUGH STEAM GENERATOR TEST.
1-26 1.5.2 CONTROL ROD DRIVE LINE TEST.
1-26 1.5.3 SELF-POWERED DETECTOR TESTS.
1-27 1.5.h THERMAL AND HYDRAULIC PROGRAMS.
1-27 1.6 IDENTIFICATION OF AGENTS AND CONTRACTORS 1-27
1.7 CONCLUSION
S.
1-28 7
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Section
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2 SITE AND ENVIRONMENT Volume 1.
. Tab 3 2-1 2.1-
SUMMARY
2-1 2.2 SITE AND ADJACENT AREAS.
2-1 2.2.1 SITE LOCATION AND TOPOGRAPHY 2-1 2.2.2 SITE OWNERSHIP 2-2 2.2.3 SITE AcrIVITIES.
2-2 2.2.4 POPULATION 2-3 2.2.5 LAND USE 2-3 2.2.6 DAIRY ANIMALS 2-3 2.3 METEOR 0LCGY AND CLIMATOLOGY 2-3 2.3.1
SUMMARY
2-3 2.3.2 DESCRIPTIVE METECROLOGY 2-4 2.3.3 ATMOSPHERIC DIFFUSION.
2-7 2.3.h SITE METEOROLOGICAL PROGRAM.
2-9 2.h HYDROLOGY 2-10 2.k.1 CHARACTERISTICS OF STREAMS IN VICINITY 2-10 2.h.2 FLOOD STUDIES AND HURRICANE EFFECTS 2-11 2.h.3 DESIGN OF CIRCULATING WATER SYSTEM 2-11 2.h.h LIQUID WASTE DISCHARGES 2-12 2.4.5 GROUNDWATER 2-12 2.5 GEOLOGY 2-12 2.6 SEISMOLOGY 2-13 2.6.1 SEISMICITY STUDY 2-13 2.6.2 RESPONSE SPECTRA 2-13
("'s 2.7 SITE ENVIRONMENTAL RADIOACTIVITY PROGPAM 2-13
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2.8 REFERENCES
2-14 3
REACTOR.
Volume 1.
. Tab 3 3-1 3.1 DESIGN BASES 3-1 3.1.1 PERFO'tMANCE OBJECTIVES 3-1 3.1.2 LIMI7J.
3-1 3.2 REACTOR JESIGN.
3-6 3 2.1 GENERAL
SUMMARY
3-6 3.2.2 NUCLEAR DESIGN AND EVALUATION 3-7 3.2.3 THERMAL AND HYDRAULIC DESIGN AND EVALUATICN 3-32 3.2.4 MECHANICAL DESIGN LAYOUT.
3-68 3.3 TESTS AND INSPECTIONS 3-95 3.3.1 NUCLEAR TESTS AND INSPECTION 3-95 3.3.2 THERMAL AND HYDRAULIC TESTS AND INSPECTION.
3-95 3 3.3
' FUEL' ASSEMBLY, CONTROL ROD ASSEMBLY, AND CONTROL R0D DRIVE MECHANICAL TESTS AND INSPECTION.
3-98 3.3.h INTERNALS TESTS AND INSPECTIONS 3-103 3.h REFERENCES 3-10h h
Volume 1.
. Tab 4 h-1 k.1 PERFORMANCE OBJECTIVES h-1 h.1.2 DESIGN CHARACTERISTICS h-1 l'~s b.1.3 EXPECTED OPERATING CONDITIONS h-2
(
i v
1 0014
Section Page nCl 4
REACTOR C00LA'!T SYSTEM (CONTINUED). Volume 1.
Tab 4 h.l.h SERVICE LIFE.
h-3 k.l.5 CODES AND CLASSIFICATIONS 4-6 k.2 SYSTEM DESCRIPTION AND OPERATION.
4-6 h.2.1 GENERAL DESCRIPTION h-6 h.2.2 MAJOR COMPONENTS h-6 4.2.3 PRESSURE-RELIEVING DEVICES k-12 h.2.h ENVIRONMENTAL PROTECTION.
h-12 4.2.5 MATERIALS OF CONSTRUCTION h-12 h.2.6 MAXIMUM HEATING AND COOLING RATES.
4-lh 4.2.7 LEAK DETECTION 4-lh b.3 SYSTEM DESIGN EVALUATION h-16 h.3.1 SAFETY FACTORS 4-16 h.3.2 RELIANCE ON INTERCONNECTED SYSTENS h-23 h.3.3 SYSTEM INTEGRITY h-23 h.3.h PRESSURE RELIEF.
4-23 4.3.5 REDUNDANCY 4-2h 4.3.6 SAFETY ANALYSIS.
4-2h 4.3.7 OPERATIONAL LIMITS.
4-2h 4.h TESTS AND INSPECTIONS k-25 h.h.1 COMPONENT IN-SERVICE INSPECTION 4-25 k.h.2 REACTOR COOLANT SYSTEM TESTS AND INSPECTIONS h-27 h.h.3 MATERIAL IRRADIATION SURVEILLANCE.
h-28
4.5 REFERENCES
h-30 C\\
\\- I 5
CONTAINMENT SYSTEM Volume 2.
Tab 5 5-1 5.1 REACTOR BUILDING 5-1 5 1.1 DESIGN BASES.
5-1 5.1.2 STRUCTURE DESIGN 5-2 5.2 ISOLATION SYSTFM 5-9 5.2.1 DESIGN BASES.
5-9 5.2.2 SYSTEM DESIGN 5-10 5.3 VENTILATION SYSTEM 5-11 5.3.1 DESIGN BASES.
5-11 5.3.2 SYSTEM DESIGN 5-12 5.4 LEAKAGE MONITORING SYSTEM 5-13 5.5 SYSTEM DESIGN EVALUATION 5-15 5.6 TESTS AND INSPECTION.
5-15 5.6.1 PREOPERATIONAL TESTING AND INSPECTION 5-15 5.6.2 POSTOPERATIONAL LEAK MONITORING 5-16 6
ENGINEERED SAFEGUARDS Volume 2.
Tab 6.
6-1 6.1 EMERGENCY INJECTION 6-1 6.1.1 DESIGN BASES.
6-1 6.
1.2 DESCRIPTION
6-2 6.1.3 DESIGN EVALUATION 6-3 6.1.h TESTS AND INSPECTIONS.
6-6 6.2 REACTOR BUILDING ATMOSPHERE COOLING AND WASHING.
6-13 s
)
6.2.1 DESIGN BASES.
6-13 s
6.
2.2 DESCRIPTION
6-13
Section Pg I
k
\\- /
6 ENGINEERE7 SAFEGUARDS (CONTINUED). Voluce 2.
Tab 6 6.
2.2 DESCRIPTION
6-13 6.2.3 DESIGN EVALUATION 6-lh 6.2.h TESTS AND INSPECTIONS.
6-19 6.3 ENGINEERED SAFEG'ARDS LEAKAGE AND RADIATION CONSIDERATIONS 6-20 6.
3.1 INTRODUCTION
6-20 6.3.2
SUMMARY
OF POSTACCIDENT RECIRCULATION AND LEAKAGE CONSIDERATIONS 6-20 6.3.3 LEAKAGE ASSUMPTIONS 6-21 6.3.4 DESIGN BASIS LEAKAGE 6-22 6.3.5 LEAKAGE ANALYSIS CONCLUSIONS 6-22 7
INSTRUMENTATION AND CONTROL Volume 2.
Tab 7 7-1 7.1 PROTECTION SYSTENS 7-1 7.1.1 DESIGN BASES.
7-1 7.1.2 SYSTEM DESIGN 7-5 7 1.3 SYSTEMS EVALUATION.
7-11 7.2 REGULATING SYSTEMg, 7-15.
7.2.1 DESIGN BASES.
7-15 7.2.2 SYSTEM DESIGN 7-17 7.2.3 SYSTEM EVALUATION 7-22
()
7.3 INSTRUMENTATION T-25 V
7 3.1 NUCLEAR INSTRUMENTATION 7-25 7.3.2 NONNUCLEAR PROCESS INSTRUMENTATION 7-27 7.3.3 INCORE MONITORING SYSTEM.
7-28 7.h OPERATING CONTROL STATIONS 7-31 7.4.1 GENERAL LAYOUT 7-31 7.k.2 INFORMATION DISPLAY AND CONTROL FUNCTION 7-31 7.h.3 SUNWMRY OF ALARMS 7-31 7.4.h COMMUNICATION 7-32 7.k.5 OCCUPANCY.
7-32 7.h.6 AUXILIARY CONTROL STATIONS 7-33 7.h.7 SAFETY FEATURES.
7-33 l
8
- ELECTRICAL SYSTEMS Volume 2.
Tab 8.
8-1 8.1 DESIGN BASES 8-1 8.2 ELECIRICAL SYSTEM DESIGN 8-1 8.2.1 NETWORK INTERCONNECTIONS.
8-1 8.2.2 PLANT DISTRIBUTION SYSTEM 8-2ll 8.2.3 SOURCES OF AUXILIARY POWER 8-6 8.3 TESTS AND INSPECTIONS 8-9 9
AUXILIARY AND EMERGENCY SYSTEMS.
Volume 2.
Tab 9 9-1 9.1 MAKEUP AhD PURIFICATION SYSTEM 9-2
-n L_)
00<Iw r
iv (Revised 1-15-68)
Section P_ age, b'
9 AUXILIARY AND EMERGENCY SYSTEMS (CONTINUED).
Volume 2.
Tab 9 9.1.1 DESIGN BASES 9-2 9.1.2 SYSTEM DESCRIPTION AND EVALUATION 9-3 9.2 CHEMICAL ADDITION AND SAMPLING SYSTEM 9-Q 9.2.1 DESIGN BASES 3-S 9.2.2 SYSTEM DESCPIPTION AND EVALUATION 9-10 93 COOLING WATER SYSTEMS.
9-18 9.3.1 DESIGN BASES 9-18 9 3.2 SYSTEM DESCRIPTION AND EVALUATION 9-19 9.h SPENT FUEL COOLING SYSTEM 9-24 9.h.1 DESIGN BASES 9-2h I
9.h.2
. SYSTEM DESCRIPTION AND EVALUATION 9-2h 9.5 DECAY HEAT REMOVAL SYSTEM 9-27 9.5.1 DESIGN BASES 9-27 9.5.2 SYSTEM DESCRIPTION AND EVALUATION 9-27 9.6 FUEL HANDLING SYSTEM 9-31 9.6.1 DELIGN BASES 9-31 9.6.2 SYSTEM DESCRIPTICN AND EVALUATION 9-32 9.7 PLANT VENTILATION SYSTEMS 9-37 9.7.1 DESIGN BASES 9-37 9.7.2 SYSTEM DESCRIPTION AND EVALUATION 9-37 10 STEAM AND POWER CONVERSION SYSTEM Volume 2.
Tab 10.
. 10-1 p(_,)
10.1 DESIGN BASES
. 10-1 10.1.1 OPERATING AND PERFORMANCE REQUIREMENTS
. 10-1 10.1.2 ELECTRICAL SYSTEM CHARACTERISTICS.
. 10-1 10.1.3 FUNCTIONAL LIMITATIONS
. 10-1 10.1.h SECONDARY FUNCTIONS
. 10-1 10.2 SYSTEM DESIGN AND OPERATION
. 10-2 10.2.1 SCHEMATIC FLOW DIAGRAM
. 10-2 10.2.2 CODES AND STANDARDS
. 10-2 10.2.3 DESIGN FEATURES.
. 10-3 10.2.4 SHIELDING.
. 10-3 10.2.5 CORROSION PROTECTION
. 10-3 10.2.6 IMPURITIES CONTROL.
. 10-3 10.2.7 RADI0 ACTIVITY
. 10-3 10.3 SYSTEM ANALYSIS
. 10-3
-10.3.1 TRIPS, AUTOMATIC CONTROL ACTIONS, AND AIRIMS
. 10-3 10.3.2 TRANSIENT CONDITIONS
. 10-h 10.3.3 MALFUNCTIONS
. 10-5 10.3.h OVERPRESSURE PROTECTION
. 10-5 10.3 5 INTERACTIONS,
. 10-5 10.3.6 OPERATIONAL LIMITS.
10-5 10.h TESTS AND INSPECTIONS
. 10-5 0017 v-~s V
Section P_ag a
(~ \\
V j
11 RADIOACTIVE WASTES AND RADIATION PROTECTION Volume 3.
Tab 11.
11-1 11.1 RADIOACTIVE WASTES 11-1 11.1.1 DESIGN BASES.
11-1 11.1.2 SYSTEM DESIGN 11-3 11.1.3 TESTS AND INSPECTIONS.
11-12 11.2 RADIATION SHIELDING 11-12 11.2.1 PRIMARY, SECONDARY, REACTOR BUILDING, AND AUXILIARY SHIELDING.
11-12 i
11.2.2 AREA RADIATION MONITORING SYSTEM 11-17 11.2.3 HEALTH PHYSICS 11-18 3
11.3 REFERENCES
11-22 4
12 CONDUCT OF OPERATIONS Volume 3.
Tab 12.
12-1 12.1 GRGANIZATION AND RESPONSIBILITY 12-1 12.1.1 FUNCTIONAL DESCRIPTION 12-1 12.1.2 QUALIFICATIONS 12-2 12.1.3 ORGANIZATION DIAGRAM 12-2 12.2 TRAINING.
12-2 12.2.1 STATION STAFF 12-2 12.2.2 REPLACEMENT PERSONNEL.
12-5 12.2.3 ON-THE-JOB TRAINING 12-6 i
()
12.2.h EMERGENCY PLANS.
12-6 l 12.2.5 PROCEDURES APPLICABLE TO ACCIDENTS INVOLVING RADIOACTIVE MATERIALS 12-6 12.3 WRITTEN PROCEDURES 12-7 12.h RECORDS 12-7 12.5 ADMINISTRATIVE CONTROL 12-7 13 INITIAL TESTS AND OPERATION Volume 3.
Tab 13.
13-1 13.1 TESTS PRIOR TO REACTOR FUELING 13-1 13.2 INITIAL CRITICALITY 13-1 13.3 FOSTCRITICALITY TESTS 13-1 1h SAFMTY N:ALY3IG Volume 3.
Tab 14 14-1 1h.1 CORE AND COOLANT BOUNDARY PROTECTION ANALYSIS 14-1 1h.1.1 ABNORMALITIES 1h-1 14.1.2 ANALYSIS OF EFFECTS AND CONSEQUENCES.
14-3 14.2 STANDBY SAFEGUARDS ANALYSIS 14-20 14.2.1 SITUATIONS ANALYZED AND CAUSES.
14-20 1h.2.2 ACCIDENT ANALYSES 1h-21 1h.3 REFERENCES Ih-57 15 TECHNICAL SPECIFICATIONS 15-1 (y
N./-
nn3 r-UUlu vi -(Revised 1-15-68).
--t 9
,_y
TABLE OF APPENDICES Appendix 1A TECHNICAL QUALIFICATIONS........ Appendices..... Tab 1A PA POPULATION AND LAND USE
. Appendices..... Tab 2A 2B ETEOROLOGY
.1ppendices.
. Tab 23 2C FLOOD STUDIES AND HURRICANE EFFECTS
. Appendices.
. Tab 2C 2D BADIOACTI n LIQUID WASTE DISCHARGE LIMITS..
. Appendices.
. Tab 2D 2E GROUNDWATER
. Appendices..... Tab 2E 2F GENERAL GEOLOGY--FIGIONAL TECTONICS
. Appendices.
. Tab 2F 2G ENGIEERING GEOLOGY AND FOUNDATION STUDIES.
. Appendices.
. Tab 20 2H BEDROCK SOLUTION STUDIES..
. Appendices..... Tab 2H 2I SEISMOLOGY.
. Appendices.
. Tab 2I SA STRUCTURAL.
............,.. Appendices.
. Tab 5A 5B DESIGN PROGRAM FOR REACTOR BUILDING
. Appenaices..... Tab 5B 5C DESIGN CRITERIA FOR REACTOR BUILDING.. Appendices.
. Tab SC SD QUALITY CONTROL
..... Appendices..... Tab SD SE LINER PLATE SPECIFICATION
. Appendices.
. Tab SE 5F REACTOR BUILDING INSTRUMENTATION.
. Appendices.
. Tab 5F SG TURBINE-GENERATOR MISSILES.
. Appendices..... Tab 5G O
12A FLORIDA PUBLIC SAFETY EMERGENCY PROCEDURES.
. Appendices.
. Tab 12A Supplement 1
Response to DRL letter,1-19-68..... Volume 4.. Supplement No.1 2
Voluntary Response to AEC Oral Inquiry. Volume 4.. Supplement No. 2 3
Voluntary Response to AEC Oral Inquiry. Volume 4.. Supplement No. 3 4
Response to DRL letter, 3-13 69..... Volume 4.. Supple =ent No. 4 5-Response to DRL letter,11-8-69...... Volume 5.. Supplement No. 5 6
Response to DRL letter, 11-8-695
. Volume 5.. Supplement'No. 6 vii (3-2-70) 0019 L
-we..<--~e
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