ML20039B315
| ML20039B315 | |
| Person / Time | |
|---|---|
| Site: | Clinch River |
| Issue date: | 12/18/1981 |
| From: | ENERGY, DEPT. OF |
| To: | |
| Shared Package | |
| ML20039B314 | List: |
| References | |
| NUDOCS 8112220515 | |
| Download: ML20039B315 (53) | |
Text
{{#Wiki_filter:s O PAGE REPLACEMENT GUIDE FOR AMENDMENT 63 CLINCH RIVER BREEDER REACTOR PLANT PRELIMINARY SAFETY ANALYSIS REPORT (DOCKET NO. 50-537) Transmitted herein is Amendment 63 to Clinch River Breeder Reactor Plant Preliminary Safety Analysis Report, Docket 50-537. Amendment 63 consists of new and replacement rges for the PSAR text. Vertical lines on the right hand side of the page are used to iden-tify question response infonnation and lines on the left hand side are used to identify new or changed design infonnation. The following attached sheets list Amendment 63 pages and instructions for their incorporation into the Preliminary Safety Analysis Report. O wwaakk B
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AMENDMENT 63 PAGE REPLACEMENT GUIDE REMOVE THESE PAGES INSERT THESE PAGES Chapter 1 1.4-9 thru 14 1.4-9 thru 14 1.4-27, 27a, 28, 29 1.4-27 27a, 28, 29 1.4-34, 35 1.4-34, 35 1.6-1, 2 1.6-1, 2. Chapter 3 3.8-1, la 3.8-1, la 3.8-3, 3a- 3.8-3, 3a Chapter 5 5.1-19 5.1-19 5.5-46, 47 5.5-46, 47 5.5-52, 53 5.5-52, 53 5.7-9, 10 5.7-9, 10 Chapter 8 REMOVE ENTIRE CHAPTdR 8 INSERT ENTIRE CHAPTER 8 (Maintain Tabs) (Last page is 8.3-104) Chapter 9 9.4-1, 2, 3, 3a 9.4-1, 2, 3, 3a Chapter 15 15.1-98, 99 15.1-98, 99 Chapter 17 170-10a, 11.thru 17, 17a 17D-10a, 11 thru 17, 17a 17D-23, 23a 17D-23, 23a 17D-33 thru 36 17D-33 thru 36 17D-45 thru 53 170-45 thru 53 17E-iii, iv 17E-iii, iv 17E-3 thru 11, lla, 12 17E-3 thru 11, lla,12 17E-25,'26 17E-25, 26 17E-29, 30 17E-29, 30 17E-37, 38 17E-37, 38 p(j- 17E-41 thru 51 17E-41 thru 51 17El-1, la, 2 thru 15 17El-1, la, 2 thru 15, 17E2-1 17E2-1 - A
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O AMENDMENT 63 1 ,- Question / Response Supplement i This Question / Response Supplement contains an Amendment 63 tab i sheet to be inserted following the Q-1 (Amendnent 62 , November 1981) page. Page Q-i-(Amendment 63, December 1981) is t'o follow the Amendment 63 tab 4 sheet. ' i There are no new or updated Question / Response pages included j in this amendment. ' i lO J h i ( 1 d a i f i a n lO 1 4 a- ~ - - --,,--.---mn,-w,,,,,--~vv.e . ~.-- a .-~e,--e,,-.,,---,., -,nc,n~,------nm-- e -,-----,.,.,-.r,,,,- - - - - -a.~--- - - ~ ~ . - - --
l.4.2.5 CONTRACTOR ORGANIZATIONS O V l .4. 2. 5.1 WESTINGHOUSE ELECTRIC CORPORATION (Figures 1.4-5,6) 25 45 The Advanced Reactors Division (ARD) is part of the Advanced Power Systems Divisions which are responsible for all of the fast reactor programs within the corporation. In the Clinch River Breeder Reactor Plant Program, ARD has been contracted to perform a dual responsibility. As one of the Reactor Manufacturers (RM), ARD has been given the responsibility for the design and procurement of the primary reactor system including the fuel, reactor internals, reactor enclosure and guard vessels, and primary piping. As the Lead Reactor Manufacturer (LRM) ARD has the overall responsibility for designing and supplying the entire Nuclear Island (NI) of the plant and for conducting the overall demonstration plant program. This responsibility includes management of RM functions at ARD, Atomics International (AI) and General Electric (GE) and interfacing with Burns & Roe regarding the 15 Nuclear Island which is discussed in more detail in Section 1.4.2.5.1.1. 25 The following paragraphs describe functions of senior managers directly concerned with the Clinch River Project. In addition, Westinghouse is able to draw on the expartise of engineering and management personnel associated with the FFTF Project and R & D programs, both at the Advanced Reactors Division and at the Hanford Engineering Development Laboratories, managed by Westinghouse Hanford Company. Vice President and General Manager, Advanced Power Systems Divisions l 53 45 The Vice President and General Manager of the Advanced Power Systems l q Divisions is the senior corporate official responsible for all Liquid Metal Fast I Breeder Reactor (LMFBR) activities in Westinghouse. This includes direction r
\"'J of both the Advanced Reactors Division and the Westinghouse Hanford Company.
) He reports to the Executive Vice President, Nuclear Energy Systems, and is ' thus able to draw upon the required corporate resources to assure the necessary support of the Project. General Manager, Advanced Reactors Division 6 The General Manager of the Advanced Reactors Division reports to Sj 49 the Vice President and General Manager of the Advanced Power Systems Divisions and is responsible for all the design, development and other activities of the Division. He provides direction and guidance to the CRBRP Project Manager, 45l other Project Managers, the Technology Managers, the Product Assurance Manager, 40 the Controller, the Administration Manager and the Nuclear Safety and Reliabil-53' ity Manager. He conduct: reviews of progress being made on the Clinch River Project, and assures that any problems requiring special attention by senior coroorate management are immediately made visible. Product Assurance Manager The Product Assurance Manager is responsible to the General Manager, Advanced Reactors Division for providing overall ARD Quality Assurance functions. Since the Product Assurance Manager reports directly to the Division General Manager, he has the organizational freedom to initiate and evaluate solutions to product problems and avoid any compromise in product quality resulting from other requirements such as cost, scheduling, production and p) manufacture. He directs matters of Corporate and Divisional Quality Assurance Policy throughout the Division, ircluding the LRM Quality Assurance Effort. 15 1.4-9 Amend. 53 Jan.1980 l l
O 1.4.2.5.1.1 ARD LRM OrgarlIstion (Figure 1.4-5) CRBRP Project Manager The CRBRP Project Manager reports to the General Manager, Advanced Reactors Division and is responsible for discharging the tasks associated with the Westinghouse role for the Nuclear Steam Supply System (NSSS). The Project Manager is responsible for the NSSS technical Integration and program management, for all technical and program planning, contract and project administration, customer liaison, and direction of all NSSS development, design, procurement, component fabrication, testing efforts and the LRM Quality Assurance Program. In addition, he is responsible for providing the necessary technical requirements to the Architect-Engineer (A-E) regarding NSSS facilities requirements and support, and for providing the necessary construction liaison for the NSSS. He is responsible for the identification and timely resolution of project problems in the above areas. CRBRP Technical Director The CRBRP Technical Director reports to the CRBRP Project Manager and is responsible for technical decisions in the discharge of the Lead Reactor Manufacturer NSSS tasks. He is also responsible for NSSS Licensing and Reliability. LRM OualItv Assurance Manager LRM Quality Assurance Manager reports to the CRBRP Project Manager and has been delegated the authority and execution responsibility by the CRBRP Project Manager for establishing, maintaining, directing and managing the LRM quality assurance pr ogram as described in Chapter 17, Appendix 17D. CRBRP Prmysm Control Manager ihe CRBRP Program Control Manager is responsible to the CRBRP Project Manager for NSSS plans and schedules, estimates, budgets, cost control, development of project policles and requirements, cost reduction offorts, prcject administration, and data and systems r.anagement. LRM Procurement Manager The LRM Procurement Manager is responsible to the CRBRP Project Manager for LRM Procurement activ tles. He administers and controls the LRM contracts wIth the RMs and LRM suppllers to assure that the required systems, structures l and con.gnents are procured consistent with contract requirements. O 1.4-10 Amend. 63 Dec. 1981
ARD Procram Manager The ARD Program Manager reports to the CRBRP Project Manager and is responsible for the coordination of ARD RM activities. GE Procram Manager The GE Program Manager reports to the CRBRP Project Manager and is responsible for the coordination of GE RM activities. Al Proaram Manager The Al Program Manager reports to the CRBRP Project Manager and is responsible for the coordination of Al RM activities. CRBRP Svstame integration Manager The CRBRP Systems integration Manager reports to the CRBRP Project Manager _and is responsible for control and Integration of the NSSS design and system l Interface including the LRM-AE-Constructor interface and development activities. Steam Generator Procram Manager The Steam Generator Program Manager reports to the CRBRPh'roject Manager and is responsible for the Steam Generator component design end fabrication program activities. O 1.4-11 Amend. 63 Dec. 1981
1.4.2.5.1.2 ARD RM Organization (Figure 1 4-61 CRBRP Project Manager The CRBRP Project Manager reports to the General Manager, Advanced Reactors Division and is responsible for discharging the tasks associated with the division's role as a Reactor Manufacturer (RM). In this capacity the Project Manager has the responsibility for all the technical and financial planning associated with the Westinghouse RM activities. CRBRP Reactor Plant Project Manager The CRBRP Reactor Plant Project Manager is responsible to the CRBRP Project Manager and through him to the ARD General Manager for the overall management of CRBRP RM activity at ARD. This includes the administration, design, documentation, procurement, shipment, and installation support of the NSSS systems, components, and licensing, safety and reliability related activities as well as all required sof tware as assigned by the CRBRP Project Manager. Reactor Engineering Manager The Reactor Engineering Manager is responsible to the CRBRP Reactor Plant Project Manager for establishing system requirements for the reactor enclosure, Internals, and control rod systems; and the design, documentation, shipment, and Installation support of the reactor vessel, reactor internals, reactor primary control rod system, reactor guard vessel, reactor closure head, and the components for the head access area and the reactor cavity and for the stress and thermal / hydraulic analysis of the permanent roactor components. Reactor Analvsls and Core Design Manager The Reactor Analysis and Core Design Manager is responsible to the CRBRP Reactor Plant Project Manager for structures analyses, nuclear design, core thermal and hydraulic analyses, shielding analyses, and the design, documentation, and installation support of the fuel and removable assemblies. Procram Control and Design Integration Manager The Program Control and Design Integra1L n Manager is responsible to the CRBRP Reactor Plant Project Manager for establishing reactor system requirements, integration of ARD systems (particularly interface control), maintaining cost and schedule visibility and control, planning, configuration management, and preparation of RM procedures. O 1.4-12 Amend. 62 Nov. 1981 1
,_ Reactor Plant Procurement Manager
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The Reactor Plant Procurement Manager is responsible to the CRBRP Recctor Plant Project Manager for all CRBRP procurement. This includes establishing internal purchasing procedures to assure procurement is conducted in accordance with contractual and corporate procurement requirements. Plant Engineering Manager The Plant Engineering Manager is responsible to the CRBRP Reactor Plant Manager for establishing system requirements for the reactor heat transport system, plant control, data handling, reactor and vessel instrumentation systems, plant protection systems, as well as the design, fabrication documentation, shipment, and installation support of the components in those systems. In addition, he is responsible for providing overall plant performance and reliability analyses, and the manuf acturing engineering support for all ARD RM NSSS components. CRBRP Licensing and Safety Manager The CRBRP Licensing and Safety Manager is responsible to the CRBRP Reactor Plant Project Manager for all activities necessary for licensing and the required safety analysis. He is responsible for assuring that nuclear safety, and licensing requirements have been satisfied, for the preparation and coordination of licensing documentation generated within the ARD-RM, for assuring that the required safety analyses are performed, and for directing (~ 3 safety analyses conducted by GE as the agent of the LRM. i 's' ~ ! RM Oualltv Assurance Activities All ARD RM Quality Assurance activities are performed by the Division's Product Assurance Department which is totally independent from the RM Engineering and Procurement Organization. For the description of the Divisional RM Quality Assurance Organization and its duties and responsibilities see Chapter 17 Appendix 17H. 1.4.2.5.2 Burns and Roe. Inc. - Breeder Reactor Division (Figure 1.4-7) Breeder Reactor Division Senior Corocrate Vice President The Senior Corporate Vice President and Director of the Breeder Reactor Division is the senior corporate officer assigned to the project and reports to the President. He draws upon the total resources of the corporation to assure that all necessary actions and support are forthcoming. He provides senior technical guidance as ne:essary. He assures that any problems requiring attention and resolution are being acted on in a timely manner, ry
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1.4-13 Amend. 62 Nov. 1981
Breeder Reactor Division Vice President The Vice President and Deputy Director of the Breader Reactor Division reports to the senior corporate officer assigned to the project. He provides guidance and direction to the Project Manager and the Project Quality Assurance Manager in the conduct of the project. He performs special reviews of the engineering and design work being conducted on the project and of progress being made. He assures that any problems requiring attention and resolution are being acted on in a timely manner. He contacts senior representatives of DOE and the LRM as necessary to assure satisfactory completion of overall project efforts. CRBRP Project - Project Manager The Project Manager reports to the division Vice President and is assigned overall responsibility and authority for carrying c,ut Burns and Roe's contractual commitments to DOE. He directs and coordinates all project activities in a manner to assure that all Burns and Roe efforts are proceeding in an integrated fashion which will support procurement and construction efforts and will produce a satisfactory technical product, on time, and at minimum cost to DOE. He assures that the engineering and design work by Burns and Roe provides a safe and reliable plant with minimum environmental impact, and a plant which has good operability, availability, maintainability, flexibility, inspectability, and prospect for future economy. He is the official point of contact for the project within Burns and Roe and assures that Burns and Roe's efforts are carried out in a satisfactory manner. He issues management reports and information concerning the project. Assistant Project Manager The Assistant Project Manager reports to the Projec t Manager. He is l responsible for monitoring the coordination of in-house activities to ensure the design product, daily production and continuing output are all in confermance with contractual requirements. He performs such other duties or tasks as he may be assigned by the Project Manager. Contract Administration Manager The Contract Administration Manager directs the contract administration functions for the project. He reports to the BRD Vice President and supports the CRBRP Project Manager as the central point of contact for the project on contract administre.+1on matters, included in contract administration matters are preparation of documentation, compliance with notification provisions, cost segregation, and negotiation. O 1.4-14 Amend. 63 Dec. 1981
i i s l Breeder Reactor Division Vice President V A minimum of 15 years of progressive responsibilitles in the management and supervision of all phases of engineering efforts is required with primary emphasis in the nuclear field. He must have a working knowledge of the corporation's resources and also have a Bachelor's degree in Business and/or Science with additional education and/or training in nuclear technology. CRBRP Project Manager A minimum of 12 years of progressive responsibility for the management and supervision of technical efforts is essential, with primary emphasis on the development of nuclear power plants. He must have at least a Bachelor of Science degree and education and training in nuclear reactor technology with some training in Business Administration or Management preferred. Assistant Project Manager l A minimum of 8 years experience in progressively responsible positions for the management and/or supervision of technical efforts primarily in nuclear power l plant technology. He must have at least a Bachelor's degree in Science or Engineering with some training in business administration or management. Contract Administration Manager A minimum of 5 years of practical contract administration experience in the p administration and negotiation of government and/or commercial contracts and Q possess a knowledge of federal procurement regulations and policies. He must have a minimum of a Bachelor's degree in Business Administration or Engineering. Licensing and Environmental Manager l A minimui of 5 years experience in supervision of nuclear power plant iIcensing and engineering is required. At least a Bachelor of Science degree with education and training in nuclear reactor technology is required. l Nuclear Island and Balance of Plant Profect Engineering Managers l The requirement is a minimum of 8 years of progressive responsibility for the management and supervision of technical efforts, with primary emphasis on the development of nuclear power plants. He must have at least a Bachelor of l Science degree and some training in Business Administration or Management. O 1.4-27 Amend. 63 Dec. 1981
Project Ooerations Manager l A minimum of 7 years of experience is required in the management of technical l ef forts with a detailed knowledge of project management techniques. He must have at least a Bachelor of Science degree with education in management principles. O O 1.4-27a ATiend. 63 Dec. 1981
OualItv Assurance Manager O The minimum requirements for the Quality Assurance Manager are shown in (~'/ Section 17E 1.4.1. Project Office Resident Manager l A minimum of 5 years of progressive responsibility for the management and supervision of technical efforts with primary emphasis in nuclear technology. , l He must have at least a Bachelor of Science degree or equivalent experience and education and training in nuclear reactor technology. 1.4.4.6 Stone and Webster Engineering Corocration Specific qualification requirements at Stone and Webster Engineering Corporation are identified for key positions identified and described in Section 1.4.2.5.6. For alI the qualification requirements, in Ileu of a degree, equivalent qualifications may be substituted based on other educational accomplishments, experience in related fields and technical achievements, such as holding a license as a Professional Engineer or Certification as a Quality or Reliability Engineer by the American Society for Quality Control. CRBRP Senior Project Manager A minimum of ten years of progressive responsibilities in the supervision and management of various phases of engineering, construction, and/or quality O D assurance efforts is required, with primary emphasis in the nuclear power plant field. He must have a working knowledge of the Corporation's resources and also have a Bachelor of Science or Arts degree with additional and/or training in power plant technology. CRBRP Denutv Director of Construction A minimum of ten years of progressive responsibilities in the supervision and management of heavy construction projects, with emphasis on the construction of power and/or process facilities. He must have a working knowledge of the Corporation's resources and also have a Bachelor of Science or Arts degree. CRBRP Project Manager A minimum of ten years of progressive responsibility in the management and Supervision of technical efforts is essential, with emphasis in the nuclear po e plant field. He must have a Bachelor of Science or /.rts degree, with additional education and training in management and power plant technology. C 1.4-28 Amend. 63 Dec. 1981
CRBRP Project Quality Assurance Manager A mimimum of five years in responsible assignments in quality assurance and control, and/or construction of a power station is required. He must have a Bachelor of Science or Arts degree. Senior Site Construction Representative A minimum of five years in responsible assignments in field engineering and construction activities, with emphasis in the construction of power and/or process facilities. He must have a Bachelor of Science or 25 Arts degree. O O Amend. 25 1.4-29 Aug. 1976
O t t p l CLINCH RIVER BREL)R REACTOR PLANT s WESTINGHOUSE ELECTRIC CORPORATION-LRM ORGANIZATION ADV ANCE D PglWE R 5 SV STE Mi DIVIDON VICE PREseOENT AND
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ADVANCED RE actor DIVISION GENERAL M ANAGER I CReRP PROJE CT M AN AGE R I I I I i 1 SITE PERSONNEL GUALITY TE CHNICAL PROCURE MENT CONT ROLLE R RELATIONS ASSURANCE DIRECTOR 4 ASST. TO OA LRM COMPUTER
- M AN AGE R L!CE NSING _ OPERATIONS w
I I I I I I b, y SYSTEMS INTEGRATION PROGRAM CONTROL STE AM GENERATOR PROGRAM ARD PROGRAMS Al PROGRAMS GE PROGRAMS ll NSSS REACTOR AND FUEL HANDLING SYSTEMS AND DATA Er SYSTEMS STEAM GENERATOR M TENANCE LIAISON ENCLOSURE - 4 MAINTENANCE - COMPONENT ENGR DESIGN CONTROL _~ - MANAGEMENT - - OMR O REACTOR Pt ANT g,[h AUXILIARY MAJOR EOulPMENT SYSTEMS INTERFACE SUDGET AND FIN. - PROJECTS PLANNING
- PROCURE MENT -
RELATED DESIGNS
- SYSTEMS ENGINZERING -- CONTROI -
RESIDE NT RESIDENT RE SIDE NT CRSRP SITE PLANNING RESIDE NT RESIDENT MANAGER M AN AGE R M AN AGE R REPRE SE NT ATIVE SCHEDULING _ M AN AGE R _ ,.. ,_ MANAGER 86R - Al ARD RM Al GE AT FFTP CONTROL a l - i TEAM GENERATOR TECHNICAL E NGINE E RING
- ASSISTANT
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1.6 MATERIAL INCORPORATED BY REFERENCE 1.6.1 Introduction This section ' identifies technical reports incorporated by reference into the PSAR. Some of the technical reports cited were produced for the LMFBR program under the direction of the Fnergy Re-search and Development Administration (ERDA) and, therefore, contain the disclaimer notice as required by ERDA manual Appendix 3201, Part II-D. In support of the construction permit application for the Clinch River Breeder Reactor Plant, however, any such disclaimer notice should be considered to be deleted and therefore of no effect. 1.6.2 References 24l36l 1. Deleted.
- 2. WARD-D-0185, " Clinch River Breeder Reactor Plant Integrity of 42 Primary and Intermediate Heat Transport System Piping in Contain-ment", September 1977.
- 3. WARD-D-0115, " Development and Application of a Cumulative Mech-anical Damage Function for Fuel Pin Failure Analysis in LMFBR O Systems", April 1976.
-V
- 4. WARD-D-0005, " Demo Code" LMFBR Demonstration Plant Simulation Model , Rev. 4
- 5. WARD-D-0090, "CRBRP Decay Power Analysis", January 1976.
36
- 7. AI Report No. 99-TI-413-039, "EVTM/CLEM Full Scale Test Analysis" R.G. Hanson, issued August 15, 1975.
- 8. AI Report No. 99-TI-413-042, "Subscale Emissivity Test Analysis (EVTM)", D. Vanevenhoven, issued October 17, 1975.
- 9. " Hypothetical Turbine Missile Data and Probability of Occurrence for 3600-RPM-23-Inch LSB Unit for Use with Liquid Metal Cooled Fast 42 16 Breeder Reactor", General Electric Co'., August 4, 1977.
I Amend. 49 1.6-1 AP I- 1979-
10a. CRBRP-3, Volume 1, " Hypothetical Core Disruptive Accident Considerations in CRBRP; Energetics and Structural Margin Beyond the Design Basis". 10b. CRBRP-3, Volume 2, " Hypothetical Core Disruptive Accident Considerations In CRBRP, Assessment of Thermal Margin Beyond the Design Base", Rev. 2. l
- 11. WARD-D-0178, "CRBRP Closure Head Capability for Structural Margin Beyond Design Basis Loading", Revision 3, November,1978.
- 12. WARD-D-0174, "CRBRP; Active Pump and Valve Operability Verification Plan", April 1977.
- 13. WARD-D-0165, " Requirements for Environmental Qualification of CRBRP l Class 1E Equipment", Rev. 5.
14 WARD-D-0218, " Structural Response of CRBRP Scale Models to a Simulated Hypothetical Core Disruptive Accident", October 1978.
- 15. CRBRP-GEFR-00103, "CRBRP; An Analysis of Hypothetical Core Disruptive Events in the Clinch River Breeder Reactor Plant", April 1978 O
l O 1.6-2 A:nend. 63 Dec. 1981 L
3.8 DESIGN OF CATEGORY I STRUCTURES b d 3.8.1 Concrete Containment (Not Acolicable) 3.8.2 Steel Containment System 3.8.2.1 Descriotion of the Containment The Containment Vessel is a low leakage, free-standing, all welded steel vessel anchored to the base mat with a steel lined concrete bottom in the form of a vertical right cylinder having an inside diameter of 186 feet and with side walls extending approximately 169 feet from the flat bottom liner at the base to the spring line of the ellipsoidal-spherical dome. The cylindrical 4d 45 shell is embedded in concrete up to the elevation of the operating floor. On the inside of the Containment Vessel, there is the continuous reinforced concrete wall comprising the peripher al boundary of the internal concrete structure. Butting against the outside face of the steel shell from elevation 4Sl 733 feet up to the elevation of the underside of the operating floor, there is another reinforced concrete wall of sufficient thickness designed to prevent g buckling of the steel shell. Neither of the two concrete walls are considered part of the containment vessel. Alumina-silica insulation is attached to the 33 Inside surface of the Containment Vessel from elevation 816 feet to elevation 823 feet. For the Design Basis Accident, a minimum of 3 inches of insulation, I having a value of 0.0267 Btu /hr-f t-oF, is required to limit the shell 48l 61 temperature, at elevation 816', to 1300F. includes: its shell, a 1/4" bottom liner plate, one access 45l The vesselairlock, one emergency egress airlock, vacuum relief system, one equipme
/ .) hatch, penetrations, inspection ladders, miscellaneous appurtenances and attachments. The configuration of the Containment Building is shown in Ifigures in Section 1.2. The design lifetime of the containment vessel shall 391 be 30 years.
3.8.2.2 Aeolicable Codes. Standards and Soecifications 3.8.2.2.1 Codes The Containment Vessel will be designed, material procured, f abricated, installed and tested in accordance with the requirements of the ASE B&PV 43 Code, Section lil, Division 1,1974 Edition with Addenda through Winter 1974 SC and Code cases 1713,1714,1809,1682 and 1785 and ASE-Ill, Division 2,1975 Edition, Subsection CC, for the steel lined concrete containment bottom. The design shall also meet the requirements of the Class MC Section of RDT Standard E15-2T, " Requirements for Nuclear Components". l v 3.8-1 Amend. 61 Sept. 1981
All structural steel non-pressure parts such as ladders, walkways, handrail, etc. will be designed in accordance with the American Institute of Steel Construction (AISC), " Specification for the Design, Fabrication and Erection of Structural Steel Buildings (AISC, February 12,1%9). 3.8.2.2.2 Design Soecification Summary and Design Criterla The Containment Vessel, including all access openings and penetrations will be designed such that the leakage of radioactive materials from the Containment under conditions of temperature and pressure resulting from the extremely unlikely faults could not cause undue risk to the health and cafety of the public and will not result in potential offsite exposures in excess of guideline values of 10CFR100. O O 3.8-la Amend. 63 Dec. 1981
Tolerances n\/ The Containment Vessel as constructed shall not exceed the tolerance requirements of NE-4000 of ASME-Ill for fabrication or erection. The dimensional control procedures shall meet the requirements of RDT STD F3-15T. The out-of-plumb tolerances shall not exceed 1/500. The out-of-roundness tolerance shall not exceed 1/2 of one percent of the nominal inside diameter. 3.8.2.2.3 Agglicable NRC Regulations and Regulatorv Guides NRC Regulatorv Guldes The applicable regulatory guides are listed below. 1.10: Mechanical (Caldwell) Splices in Reinforcing Bars of Category l Concrete Structures (Revision 1, January 2,1973). 1.11: Instrument Lines Penetrating Primary Reactor Containment (March 10,1971) 1.12: Instrumentation for Earthquakes (Revision 1, April, 1974) 1.13: Spent Fuel Storage Facility Design Basis (December,1975) Attachment l 1.15: Testing of Reinforcing Bars for Category 1, Concrete Structures ()/ \_, (Revision 1, December 28, 1972) 1.19: Nondestructive Examination of Primary Containment Liner Welds (Revision 1, August 11, 1972) 1.29: Seismic Design Classification (Revision 2, August 1976) 1.55: Concrete Placement in Category 1, Structures (June 1973) 1.57: Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components (June,1973) 1.60: Design Response Spectra for Seismic Design of Nuclear Power Plants (Revision 1, December,1973) 1.61 : Damping Values for Seismic Design of Nuclear Power Plants (Oct. 1973) 1.63: Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants (Revision 2, July,1978) 1.69: Concrete and Radiation Shields for Nuclear Power Plants (December, 1973) D 3.8-3 Amend. 63 Dec. 1981
1.75: Physical Independence of Electrical Systems Division 2 (September, 1978) 1.85: Materials Code Case Acceptability - ASME Section 111, Division 1, 1976 1.92: Combining Modal Responses and Spatial Components in Seismic Response Analysis (Revision 1, Feb., 1976) 1.102: Flood Protection for Nuclear Power Plants Rev. 1 (September 1976) 1.117: Tornado Design Classification (September 1976) 1.122: Development of Floor Design response Spectra for Seismic Design of Floor-Supported Equiptrant or Components (September 1976) I 1.124: Design Limits and Loading Combinations for Class l Linear-Type Component Supports Of the above, Regulatory Guide 1.63 is applicable after the following changes:
- 1. Deleting "Iight-water-cooled" wherever it appears.
- 2. Replacing " Appendix B to 10 CFR Part 50" wherever it appears with "RDT Standard F2-2".
- 3. Replacing " General Design Criterion 50 of Appendix A to 10 CFR Part 50" wherever it appears wIth "CRBRP GDC 41".
- 4. Replacing " loss of coolant accident" with " containment design basis accident."
- 5. Substituting "(Summer 1972 Addenda)" following "...ASME Boller and Pressure Vessel Code" with ",1974 Edition."
Construction No special construction techniques are anticipated for this containment vessel. O 3.8-3a Amend. 63 Dec. 1981
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OvesP f .a . y pie, 19 %8 M.4 t 17518 u5 j ro son... sesf f Rui 0*.II Pe.GO.T Figure 5.1-3. HTS Hydraulic Profile PSAR 6250 Amend. 53 5.1-19 Dec. 1981 r 1
TABLE 5.5-6 p
'w) SGS LOADING CONDITIONS 35l ASME III Code Class 3 system components will'be designed considering d
the following load combinations: 1 Pumps (Recirculation loop) Operating Condition Component Load Stress Limit See Note 1 Pump Case Design Pressure Section III Design Temperature Allowable Stress Cover Design Pressure Section III Bolting Design Temperature Allowable Stress Safe Shutdown Earthquake Pump Thrust Weight-Gasket Loads Note 1: Design pressures and. temperatures .of the recirculation system com-ponents are established using pressures and temperatures occurring during emergency and faulted transients. The design temperature is
, not exceeded during these transients'. The design pressure may be O't./ exceeded by not more than~10% during these transients. Normal and upset conditions are not controllina.
2 Valves (Recirculation Loop and fiain Water / Steam) 35l The valve pressure retaining parts designed to ASf1E -~III Class 3 will withstand seismic forces and pipe loads of the SSE as well as design pressure and temperatures. On other parts, if earthquake needs are to be considered, the following applies:
- Operating Condition Loads Upset 1. Normal Operating
- 2. OBE Faulted 1. Normal Operating
- 2. SSE T
1
- Amend.-35 5.5-46 Feb. 1977
T AIR E 5.5-7 SGS PIPING AND THEIR DESIGN CHARACTERISTICS NO. NO. ASME CODE COMPONENT PER PER SEC. It! DESIGN PIPING AND HEADERS SIZE LOOP PL ANT CLASS REQUIREMENTS
- l. Steam Generator Subsystem & Feedwater Sut, system SGB Wall to Drum Feedwater isolation 3000 psig, 500 F 10", sch. 160 3 3 Valve 1 Feedwater Drum Isolation Valve to 2200 psig, 650 F Steam Drum 10", sch. 140 1 3 3 Drum to Pump Intet Header 10", sch. 140 4 12 3 2200 psig, 650 F Pump Headers (Inlet) 18", sch. 140 1 3 3 2200 psig, 650 F Pump Inlet Header to Pump 18", sch. 140 1 3 3 2200 psig, 650 F Pump to Pump Discharge Tee 12", sch. 160 ' 1 3 3 2450 psig, 650 F Pump Discharge Tee 12", sch. 160 1 3 3 2450 psig, 650 F m
- Pump Discharge Tee to Esaporator
- lsolation Valve 10", sch. 16C 2 6 3 2450 psig, 650 F
*= Evaporator Isolation Valve to 2400 psig, 650 F N Evaporator 10", sch. 160 2 6 3 Evaporator to Drum 66", sch. 140 2 6 3 2200 psig, 650 F 12", sch. 140 3 3 2200 psig, 650 F Drum to S.H. 1 2200 psig, 650 F 3 3 S.H. to isolation Valve 16", sch. 160 1 3 3 1900 psig, 935 F isolation Valve to SGB Wall 16", sch. 160 1 Startup Feedwater Control Valve 3000 psig, 500 F sch. 160 3 3 Piping 4", 1
- 2. SWRPRS Sodium Rupture Disc Discharge Lines to Separator Tanks 18" nom., var.
wall, 24" nom., var. wall, 26.46" c3 p l 3 9 3 300 psig, 800 F nom., 2.2" well Qg Separator Tanks to SGB Roof 16", sch. 40 1 3 3 125 psig, 200/800 F . s 3 ANSI 125 psig, 100 0F Q- SG8 Roof to Flere Tip 16", sch. 40 1 g B31.1 e Cr m >-* w
& O O
~ _ _ . . _ _ - _ . _ - . - . - _ _ _ _ _ _ _ _ O O O Table 5.5-10 SWR DESIGN BASIS ASME CODE CATEGORY OTHER STEAM GENERATORS AND IHTS EQUlPMENT FAILED STEAM ENERATOR AFFECTED RPST IN THE AFFECTED LOOP LEAK DESCRIPTION (1) Upset Normal- Upset 44 SmalI Leak in One Tube One EDEG' Followed by Two Faulted , Faulted Emergency Additional Single EDEG
^ Failures at One Second 61 Intervals (Total 3 EDEG's)
(1) Seo Section 5.5.3.6 for detailed descriptions and basis 61l
- Equivalent double ended gu!Ilotine r
9'
- l0 8?if 7.!!
- CL
TABLE 5.5-11 CALCULATED RESULTS FOR LARGE SWR DESIGN BASIS LEAK' lHX Failed Pump Peak Peak Pressure in Adjacent Time to Failure Peak Unit Peak Pressure Steam Generators, PSIA Clear First Rollef Location P essure Pressure PSIA 8 Sec. R_Sne- Line, Seconds PSIA 8 Sec. PSIA 8 Sec. Evaporator Superheater l Evaporator 331 '. 4 373 320 337 9 0.412 = . 20 0 0.436 0 0.391 0 0.364 4.24 Superheater 304 333 311 254 3.65 _ 0 0.311 8 0.548 8 0.619 0 0.438 Water injection rate = 1.2 lb/sec for 0 1 + 1 = 0.3 sec Precursor Leak At t = 0.3 sec, one EDEG occurs. At t = 1.3 sec., one additional EDEG occurs. At t = 2.3 sec., one more DEG occurs. (total 3 (EDEG) U1 I U1 W Pao. we O
-w t
900 , , g g PRIMARY HOT LEG 940 - 920 - INTERMEDIATE HOT LEG 900 - 880 - STE AM (TURSINE THROTTLE) 860 720 700 - - PRIMARY COLD LEG 680 -
~
660 - - E I - h cc 640 - 620 - g INTERME0 TATE COLD LEG 600 -
/ -
~
580 - EV APOR ATOR INLET (WATER)
$60 540 480 460 - -
440 - FEE 0 WATER 420 - 400 - - I ' ' ' 380 20 40 60 80 100 120 THERMAL POWER N Figure 5.7-l. Expected Loop Thermal Parameters Vs. Power Level Constant Primary Flow to Power Level Ratio Constant Steam Pressure at 1450 psig Linear Primary Hot Leg Temperature 5185-2 Amend. 62 5.7-9 dov. 1981
15 2.6 l l
~
14 - 2.4 13 - VAPORATOR 2.2
- 2 g 12 -
2.0 g E E
~ ~
E0 PRIM AR Y E E
$ 10 - -
1.6 3 2 d E 0 ~ INTERMEDIATE
~
l4 e e m 8 - - 1.2 o o 7 - - 10 3 6 - ! FEEDWATER - 0.8 s - 0.6 4 04 1.1 - t7 10 - - 1.6 PRIMARY 09 - - 1.5 B og, 08 - _ i .4 g$g De C :" o z 0.7 -
/r \' _ 1,3 gg
- w o w b2 g o 0.6 - -
1.2 g$ INTE RME 0l ATE g 08 - _ j ,i 04 - - 1.0 I I I I 0.3 0.9 20 40 60 80 100 120 THERMAL POWER (%) Figure 5.7-2. Expected Loop Flow Parameters Vs. Power Level Constant Primary Flow to Power Lesel Ratio Constant Steam Pressure at 1450 psig Linear Primary llot Leg Temperature Amend. 63 5.7-10 l Lac. 1981 L
CHAPTER 8.0 ELECTRICAL POWER < TABLE OF CONTENTS PAGE
8.1 INTRODUCTION
8.1-1 1 8.1.1 Utility Grid and Interconnections 8.1-1 8.1.2 Plant Electrical Power System 8.1-1 8.1.3 Criteria and Standards 8.1-3 f 8.2 0FF-SITE POWER SYSTEM 8.2-1 8.2.1 Description 8.2-1 8.2.1.1 Connection of the Switchyards to the Utility Grid 8.2-1 8.2.1.2 CRBRP Preferred AC Power Supply 8.2-1 8.2.1.3 Reserve AC Power Supply 8.2-2 8.2.2 Analysis 8.2-4 8.2.2.1 General Analysis 8.2-4 8.2.2.2 Steady-State and Transient Analyses 8.2-6 8.2.2.3 Effects of Electrical Faults 8.2-7 8.3 ON-SITE POWER SYSTEMS 8.3-1 } 8.3.1 AC Power Systems 8.3-1 8.3.1.1 Description 8.3-1 8.3.1.1.1 Standby AC Power Supply 8.3-3 8.3.1.1.2 Safety-Related AC Power Distribution System 8.3-7 8.3.1.1.3 Plant Power Supply 8.3-17 8.3.1.1.4 Plant AC Distribution System 8.3-18 I 8.3.1.1.5 120/208 Volt Vital (Uninterruptible) AC Power System 8.3-19 . 4 8.3.1.1.6 Remote Multiplexing System (RMS) 8.3-21 8.3.1.1.7 Motors 8.3-22
'8.3.1.2 Analysis 8.3-22 Amend 63 Dec. 1981 l
i 1 TABLE OF CONTENTS (Cont'd) PAGE 8.3.1.3 Conformance with Appropriate Quality Assurance Standards 8.3-35 i 8.3.1.4 Independence of Class 1E Systems 8.3-35 8.3.1.5 Physical Identification of Class 1E and Non-Class 1E Equipment 8.3-43 8.3.1.6 Grounding Requirements 8.3-44 8.3.2 DC Power System 8.3-44 8.3.2.1 Description 8.3-44 8.3.2.1.1 Class 1E DC Power System 8.3-45 8.3.2.1.2 Non-Class 1E DC Power System 8.3-46 8.3.2.1.3 System Operations, Testing and Int.pection 8.3-47 8.3.2.2 Analysis 8.3-49 9 i O Amend 63 8-ii Dec. 1981
TABLE OF CONTENTS (Cont'd) _, LIST OF TABLES 3 ('- / TABLE NO. PAGE 8.2-1 Fort Loudoun K-31 Outage History 8.2-10 8.3-1A Class 1E Division 1 Diesel Generator Load List 8.3-52 8.3-1B Class 1E Division 2 Diesel Generator Load List 8.3-62 8.3-1C Class 1E Division 3 Diesel Generator Load List 8.3-73 8.3-1D Diesel Generator Load List Notes 8.3-78 8.3-2A Class 1E Division 1 125V DC Load List 8.3-79 8.3-2B Class 1E Division 2125V DC Load List 8.3-81 8.3-2C Class 1E Division 3 125V DC Load List 8.3-83 8.3-2D DC Load List Notes 8.3-84 8.3-3 Component Arrangement Criteria 8.3-85
's N -~
d Amend 63 8-iii Dec. 1981
~ . ,-
TABLE OF CONTENTS (Cont'd) LIST OF FIGURES FIGURE NO. PAGE 8.1-1 TiA 161KV Transmission System 8.1-8 8.1-2 Location of ESF Switchgear and Unit Substations 8.1-9 8.2-1 CRBRP Preferred and Reserve AC Power Supplies 8.2-11 8.2-2 CRBRP Of f-Site Power Supply-System Normal 8.2-12 8.2-3 CRBRP Off-Site Power Supply-Loss of CRBRP Generation 8.2-13 8.2-1 CRBRP Off-Site Power Supply-Loss of One Cumberland Unit 8.2-14 8.2-5 CRBRP Off-Site Power Supply-Loss of K-31 8.2-15 8.2-6 CRBRP Off-Site Power Supply-Loss of Fort Loudoun 8.2-16 Connection to the Reserve Switchyard 8.2-7 161KV Generating Switchyard Voltage Performance During 8.2-17 Loss of CRBRP Unit - No Electrical Fault 8.2-8 161KV Generating Switchyard Frequency Performance 8.2-18 During Loss of CRBRP Unit - No Electrical Fault 8.2-9 161KV Reserve Switchyard Bus Voltage Performance During 8.2-19 Loss of Fort Loudoun 161KV Line Supplying Off-Site Power Under Most Severe Transmission Disturbance 8.2-10 161KV Reserve Switchyard Bus Frequency Performance 8.2-20 During Loss of Fort Loudoun 161KV Line Supplying Off-Site Power Under Most Severe Transmission Line Disturbance 8.3-1 Key One Line Diagram AC Power Distribution, Sheet 1 of 2 8.3-90 Key One Line Diagram AC Power Distribution, Sheet 2 of 2 8.3-91 8.3-2 One Line Diagram DC Distribution System, Sheet 1 of 5 8.3-92 One Line Diagram DC Distribution System, Sheet 2 of 5 8.3-93 One Line Diagram DC Distribution System, Sheet 3 of 5 8.3-94 One Line Diagram DC Distribution System, Sheet 4 of 5 8.3-95 Amend 63 8-iv Dec. 1981 1
i i i TABLE OF CONTENTS (Cont'd) LIST OF FIGURES
. l 4 t ;
FIGURE NO. PAGE 8.3-2 One Line Diagram DC Distribution System, Sheet 5 of 5 8.3-96 8.3-3 4.16KV Class 1E Switchgear One Line Diagram, Sheet 1 of 2 8.3-97 i j 4.16KV Class 1E Switchgear One Line Diagram, Sheet 2 of 2 8.3-98 -
- 8.3-4. 4.16KV Switchgear One Line Diagram, Sheet 1 of 2 8.3-99 1
- j. 4.16KV Switchgear One Line Diagram, Sheet 2 of 2 8.3-100 8.3-5 480V Unit Substation One Line Diagram, Sheet 1 of 4 8.3-101 l
; 480V Unit Substation One Line Diagram, Sheet 2 of 4 8.3-102 480V Unit Substation One Line Diagram, Sheet 3 of 4 8.3-103 480V Unit Substation One Line Diagram, Sheet 4 of 4 8.3-104 i
i.
. O i
i i O Amend 63
- 8-v Dec. 1981 l
t i i
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CHAPTER 8.0 ELECTRIC POWER
8.1 INTRODUCTION
8.1.1 Utility Grid and Interconnections The State of Tennessee and parts of neighboring states are supplied with electric power by the Tennessee Valley Authority (TVA). TVA is a United States Government owned corporation which consists of inter-connected hydro, fossil-fueled, combustion turbine, and nuclear power plants and transmission facilities. These plants comprise the TVA utility grid and are interconnected with other power companies in surrounding states (see Figure 8.1-1). l The CRBRP will be connected to the TVA 161KV grid using two i separate and physically independent switchyards providing four separate connections to the TVA 161KV grid. The plant generating switchyard will be connected to the TVA 161XV power grid by two 161KV transmission lines, one connected to the 500-161KV Roane substation of TVA and designated as the Roane line, and the second to the Fort Loudoun Hydroe'ectric Plant and designated as the Fort Loudoun-1 line. The p. ant reserve switchyard will be connected to the TVA 161KV grid by two phys'cally separate and electri-cally independent 161KV transmission lines, one connected to the Oak Ridge Gaseous Diffusion Plant (0RGDP) switchyard of 00E and designated as the K-31 line, and the other to the Fort Loudoun Hydroelectric Plant and I designated as the Fort Loudoun-2 line. 8.1.2 Plant Electrical Power System (See Figures 8.1-2,8.3-1,8.3-2) J Power Supplies The Plant Electrical Power System consists of power supplies and power distribution systems which provide flexibility in plant operation and availability under single contingency conditions. The power supplies are comprised of: -
- 1) The Plant AC Power Supply which consists of the main generator supplying power to all plant loads through the generator circuit breaker and the unit station-service transformers (USSTs).
- 2) The CRBRP Preferred (off-site) AC Power Supply which consists of two 161XV transmission line connections from CRBRP generating switchyard to the TVA grid, each capable of supplying power to all plant loads through the main power transformer and the unit station service transformers.
- 3) The Reserve (off-site) AC Power Supply which consists of two physically independent 161XV transmission line connections from CRBRP reserve switchyard to the TVA grid. (" Reserve Power" as described here is " Preferred Power" according to l IEEE Std. 308 terminology and 10CFR Part 50, Appendix A). ;
Each line is capable of supplying power to all plaat loads ' p through the two reserve station service transformers (RSSTs). Amend 63 8.1-1 Dec. 1981
- 4) The Standby (on-site) AC Power Supply
- which consists of three physically separate and electrically independent diesel generators. Two of these diesel generators supply power to safety-related (Class 1E) Division 1 and 2 loads redundant to each other. Either one of these standby diesel generators can provide sufficient power to facilitate and maintain a safe plant shutdown. The third diesel generator provi&s power to Class 1E, Division 3 decay heat removal system and certain Non-Class 1E loads through an isolation transformer.
- 5) The DC Power Supply
- which, for each Division 1, 2, or 3, con-sists of one independent 125 volt DC battery with its asso-ciated active and spare battery chargers and an inverter for 120/208 volt AC uninterruptible power supply (UPS). Each bat-tery is capable of supplying power to DC loads and UPS loads of its associated safety division. Class 1E UPS is also referred to as vital AC power supply.
- 6) The 120/208 volt vital AC Power Supply
- which, for each Division 1, 2 or 3, consists of one independent inverter supplied by an independent DC system. Each inverter will supply power to vital AC loads of its associated safety Divi-sion. Division 1 and 2 vital AC loads are redundant to each other.
- 7) The Non-Class 1E DC Power Supply consists of two systems (Divisions A and B) each having one 125 volt DC battery dedi-cated for plant instrumentation and control. Two separate 125 volt DC batteries are dedicated for switchyard control and instrumentation and two 48 volt DC batteries are provided for the plant communication systems. Division A also has one 250 volt battery to provide power for DC motor loads. Each battery system is equipped with its own active and spare bat-tery chargers, switchgear and distribution panels. 125 volt DC and 250 volt DC battery systems have inverters for 120/208 volt uninterruptible power supply (UPS). Non-Class 1E UPS is also referred to as Non-Class 1E essential power supply.
- 8) Two Non-Class 1E 125 volt DC Power Supplies (one for Division A and the other for Division B) will be provided complete with associated active and spare battery chargers for security systems, and the associated inverters for 480 volt M UPS for security and lighting loads.
Distribution Systems The Plant electrical power distribution system can be fed by the Plant, the CRBRP Preferred and the Reserve Power supplies and provides power to all Non-Class 1E and Class 1E loads. The Plant distribution system has been divided into two systems; the normal distribution (Non-Class 1E) system and the safety-related distribution (Class 1E) system. The safety-related distribution system can be fed by the Plant,
- This equipment is Class 1E as defined by IEEE Standard 308.
O Amend 63 Dec. 1981 8.1-2
= .._ .. _. . _ . - __. .. -_ -- - - . - _ - _ - - _ -
the CRBRP Preferred, the Reserve and the Standby Power Supplies. The Standby Power Supplies are capable of providing the necessary power for all Class 1E loads. Operation When the main generator is operating, the safety-related and non-safety related distribution system receives power from the Plant Power i Supply via the generator circuit breaker and unit station service transfor-J mers. In the event of a turbine trip, a reactor trip, a main generator , fault, or a fault between the main generator and the generator circuit breaker, the generator circuit breaker will be tripped automatically. The unit station service transformers will remain connected to the CRBRP Preferred AC Power Supply (from 161KV generating switchyard) via the main power transformer and provide uninterrupted power through the Plant AC distribution system to the plant auxiliary loads. An electrical fault downstream of the generator circuit breaker will cause tripping of asso-ciated 161KV circuit breakers in the generating switchyard and circuit
- breakers of the 13.8KV and 4.16KV medium voltage (MV) switchgear. This will
] cause the loss of CRBRP Preferred- AC Power Supply to the unit station j service transformers. Upon loss of power supply to the unit station service transformers, the MV switchgear of the Plant AC distribution system will be connected automatically to the Reserve AC Power Supply. Upon' loss of the CRBRP Preferred and the Reserve AC Power Supplies, the safety-related AC distribution system will receive power from the standby (on-site) diesel generators. All Class 1E loads and their requirements are listed -in Tables 8.3-1A, 8.3-1B, 8.3-1C, 8.3-2A, 8.3-2B and 8.3-2C. 8.1.3 Criteria and Standards The following form the principal bases for the design of the electrical power system:
- 1) The entire Non-Class IE electrical power system will be split into two load groups designated as Division A and Division B, each with its own power supply, buses, transform-ers and control power.- Safety-related loads are divided into three load groups designated as Divisions 1, 2 and 3.
f 4.16KV buses of safety Divisions 1 and 2 will be fed from the e same USSTs and RSSTs as' Divisions A and.B. respectively. Division 3 will be supplied from the USST-or RSSI of Division A. i la) The Class 1E electrical system will comply with the single failure criterion. O Amend 63 , Dec. 1981 8.1-3
l 2) C' vision 1 and Division 2 will consist of loads redundant to each other, and each will have one independent diesel genera-tor connected to its bus as a stundby source of power. A manual tie between these two diesel generator buses will be provided for extreme emergency conditions.
- 3) Safety Division 3 will be powered from a separate standby diesel generator and will be independent of safety Divisions 1 and 2. This Division will feed loop 3 decay heat removal system loads. It will have its own set of battery chargers, 125V storage battery and associated inverter. The inverter will provide 120/208V vital AC power for vital AC loads of Divison 3.
- 4) There will be no automatic paralleling of the diesel generators or automatic transfer of loads between the safety divisions.
- 5) Each safety division will have its own 125V DC control and instrumentation supply complete with battery chargers and storage batteries. Inverters will provide 120/208V vital AC power supply for each of these Divisions.
- 6) Each Division A or B of Non-Class 1E loads has its own independent 125V DC and 48V DC control and instrumentation supply complete with storage batteries and battery chargers.
Division A will also have one 250V DC battery with its own battery chargers. 125V DC and 250V DC batteries will have inverters to supply 120/208V UPS for essential Non-Class 1E loads.
- 7) All storage batteries (except for security systems) will be sized to feed their connected loads for at least a two hour operation without recharging. Storage batteries for security systems are not described here.
- 8) Raceways will not be shared by Class 1E and Non-Class 1E cables. However, the Class 1E associated circuits will be treated as Class 1E circuits for cable routing purposes (in accordance with IEEE Std. 364 and Regulatory Guide 1.75),
unless an acceptable isolation device is provided.
- 9) Special identification criteria will apply for Class 1E equipment, including cabling and raceways.
- 10) Separation criteria of IEEE Std. 384 and Regulatory Guide 1.75 will be used. These establish requirements for preserving the independence of redundant Class 1E electrical systems.
- 11) Class 1E equipment will be designed with the capability to be tested periodically.
- 12) Clinch River Breeder Reactor Plant (CRBRP) General Design Criteria 15 and 16 will be satisfied in the design of the Plant power distribution system (seec action 3.1).
Amend 63 8.1-4 Dec. 1981
- 13) The following NRC hegulatory Guides will be followed in the design of the Plant power distribution system, as discussed in the appropriate sections:
Regulatory Guide 1.6 (Safety Guide 6), Rev. O, 3/71,
" Independence Between Redundant Standby (On-site) Power Sources and Between Their Distribution Systems".
Regulatory Guide 1.9 (Safety Guide 9), Rev. 2,12/79,
" Selection of Diesel Generator Set Capacity for Standby Power Supplies".
Regulatory Guiife 1.22 (Safety Guide 22), Rev. O, 2/72,
" Periodic Testing of Protection System Actuation Functions;"
Regulatory Guide 1.29, Rev. 3, 9/78, " Seismic Design , Classification". Regulatory Guide 1.30 (Safety Guide 30), Rev. O, 8/72,
" Quality Assurance Requirements for the Installation, Inspection, and Testing of Instrumentation and Electric Equipment".
Regulatory Guide 1.32, Rev. 2, 2/77, " Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants". Regulatory Guide 1.40, Rev.1,10/79, " Qualification Tests of f,3 Continuous Duty Motors Installed Inside the Containment of Q Water Cooled Nuclear Power Plants". Regulatory Guide 1.41, Rev. O, 3/73, "Preoperational Testing of Redundant Onsite Electric Power Systems to Verify Proper Load Group Assignments". Regulatory Guide 1.47, Rev. O, 5/73, " Bypassed and Inoperable' Status Indication for Nuclear Power Plant Safety Systems". Regulatory Guide 1.53, Rev. O, 6/73, " Application of the Single Failure Criterion to Nuclear Power Plant Protection Systems". Regulatory Guide 1.63, Rev. 2, 7/78, " Electric Penetration Assemblies in Containment Structures for Light-Water Cooled Nuclear Power Plants". Regulatory Guide 1.68, Rev. 2, 8/78, " Initial Test Program for Water Cooled Nuclear Power Plants". Regulatory Guide 1.73, Rev. O,1/74, " Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants". Regulatory Guide 1.75, Rev. 2, 9/78, " Physical Independence of Electric Systems". p. h Regulatory Guide 1.89, Rev. O,11/74, " Qualification of Class 1E Equipment for Nuclear Power Plants". Amend 63
. 8.1-5 Dec. 1981
Regulatory Guide 1.93, Rev. 0,12/74, " Availability of Electric Power Sources". Regulatory Guide 1.97, Rev. 2,12/80, " Instrumentation for Light-Water Cooled luclear Power Plants to Assess Plant Conditions During and Fcilowing an Accident". Regulatory Guide 1.100, Rev.1, 8/77, " Seismic Qualification of Electric Equipment for Nuclear Power Plants". Regulatory Guide 1.106, Rev.1, 3/77, " Thermal Overload Protection for Electric Motors on Motor Operated Valves". Regulatory Guide 1.108, Rev.1, 8/77, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants". Regulatory Guide 1.118, Rev. 2, 6/78, " Periodic Testing of Electric Power and Protection Systems". Regulatory Guide 1.128, Rev.1,10/78, " Installation Design and Installation of Large Lead Storage Batteries for Nuclear Pt.wer Plants". Regulatory Guide 1.129, Rev.1, 2/78, " Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants". Regulatory Guide 1.131, Rev. O, 8/77, " Qualification Tests of Electric Cables, Field Splices, and Connections for Light-Water Cooled Nuclear Power Plants". Regulatory Guide 1.137, Rev.1,10/79, " Fuel Oil Systems for Standby Diesel Generators".
- 14) The following IEEE standards have been followed in the design, qualification and maintenance of the Plant power distribution system:
IEEE 308-1980, " Criteria for Class 1E Power Systems for Nuclear Power Generating Stations". IEEE 317-1976, " Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations". IEEE 323-1974, " Qualifying Class 1E Equipment for Nuclear Power Generating Stations". IEEE 344-1975, " Recommended Practices for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations". IEEE 384-1974, " Criteria for Independence of Class 1E Equipment and Circuits". Amend 63 8.1-6 Dec. 1981
IEEE 387-1977, " Criteria for Diesel Generator Units fpplied as Standby Power Supplies for Nuclear Power Generating Sta ti on s . IEEE 450-1980, "Recocrnended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Generating Stations and Substations". A discussion for each of the above Regulatory Guides, and IEEE standards is provided in Sections 8.2 and 8.3. O l 4 l Amend 63 l 8.1-7 Dec. 1981 l
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8.2 0FF-SITE POWER SYSTEM p 8.2.1 Descriptien The off-site power supply system provides a reliable source of AC power to the CRPRP. The system consists of the CRBRP Preferred AC Power Supply and the Reserve AC Power Supply, each having two independent 161KV annections to the TVA grid. All four of these 161KV grid connections are
; 'ept contir:ausly energized. Any one of these connections can supply the
' entire plant AC distribution system loads to facilitate and maintain a safe plant shutdown and startup.
8.2.1.1 Connection of the Switchyards to the Utility Grid Off-site power will be supplied to the CRBRP by one of the four 161KV transmission lines (See Figure 8.2-1.). Two 161KV transmission lines to the Reserve Switchyard will be formed by opening and reterminating the DOE owned Fort Loudoun K-31 line. One of the lines formed by the retermination will be approximately four miles long, will connect the DOE K-31 substation bus in the reserve switchyard and will be designated as K-31 line. The K-31 substation is connected to the TVA grid by four other 161KV lines. Three of the lines connect to TVA's Kingston Steam Poder Plant and the other to TVA's Bull Run Steam Power Plant. The second 161KV transmission line, formed by the retermination and designated as Fort Loudoun-2 line, will be approximately ten miles long and will connect to TVA's Fort Loudoun Hydroelectric Plant. The Fort Loudoun Hydroelectric plant, with a generating capacity of 142,220KVA is connected to the grid by six 161KV lines. Two of the six lines connect to the CRBRP, and the [V' ') other four lines connect to 161KV substations that are an integral part of the 161KV transmission network. Two 161XV transmission lines to the generating switchyard will be formed by opening and extending the TVA owned Fort Loudoun K-33161KV line. One of the these lines will be approximately eight miles long, and will connect CRBRP to the TVA Roane substation, and will be designated as the Roane line. The fourth line, designated as Fort Loudoun-1 line, will be thirteen miles long and will connect to TVA's Fort Loudoun Hydroelectric Plant described above. 8.2.1.2 CRBRP Preferred AC Power Supply (See Figures 8.2-1 & 8.3-1) The CRBRP Preferred Power Supply consists of two 161KV transmission lines in the generating switchyard connected to the Plant distribution system through the main power transformer, and the unit sta-tion service transformers. Hereinafter this will be referred to as LRBRP Preferred AC Power Supply. The generating switchyard consists of two main buses and three bays. The Roane line terminates in bay-1 and the Fort Loudoun-1 line ter-minates in bay-3. The main power transformer high voltage overhead line terminates in bay-2. The lines at bay-1 and bay-3 are connected to bus-1 through 161KV circuit breakers and to bus-2 through motor operated disconnect switches. The main power transformer high voltage overhead lind terminates (~3 in bay-2 and is connected to bus-1 and bus-2 through 161KV circuit breakers. O Amend 63 Dec. 1981 8.2-1
The main generator is connected to the system through an isolated phase bus system from le main generator terminals through the generator circuit breaker to the low voltage terminals of the main power transformer and high voltage terminals of the unit station service transformers. During normal plant operation, power to the plant auxiliary loads will be provided from the main generator v a the generator circuit breaker and the i unit station service transformers, nereinaf ter called the Plant Power Supply. In cases where the loss of the Plant Power Supply is caused by a turbine trip, reactor trip, a main generator fault, or a fault between the main generator and generator circuit breaker, the generator circuit breaker will trip. The unit station service transformers will remain energized and receive power from the CRBRP Preferred AC Power Supply via the main power transformer. 8.2.1.3 Reserve AC Power Supply (See Figures 8.2-1 & 8.3-1) The CRBRP Of f-site AC Power Supply in the reserve switchyard con-sists of two independent 161KV transmission lines (K-31 and Fort Loudoun-2 lines) connected to two independent reserve station service transformers. The K-31 line terminates in bay-6 and the Fort Loudoun-2 line in bay-8. Hereinafter this will be referred to as the Reserve AC Power Supply. The Reserve Power Supply, as described herein, is the preferred power supply in IEEE Std. 308 and 10CFR Part 50 terminology). The reserve station service transformer yard consists of two reserve station service transf ormers, and it is physically combined with the reserve switchyard. The two reserve station service transformers are connected to reserve switchyard bus-2 and bus-1, respectively, by a rigid bus from transformer high voltage terminals. In the event of the loss of the Plant Power Supply concurrent with the loss of the CRBRP Preferred AC Power Supply, the Plant distribution system will be transferred automatically to the Reserve Power Supply by a fast dead bus transfer scheme, as described in Section 8.3.1.1. Offsite Power Supply Lines The DOE owned K-31 Fort Loudoun 161KV transmission line, which will be opened and reterminated at the CRBRP consists of approximately ten miles of single circuit, self-supporting steel towers and approximately four miles of single circuit wood H-frame construction. Both sections of the line were designed to meet or exceed the National Electrical Safety Code heavy loading strength requirements. This ensures that the line has ade-quate structural integrity for wind and heavy icing conditions in excess of Amend 53 9 Dec. 1981 8.2-2
those that would be expected to occur in the area. The wire tensions for the conductors and shield wires were selected to ensure that vibration damage will not occur. Long experience with transmission lines in the Tennessee Valley area has verified that, where the tension is kept below 18 O percent of the ultimate strength of the cable, vibration will not be a problem. Galloping of conductors has never been observed on lines in the eastern portion of the TVA system. Both the steel tower and wood pole line sections have two overhead ground wires to provide lightning protection. The use of circuit breakers with high speed reclosing relays will clear the majority of the transmission line faults. The TVA owned Fort Loudoun-Roane 161XV transmission line (presently operating as the Fort Loudoun K-33 line) will be looped into the CRBRP. This line is single circuit wood H-frame construction and was designed to conform with the heavy loading strength requirements of the National Electrical Safety Code. The design considerations incorporated into this existing line are identical to those outlined in the discussion of the DOE owned K-31 Fort Loudoun 161KV transmission line. The new line construction, required to complete the CRBRP Roane and CRBRP Fort Loudoun-1 161KV lines will begin where the existing 161KV line crosses under a TVA 500KV line. Thus, the two lines will parallel the 500KV line along the side of Chestnut Ridge for approximately 2.7 miles before turning southwestward and paralleling the Fort Loudoun K-31 line into tne CRDRP Switchyard. At the CRBRP, the K-31 (Reserve AC Power Supply) line will cross over the two power circuits in such a way that phy-sical failure of either power circuit will not endanger the Reserve AC O Power Supply. The loop line structures will be on 75 foot centers with 100 foot separation from the 500KV line. This will minimize the acreage for right of way and also reduce clearing requirements. The 500KV line will provide substantial shielding to the loop line from lightning. The new construction which will be used for this loop connection, will provide adequate separation between the 161KV circuits to ensure that ' loss of one line will not jeopardize the integrity of the other circuit. The single circuit structures will be compact, self-supporting, narrow base towers suitable in strength. These narrow, silhouette structures will com-bine epoxy fiberglass crossarms on a new design stem of structural steel. The foundation will be composed of a precast concrete section made to fit an augered hole. This combination of steel and epoxy fiberglass will ensure minimum maintenance and structural reliabilty for weather element loading. As previously stated, the northwestern end of the K-33 Fort Loudoun 161KV line will be terminated at TVA's Roane 500KV Substation. There are no traasmission lines that cross over the Fort Loudoun-1 CRBRP line and Fort Loudoun-2 CRBRP line that vill connect to the generating switchyard and reserve switchyard, respectively. There are transmission lines which cross the remaining CRBRP lines; however, chere is ro single transmission line that crosses over more than one of the CRBRP transmission lines. fN Amend 63 ( Dec. 1981 8.2-3
All transmission lines which cross the lines to the CRBRP, are designed to meet medium loading requirements of the National Electrical Safety Code (ANSI C2). In addition, design provides for wind loadings of approximately 85 mph winds on bare conductors and vertical loading strength based on approximately one (1) inch of radial ice. These loading con-ditions ensure adequate strength to provide reliability under the worst possible weather conditions encountered on TVA's transmission line system. 8.2.2 Analysis 8.2.2.1 General Analysis The CRBRP Preferred AC Power Supply is designed to provide unin-terrupted AC power to the plant distribution system. In case of a turbine trip or a reactor trip in the absence of an electrical fault, the generator circuit breaker permits automatic isolation of the main generator from the grid without disconnecting the CRBRP Preferred AC Power Supply. The 161KV rigid buses in the generating switchyard and the reserve switchyard provide reliability in the design. Since circuit breakers and disconnect switches to bus-1 are all normally closed, the CRBRP Preferred AC Power Supply is connected to the transmission system through two dif ferent paths. The cir-cuit protective devices reduce the effect of system disturbances by promptly isolating the faulted section. This provides connection of the CRBRP Preferred AC Power Supply to at least one transmission line for most system disturbances. Each 161KV line is individually capable of supplying sufficient power for the startup as well as the safe shutdown of the plant and to maintain the shutdown conditions. The Reserve AC Power Supply is designed to be available within a few cycles after the CRBRP Praferred AC Power Supply becomes unavailable. The 161KV disconnect switches and the circuit breakers are all normally closed so that each reserve station service transferrer is connected to two 161KV transmission lines through two dif ferent patha. This arrangement provides connection of each reserve station service transformer to at least one transmission line for most system disturbances. Each 161KV line for the Reserve AC Power Supply is capable of supplying suf ficient power to the plant distribution system for the startup as well as for the safe shut-down of the plant and to maintain the shutdown conditions. Each reserve sta-tion service transformer is capable of s mplying sufficient power to the Plant distribution system for the safe st.atdown of the plant and to main-tain the shutdown conditions. Compliance with CRBRP General Design Criteria 15 and 16 is discussed in Section 3.1. Compliance with Regulatory Guide 1.32, 1.93 and IEEE Std. 308-74 are discussed below. Regulatory Guide 1.32, Rev. 2 The CRBRP Preferred and the Reserve AC Power Supplies are imme-diate access circuits. Amend 63 Dec. 1981 8.2-4
The CRBRP Preferred AC Power Supply consists of two 161KV transmission lines in the generating switchyard connected to the main power [V ,} transformer. 'In the event of a turbine trip when no electrical fault is pre-sent, the generator circuit breaker will open automatically and disconnect the Plant Power Supply. The Plant AC power distribution system will then be provided with power by the CRBRP Preferred AC Power Supply through the main power transformer without interruption. In the event of non-availability of both the Plant and the CRBRP Preferred AC Pcwer Supplies, the Plant AC distribution system will be transferred to the Reserve AC Pnwer Supply. This transfer is performed within a period of 6 cycles by a fast dead bus transfer scheme as described in Section 8.3.1.1. Both reserve station service transformers are kept energized at all times during plant operation and are available to the Plant AC distribution system within a few cycles. This assures that the specified acceptable design limits are maintained. Regulatory Guide 1.93, Rev. 0 (12/74) The available off-site AC power sources consist of the CRBRP Preferred AC Power Supply and the Reserve AC Power Supply. Each of these two supplies provides two connections to the TVA 161KV grid. The two 161KV grid connections to the reserve station service transformers constitute the required independent off-site power sources. In addition, two 161KV grid connections to the generating switchyard provide an added reliability to off-site power, availab',1 through the main power and the unit station ser-- vice transformers. O Q On-site AC power sources and on-site DC power sources comply with the requirements of CRBRP GDC15 for the availability of electric power sources. Should an LC0 be violated on these power sources, the plant's con-tinued operation will be restricted in accordance with the Regulatory Guide 1.93 recommendations. IEEE Standard 308-1974 The Reserve AC Power Supply provides the two independent circuits of the IEEE Std. 308-1974 " preferred power supply". It connects the TVA 161KV grid to each of the two 4.16KV Class 1E switchgear buses' through the reserve station service transformers. Hence, the safety-related AC distri-bution system has two phys;eally separate and electrically independent sources available from the TVA grid. The CRBRP Preferred and the Reserve AC Power Supplies, each has sufficient capacity to operate the loads applied during a design basis accident. Both the CRBRP Preferred and the Reserve AC Power Supplies are available during normal operation (see Section 16.L9). Amend 63 O Dec. 1981 8.2-5
8.2.2.2 Steady-State and Transient Analyses Results of steady-state studies show that the 161KV off-site power sources of the Reserve AC Power Supply remain a reliable source to supply the Plant electric power distribution system for single contingency conditions including loss of the CRBRP generating unit, loss of one of the largest generating units on the system, loss of one offsite source, or the loss of a critical 500KV transmission facility. Steady-state studies also show that each 161KV line connected to CRBRP is capable of supplying the total Plant power distribution requirements for the startup as well as for the safe shutdown of the plant and to maintain the shutdown conditions. Line flows and bus voltages can be obtained from the following steady state power flow diagrams. Diagram Conditions Figure 8.2-2 Off-site Power Supply - System Normal Figure 8.2-3 Off-site Power Supply - Loss of CRBRP Generation Figure 8.2-4 Off-site Power Supply - Loss of One Cumberland Unit Figure 8.2-5 Off-site Power Supply - Loss of K-31 Line Connection to the Reserve Switchyard Fiqure 8.2-6 Off-site Power Supply - Loss of Fort Loudoun-2 Line Connection to the Reserve Switchyard Results of transient stability studies show that the Reserve AC Power Supply remains a reliable source to supply the plant power distribu-tion system for single contingency cases including loss of the CRBRP unit, loss of a critical 161KV transmission line, or loss of the largest generating unit on the TVA system. Transient stability studies included single contingency conditions consisting of three-phase faults on transmission lines connecting the CRBRP unit into the 161KV transmission system and conditions of three phase faults on transmission lines connecting the Reserve AC Power Supply bus into the 161KV transmission system. These studies included unsuccessful reclosures in which lines were removed from service following disturbances on the system and stuck breaker conditions in which a complete bus sec-tion was disconnected automatically by backup breakers. These cases were considered to be the most severe conditions of postulated transmission disturbances. Results of these studies show that the transmission system remains stable with negligible disturbances to the 161KV off-site power supply. Amend 63 Dec. 1981 8.2-6
The bus voltage and frequency at the respective 161KV off-site power supply bus are indicated on the following diagrams. A h Diagram Conditions Figure 8.2-7 161KV Generating Switchyard Voltage Performance during Loss of CRBRP Unit - No Electrical Fault , Figure 8.2-8 161KV Generating Switchyard Frequency 4 Performance during Loss of CRBRP Unit - No Electrial Fault Figure 8.2-9 161KV Reserve Switchyard Bus Voltage Performance during Loss of . Fort Loudoun-2161KV Line Supplying Off-site Power under Most Severe Transmission 7 Line Disturbance Figure 8.2-10 161KV Reserve Switchyard Bus Frequency Performance during Loss of Fort Loudoun-2161KV Line Supplying Of f-site Power under Most Severe Transmission Line Disturbance The most severe disturbance on the 161KV transmission system affecting the voltage and frequency at the Reserve AC Power Supply is indi-cated on Figures 8.2-9 and 8.2-10. In none of the steady-state or transient stability cases were both 161KV connections to Reserve AC Power Supply incapacitated because of ther-
. mal overloads, voltage variation, or frequency deviations.
4 : Table 8.2-1 provides a history of outages for the lines to be connected to the reserve switchyard. The present operating . record of the - Fort Loudoun-2 K-31 line, which is to be looped into the reserve switchyard to provide two independent off-site sources for the nuclear plant, is 4.61
- outages per 100 year-miles. This compares favorably with 5.17 outages per 100 year-miles for TVA's 8,303 miles of 161KV transmission line in service during 1973. The operating record of each source line supplying .the l reserve switchyard is expected to be as good as or better than the average for the system total.
! 8.2.2.3 Effects of Electrical Faults l A fault bet. ween the main generator circuit breaker, the main power transformer and the unit station service transformers is sensed by one or more differential relays with overlapping zones. These relays trip the l appropriate 161KV circui' 'ber(s), the generator circuit breaker, the generator field circuit .ar and the 13.8KV.and 4.16KV L"eakers con- ' nected to the Plant AC distribution system to isolate the fult. This causes loss of the Plant Power Supply and the CRBRP Prd erred AC Power Supply (see Section 8.2.1.2 for- a description of the Cf.8RP Preferred AC p Power Supply). b Amend 63 Dec. 1981 8.2-7
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The Reserve AC Power Supply is designed to be available within 6 cycles af ter loss of the CRBRP Preferred AC Power Supply (see Section 8.2.2.1 for a description of the Reserve AC Power Supply). Each of the four 161XV transmission lines connected to the generating and reserve switchyards is protected by means of a directional comparison relay system and a back up relay system. The directional com-parison relaying determines the fault location and trips the necessary 161KV breakers to isolate the fault. The back-up relaying will initiate a transfcr-trip of the transmission line breaker at the distant end and the tripping of the local breakers necessary to isolate the line and the faulty breaker. In the evc.it of a turbine trip coupled with a fault in one of the two 161KV transmission lines in the generating switchyard, the faulted line is tripped, the generator circuit breaker is tripped and power is delivered to the Plant AC distribution system via the second 161KV transmission line. In the event of a turbine trip coupled with a fault in both 161KV transmission lines in the generating switchyard, the Plant Power Supply and the CRBRP Preferred AC Power Supply both are lost. The generating switchyard is protected as follows: (See Figure 8.3-1 for ide itification of the 161KV circuit breakers and other switchyard equipment.) a) The plant overall dif ferential relay protects bay-2 bus and equip-ment and will trip circuit breakers 924 and 928 (if closed), b) A fault in bay-1 or bay-3 will be cleared by transmission line relaying which will trip circuit breakers 914 and 934, respec-tively. c) The bus-1 differential relay protects the equipment within the differential zone by tripping all the circuit breakers connected to bus-1. d) A fault in bus-2 (if energized) will be cleared by the transmission line relays which trip circuit breaker 928. The reserve switchyard is protected as follows: a) A fault in bay-6 will be cleared by transmission line relays which will trip circuit breaker 978, associated medium voltage breakers, and transfer-trip the corresponding K-31 breaker. Similarly, a fault on the Fort Loudoun-2 line side of breaker 974, associated redium voltage breakers, and transfer-trip the corresponding Fort Loudoun-2 line breaker. i Amend 63 Dec. 1981 8.2-8
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b) A fault in between breakers 978 and 974 in bay-7 will be cleared by the differential relay which will trip circuit breakers 974 and 978. [') v Each of the two reserve station service transformers is provided with differential, temperature, sudden pressure and breaker failure timing relays. Upon sensing a fault, the relays trip the 974 and 978 switchyard circuit breakers, the corresponding 13.8KV and 4.16KV breakers, actuate the appropriate local fault initiating switch 96G1 or 98G1, and initiate a signal to trip and lock out the appropriate remote K-31 or Fort Loudoun-2 line breaker by a transfer-trip signal. In addition, backup ground fault protection is provided by a relay installed in the neutral circuit of each re;erve station service transformer. Upon sensir:g a fault, these relays will trip circuit breaker 974 and 978 to effectively separate the two reserve station service transformers. After a time delay, the appropriate local fault initiating switch is actuated, and a signal is initiated to trip and lock out the K-31 or the Fort Loudoun-2 line remote breaker by a transfer-trip signal. J Amend 63 Dec. 1981 8.2-9 b tJ
TABLE 8.2-1 FORT LOUDOUN K-31 OUTAGE HISTORY NOTE: This transmission line, ccnnecting with Fort Loudoun, was extended in December 1968 to establish the present Fort Loudoun K-31 connection. No. of Date of Cause of Type of Duration Automatic Year Outages Outage Outage Fault of Outage Reclosing 1969 0 1970 0 1971 0 1972 1 4/11/72 Lightning A[J-Cf-Gnd. Momenta ry Successful 1973 7/10/73 1 ,htning Mome:.' a ry Successful 1 Cf-Gnd. i h O l l l O Amend 63 Dec. 1981 8.2-10 l _ . _ . _ - _ __ _
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i I DATA TO BE SUPPLIED UPON COMPI ETI0ft OF LOAD STUDY co n b EE Pa P Figure 8.2-10.161kV Reserve Switchyard Bus Frequency Performance During Loss of Fort Loudoun 161kV Line S pplying Offsite Power Under Most Severe Transmission Line Disturbance 4 O O O
8.3 ON-SITE POWER SYSTEMS
- 8.3.1 AC Pover Systems 8.3.1.1 Description The on-site power system consists of the following:
a) Non-Class 1E power distribution system which consists of two generally independent load groups (Divisions A and B). Each division is provided with its own:
- power supplies (13.8KV, 4.16KV, 480 volts, 277 volts, 208 volts and 120 volts AC)
- transformers
- cables and raceways 125 volts DC control and instrumentation power multiplexer system for control, alarm and indication 120/208 volts uninterruptible power supplies (UPS) for essential Non-Class IE loads b) Class 1E power distribution system which consists of three independent load groups (Division 1, 2 and 3). Class 1E Divi-sions 1 and 2 provide the two redundant safety related load
(
/"N) groups. Each of the three load groups consists of its own:
power supplies (4.16KV, 480 volts, 277 volts, 208 volts and 120 volts AC) standby (on-site) diesel generator transformers
- cables and raceways
- 125 volts DC control and instrumentation power solid state programmable logic system for control, diesel generator load sequencing, periodic testing, and alarm indi-cations Class 1E Division 3 provides power for Loop 3 decay heat removal system.
13.8KV and 4.16KV Distribution System During normal operation, plant auxiliary power is provided by two (2) 50 percent capacity (50 percent capacity of total plant electrical loads, but 100 percent of loads for one safety division) unit station h
\s service transformers (USSTs) fed from the main generatcr through the 22KV isolated phase bus and the generator circuit breaker.
Amend 63 Dec. 1981 8.3-1
Alternately, the USSTs can be powered from the generating switchyard through the main power transformer and the 22KV isolated phase bus. USSTs will also be used to provide the plant auxiliary power during plant startup. The main generator will be synchronized with the TVA grid at the generator circuit breaker. When the USSTs are not available, the plant auxiliary power will be provided by two (2) 50 percent capacity lh i (50 percent of total plant electrical loads but 100 percent of loads for one safety division) reserve station service transformers (RSSTs) f which are fed from the TVA grid via the Reserve Switchyard. All four transformers (USSTs and RSSTs) will be kept continuously energized during normal plant operation. Refer to Figure 8.3-1 for connections and ratings of the major equip-ment of the Plant AC distribution system. Each medium voltage bus (13.8KV and 4.16KV) cf the Non-Class 1E system has two transferrable incoming supplies. Each medium voltage bus (4.16KV) of the Class 1E system has three incoming supplies. One supply is from one of the two USSTs; the second supply is from one of the two RSSTs. The 13.8KV and 4.16KV switchgear buses distribute power to large and medium size motors and to 480 volt switchgear. 480 Volt Distribution System Power for 480 volt auxiliaries is supplied from unit substation switchgear consisting of 13.8KV/480V or 4.16KV/480V transformers and associated. low voltage switchgear. Each 480 volt switchgear is arranged as an independent radial system with each 480 volt bus fed by its own power transformer. No cross-ties are provided between 480 volt buses. The 480 volt switchgear supplies 460 volt motor loads greater than 100hp and in general equal to or less than 250 hp, motor control cen-ters, and power and control panels of the sodium heat tracing systen. The 480 volt motor control centers feed motor loads greater than 0.33 hp and equal to or less than 100 hp, distribution transformers, motor operated valves and other small loads. 277/480 Volt and 120/208 Volt Distribution System Power to 277 and 120 volt loads is supplied from 277/480 or 120/208 volt distribution panels. These panels are fed from 480 volt motor control centers through 480-277/480 or 480-120/208 volt distribution transformers. Vital (Uninterruptible) AC Power Supply System-Power for loads which must be continuously energized under all plant operating modes is supplied from 120/208 volt distribution panels which are fed from the Vital (uninterruptible) AC Power Supply Systems. Principal elements of Non-Class 1E and Class 1E Uninterruptible AC Power Supply sources are shown in Figure 8.3-2. Amend 63 Dec. 1981 8.3-2
8.3.1.1.1 Standby AC Power Supply The Standby AC Power Supply is a Class 1E system which supplies AC
/N power to the Class 1E and certain essential Non-Class 1E loads when the h Plant AC Power Supply, CRBRP Preferred Power Supply, and Reserve AC Power Supply are not available.
The Standby AC Power Supply consists of three Class 1E diesel generators, each supplying power to its own safety group loads. Safety Divisions 1 and 2 are redundant to each other. The diesel generators are physically and electrically independent of each other. .The Divisions 1 and 2 diesel generators supply power to redundant load groups. The diesel generators are sized in accordance with IEEE Standard 387-1977, su ppl e-mented by Regulatory Guide 1.9, Rev. 2. The total demand during an emergency condition when off-site AC power supplies are unavailable is within the continuous rating of each diesel generator as indicated in Tables 8.3-1A, 8.3-1B and 8.3-1C. Each diesel generator is installed in a separate and independent diesel generator room. These rooms are located in a Seismic Category I structure and are capable of withstanding missiles as described in Section 3.8.4.1.4. Auxiliary equipment, local control boards and excitation cubicles associated with each diesel generator are located in the same room with the diesel generator. Cables for Standby AC Power Supplies will be installed in their own separate division of the Class 1E raceway system. Cables and raceways of the Standby AC Power Supply will be marked in a distinctive manner as described in Section 8.3.1.4. nv The following support systems are those essential auxiliary systems or components required to start and operate the diesel generators,
- a. The Safety-Related 125V DC Power System Each diesel generator is furnished with an independent DC supply from the Safety-Related 125V DC Power System. (Section 8.3.2 describes the 125V Class 1E DC system.)
- b. The Diesel Generator Fuel Oil Storage and Transfer System Fuel is provided for starting during initial operation using a shaft driven pump taking suction from a day tank. Fuel is provided for continuous operation using AC powered fuel transfer pumps taking suction from the underground storage tanks to replenish the day tank fuel supply.
Each diesel generator is furnished with an independent fuel storage and transfer system. For details refer to Section 9.14.1. ,
- c. Diesel Generator Cooling Water System Each diesel generator is furnished with an independent cooling water support system. For details refer to Section 9.14.2.
Amend 63 (O j Dec. 1981 l l l L
- d. The Diesel Generator Starting System Each diesel generator is furnished with two independent and redun-dant air starting systems with individual star ting air compressors, air tanks, and necessary valves and other accessorie- for cranking the engine.
The two starting systems will be independent and urranged so that failure of one will not jeopardize proper operation of the other. For details refer to Section 9.14.3. , e. The Diesel Generator Lubrication System Each diesel generator has a lubrication system integral with the diesel engine. For details refer to Section 9.14.4.
- f. Diesel Generator Ventilation System Room ventilation is not required for starting of the diesel generator. During continued operation under load and during testing, the ventilation system will provide adequate cooling air for proper operation of the local instrumentation, control and other equipment. For details refer to Section 9.6.5.
Operation Each diesel generator will be automatically started upon sensing loss of voltage on the 4.16KV Class 1E bus by undervoltage relays or on an emergency signal as described in Section 8.3.1.1.2. In order to ensure rapid start capability, the engine lube oil and jacket water systems for each engine will be maintained in a preheated (standby) condition at all times, and all essential elements of the system will be continuously maintained. Each diesel generator unit operating under an emergency condition will only be tripped by sensing either of the following conditions (all other protection devices will be bypassed):
- a. Engine overspeed.
- b. Generator differential current.
All diesel generator unit protective devices will remain in force duriag unit testing. Loading of each diesel generator is indicated in Tables 8.3-1A, 8.3-1B and 8.3-1C. The diesel generators will be designed to pro /ide voltage and frequency within limits, as described in Section 8.3.1.2, which ensure proper performance of any of the loads during all possible steady-state or transient loadings. Testing and Inspection The equipment will be tested and inspected at the vendor's facil-ity prior to delivery. The system will also be inspected during installa-tion to confirm that design requirements have been met. Amend 63 Dec. 1981 8.3-4 _w
Initial operational system tests will be performed with components installed and connected to demonstrate that the system operates within p design limits and meets the performance specification, and to verify the Q independence between redue,Jant AC power sources and load groups. After being placed in service, the standby diesel generators and their respective associated supply systems will be inspected and tested periodically to detect any degradation of the system. The preoperational tests and periodic testing after the diesel generator units are placed in service will be performed in accordance with Regulatory Guide 1.108 (Rev. 1, 8/77). Detailed step-by-step procedures will be provided for each test. The procedures will identify those special arrangements or changes in normal system configuration that must be made to put the diesel generator unit under test. Jumpers and other nonstandard configurations or arrangements will not be used subsequent to initial equipment startup testing. The following tests will be performed as a minimum: A. Testing of diesel generator units during the plant preopera-tional test program and at least once every 18 months (during refueling or prolonged plant shutdown) will be performed to: (1) Demonstrate proper startup operation by simulating loss of all AC voltage and demonstrate that the diesel generator unit can start automatically and attain the rated speed (450 RPM) within 10 seconds. Verify that the generator voltage and frequency are at their rated values s./ within 10 seconds after the start signal. (2) Demonstrate proper operation for design-accident-loading sequence to design-load requirements in Tables 8.3-1A, 8.3-1B and 8.3-1C. Verify that at no time during the loading sequence will the frequency and voltage decrease to less than 95% of nominal and 75% of nominal, respec-tively. Verify that the frequency is restored to 98% of nominal and the voltage is restored to 90% of nominal within 4 seconds for each load sequence time interval. (3) Demonstrate full-load-carrying capability for an inter-val of not less than 24 hours, .of which 22 hours will be at a load equivalent to the continuous rating of the diesel generator unit and 2 hours at a load equivalent to the 2 hour rating of the diesel generator unit. Verify that voltage and frequency are maintained at rated values. The test will also verify that the cooling system functions within design limits. Amend 63 Dec. 1981 8.3-5
(4) Demonstrate proper operation during diesel generator unit load shedding, including a test of the loss of the largest single load (1050 hp) or of complete loss of load. Verify that, during recovery from transients resulting from the disconnection of the largest single load and of the complete loss of the continuous rated load, the speed of the diesel generator unit will not exceed 105% of nominal speed. (The overspeed trip set point will be at 110% of nominal speed.) Verify that the generator voltage will not exceed 110% of nominal voltage during and following the load rejection. (5) Demonstrate functional capability at full-load tem-perature conditions by rerunning the test phase outlined in A.(1) and A.(2) above immediately following A.(3) above. (6) Demonstrate the ability to (a) synchronize the diesel generator unit with off-site power while the unit is cor-nected to the emergency load, (b) transfer this load to the offsite power, (c) isolate the diesel generator unit, and (d) restore it to standby status. (7) Switching from one fuel oil supply system to another is not required and therefore not provided, because each diesel generator unit has its own independent fuel oil storage tank sized for a minimum of 7 days operation. (8) Demonstrate that the capability of the diesel generator unit to supply emergency power s,ithin the required time is not impaired during periodic testing under "C" below. (9) During the plant preoperational test program only, demonstrate the required reliability by means of any 69 consecutive valid tests (as defined in Regulatory Guide 1.108, Regulatory Position C.2.e) with no failures with a minimum of 35 tests per diesel generator unit. B. Testing of redundant diesel generator units during normal plant operation will be performed independently (nonconcurrently) to minimize common failure modes resulting from undetected interdependences among diesel generator units. However, during reliability demonstration of diesel generator units during plant preoperational testing and testing subsequent to any plant modification where diesel generator unit interdependence may have been affected or every 10 years (during a plant shutdown), whichever is shorter, a test will be conducted in which redundant units are started simultaneously to help identify certain common failure modes undetected in single diesel generator unit tests. O Amend 63 Dec. 1981 8.3-6
C. Periodic testing of diesel generator units during normal plant operation will be performed to: (1) Demonstrate proper startup and verify that the diesel generator unit can attain rated speed within 10 seconds. Verify that the generator voltage and frequency are at their rated values within 10 seconds after the start signal. This test will also verify that the components of the diesel generator unit required for automatic startup are operable. (2) Demonstrate full-load-carrying capability (continuous rating) for an interval of not less than one hour. The test will also verify that the cooling system functions within design limits. This test will be accomplished by synchronizing the generator with the off-site power and assuming a load at the maximum practical rate. D. Af ter completion of the diesel generator unit reliability demonstration under A.(9) above, the interval for periodic testing under "C" above (on a per diesel generator unit basis) will se no more than 31 days and will depend on demonstrated performance. If more than one failure has occurred in the last 100 tests the test interval will be shortened in accordance with the schedule recommended by the Regulatory Guide 1.108, Regulatory Position C.2.d. The sche-dule will be included in Chapter 16, Technical Specifications. E. Criteria for valid tests and failures for the tests under A.9 and "D" above will be based on the criteria recommended by the Regulatory Guide 1.108, Regulatory Position C.2.e. 8.3.1.1.2 Safety-Related AC Power Distribution System The Safety-Related AC Power Distribution System is a Class 1E system which distributes power to Class 1E equipment that requires AC power. The Safety Related (Class 1E) Distribution System consists of three independent divisions (Divisions 1, 2 & 3). The Divisions 1 and 2 distribute power to the two redundant Class 1E load groups. The Division 3 provides power to the Loop 3 decay heat removal system, the Division 3 PPS, control, instrumentation, al-arms and indication. The power is distributed to the loads at the following voltage levels:
- a. 4.16KV for large and medium sized motor-driven equipment,
- b. 480 volts for motor-driven auxiliaries, het irg and ven-tilation systems, and other miscellaneous loads.
- c. 480/277 volts for lighting and other miscellaneous loads,
- d. 120 volts for control, instrument power, lighting and other miscellaneous loads.
Amend 63 Dec. 1981 8.3-7
The Divisions 1, 2 and 3 are separated into three sets of cables, raceways, components and equipment, each set distributing power to its own load group. The three sets are physically and electrically independent of each other. Each division receives AC power from the Plant Power Supply, the CRBRP Preferred or Reserve AC Power Supplies or the Standby Onsite AC Power Supply. Equipment ratings for the 4.16KV and 480 volt loads on the Safety-Related AC Power Distribution System are indicated in Figure 8.3-3. Power to 4.16KV Class 1E loads is distributed through Class 1E switchgear buses. Power to 480 volt Class 1E loads is distributed from Class 1E 480 volt Unit Substation Switchgear which is supplied from unit substation transformers connected to the 4.16KV Class 1E switchgear buses. Each 480 volt Class 1E switchgear receives power from the 4.16KV switchgear bus of the same load group. The switchgear distributes power directly to Class 1E low voltage motors rated above 100 HP. The 480 volt Class 1E switchgear also distributes power to Class 1E 480 volt motor control centers which contain motor starters or circuit breakers for loads such as small Class 1E motors, heating and ventilation system loads, feeder circuit breakers for vital instrument AC regulating transformers with a rating of 480-120/208V AC, and the 125 volt DC battery chargers. Certain Non-Class 1E loads are connected to the Division 3 Class 1E diesel generator system switchgear via a high impedance transformer iso-lation system as described in Section 8.3.1.2.14. Motor control center loads such as motors are controlled by com-bination units which are installed in the motor control centers. These combination units consist of a starter or contactor for controlling the load and a circuit breaker for fault protection of the feeder cable and the load equipment. Motor loads are provided with overload protection. 120 volt AC control power for each motor control center starter or contactor is supplied from an individual control power transformer. These transformers receive power from the load side of the circuit breaker furnished in each combination starter or contactor. Auxiliary devices required to operate equipment in one load group receive power from distribution panels in the same load group. This arrangement prevents the loss of electrical power in one load group causing loss of equipment in the other load group. All components of the Safety-Related AC Power Distribution System are located in Seismic Category I structures. Each of the two redundant Class 1E 4.16KV switchgear buses is installed in a separate electrical equipment room. The electrical equipment rooms are located in a Seismic Category I structure. The switchgear for Division 3 loads is also located in an electrical area separate from Division 1 and 2 switchgear rooms. Cables for the separate, redundant load groups (Division 1 and 2) of the Safety-Related AC Power Distribution System are installed in separate raceway systems. The independence criteria of the Class 1E Amend 63 Dec. 1981 8.3-8
raceway systems is described in Section 8.3.1.4. Cables and raceways of
/7 the Safety-Related AC Power Distribution System are marked in a distinctive U manner as described in Section 8.3.1.5.
The following suppr,rt systems are those essential components which are required for proper furctioning of the Safety-Related AC Power Distribution System:
- a. The 125 Volt DC Power Supply DC power is required for control of the 4.16KV circuit breakers and 480 volt switchgear circuit breakers. Each group is furnished with an independent DC Supply from the DC Power Supply System as described in Section 8.3.2. DC power is not required to suoport the 480 volt motor control centers.
2
- b. Electrical Equipment Room HVAC Requirements Room ventilation is not required for initial operation of the safety-related electrical equipment. Adequate heating or cooling air is provided for proper functioning of safety-related local instrumentation, protective relays, control devices and other electrical equipment. Each HVAC unit is furnished with Class 1E power from the same division it ser-ves. For details, refer to Section 9.6.
Operation h d When the Main Generator is operating, the Safety-Related AC Power Distribution System receives power from the Plant Power Supply via the i generator circuit breaker and unit station service transformers. In the event of a turbine trip, a reactor trip, a main generator fault, or fault in the isolated phase bus system between the main generator and generator circuit breaker, the generator circuit breaker is automatically tripped. The unit station service transformers will remain connected to the CRBRP Preferred AC Power Supply (161XV generating switchyard) via the main step-up transformer and provide uninterrupted power through the Plant AC Distribution System to the Safety-Related AC Power Distribution System. An electrical fault downstream of the generator circuit breaker will cause the tripping of the associated 161KV circuit breaker (s) located in the generating switchyard and subsequent loss of the power supply from the unit station service transformers. Upon loss of the power supply from the unit station service transformers, the Plant AC Power Distribution System will be automatically connected to the Reserve AC Power Supply as described in Section 8.3.1.1.4. Upon loss of the Reserve AC Power Supply, the undervoltage sensors in the 4.16KV Class 1E switchgear buses sense the loss of power and ini-tiate the following:
- 1. Trip the circuit breakers connecting the Class 1E switchgear buses to the reserve station service transformers.
Amend 63 V Dec. 1981 8.3-9
- 2. Start the diesel generator and close the diesel generator circuit breaker, subject to the permissives in the Standby AC Power Supply.
The diesel generators will also start automatically on an emergency signal. However, if the CRBRP Preferred Power Supply is still available to tne safety-related 4.16KV switchgear bus, each diesel genera-tor breaker will remain open. The required safety-related loads will be sequenced on each Class 1E bus by a diesel generator load sequencer as shown on the diesel generator loading Tables 8.3-1A, 8.3-1B and 8.3-1C. The diesel generators will be shutdown manually by the plant operator in accordance with strict administrative controls. Upon a successful start of the Standby AC Power Supply (diesel generators), voltage at the 4.16KV Class 1E switchgear bus will be restored. This permits automatic sequential loading on the Safety-Related AC Power Distribution System, as required to maintain safe shutdown of the plant. Each load which is required to start automatically will receive its own start signal from the diesel generator sequencer. The required loads will be connected, as shown in Tables 8.3-1A, 8.3-1B and 8.3-1C. Upon loss of the power supply from the unit station service transformers or the reserve station service transformers, the Class 1E 480 volt switchgear will remain connected, unless intentionally tripped. Upon restoration of the voltage, the 480 volt Class 1E switchgear will be auto-matically re-energized. On restoration of the CRBRP Preferred or the Reserve Power Supply, the 4.16KV Class 1E switchgear bus will be manually synchronized with one of these available power supplies and the incoming 4.16KV circuit breaker of the diesel generator will be opened and the diesel generator will be stopped by the operator under strict administrative controls. Circuit Protection Each supply circuit breaker of the Safety-Related AC Power Distribution System is protected for any of the following conditions:
- a. Overcurrent
- b. Ground fault
- c. Transformer differential overcurrent
- d. Input tenninal undervoltage The Class 1E diesel generators are each protected against the following:
- 1) Engine overspeed
- 2) Low engine oil pressure
- 3) Generator differential overcurrent
- 4) Generator overcurrent Amend 63 8.3-10 Dec. 1981
- 5) Raverse power flow to generator
- 6) Generator loss of -field
- 7) Generator Ground overvoltage
! 8) Generator field ground Upon detection of one of.the above conditions when the diesel generator is running under test with normal plant conditions, the lockout relay will operate, which will trip the diesel generator incoming bus cir-cuit breaker. After automatic start under a plant emergency condition, all protective functions mentioned above will be bypassed except for the following:
- 1) Generator differential overcurrent
- 2) Engine overspeed
- The diesel generator circuit breaker is . included 'in the differen-tial protective zone of the diesel generator. The diesel generator will be automatically tripped for a three phase fault or phase-to-phase fault on the generator or on the generator supply feeder. It will also be tripped automatically in case of a line-to-ground fault when the diesel generator is operating in test mode.
The design of the bypass circuitry will satisfy the requirements of IEEE Std. 279-1971 at the diesel generator system level and will include the capability- for (1) testing the. status and operability of the bypass [,] circuits, (2) alarming ~in the Control Room abnormal values of the bypass U parameters, and (3) manually resetting of the trip bypass function. The following types of protection are provided for the Safety-Related AC Power Distribution System: 4.16KV Switchgear -
- 1. Each 4.16KV Class 1E switchgear bus and the incoming lines are provided with undervoltage relays to detect an under-voltage condition. The relays initiate tripping of the cir-cuit breakers connecting the Class 1E switchgear to the off-site power sources and automatic start of diesel genera-tors.
- 2. In addition to the undervoltage relays provided to detect loss of off-site power to the safety buses, a second level of undervoltage protection with time delay is provided to pro-tect the Class 1E equipment against sustained degraded -
voltage conditions of off-site power supplies. This second level of voltage protection will satisfy'the following
- i. criteria:
Amend 63 8.3-11 Dec. 1981 k (
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f a) The selection of undervoltage and time delay setpoints will be determined from an analysis of the voltage requirements of the safety related loads at all Standby On-site System distribution levels, b) Two separate time delays will be selected for the second level of undervoltage protection based on the following conditions:
- 1) The first time delay will be of a duration that establishes the existence of a sustained degraded voltage condition (i.e., something longer than a.
motor starting transient). Following this delay, an alarm in the Control Room will alert the opera-tor to the degraded condition. The subsequunt occurrence of an emergency signal will immrdiately separate the Class 1E distribution system from the off-site power system.
- 2) The second time delay will be of a limited duration such that the permanently connected Class 1E loads will not be damaged. Following this delay, if the operator has failed to restore adequate voltages, the Class IE distribution system will automatically be separated from the off-site power system.
c) The voltage sensors will be designed to satisfy the following applicable requirements derived from IEEE Std. 279-1971, " Criteria for Protection Systems for Nuclear Power Generating Stations".
- 1) Class 1E equipment will be utilized and will be physically located at and electrically connected to the Class 1E switchgear;
- 2) An independent scheme will be provided for each division of the Class 1E power system;
- 3) The undervoltage protection will include coin-cidence logic on a per bus basis to preclude spurious trips of the off-site power source;
- 4) The voltage sensors will automatically initiate the disconnection of off-site oower sources whenever the voltage set point and time delay limits have been exceeded;
- 5) Capabil;ty for test and calibration during power operation will be provided.
- 6) Annunciation will be provided in the Control Room for any bypasses incorporated in the design.
Amend 63 O 8.3-12 Dec. 1981
d) The Class 1E bus load shedding scheme will automatically prevent shedding during sequencing of the emergency loads to the bus. The load shedding feature will, however, be reinstated upon completion of the load w/ sequencing action. The technical specifications will include a test requirement to demonstrate the operabi-lity of the automatic bypass and resinstatement features at least once per 18 months during shutdown. e) The voltage levels at the safety-related buses will be optimized for the maximum and minimum load conditions
- - that are expected throughout the anticipated range of voltage variations of the off-site power sources by appropriate adjustment of the voltage tap settings of the intervening transformers. The tap settings selected will be based on an analysis of the voltage at the ter-minals of the Class 1E loads. The analyses performed to determine the minimum operating voltages will typically consider maximum unit steady state and transient loads for events such as a unit trip, startup or shutdown; with the off-site power supply (grid) at minimum antici-pated voltage and only the off-site source being con-sidered available. Maximum voltages will be analyzed with the off-site power supply (grid) at maximum expected voltage concurrent with minimum unit loads (e.g. shut-down, refueling). A separate set of the above analyses will be performed for each available connection to the off-site power supply.
(o
) f) The analytical techniques and assumptions used in the voltage analyses cited above will be verified by actual measurement. The verification and test will be per-formed prior to inital full-power reactor operation on all sources of off-site power by:
- 1) loading the station distribution buses, including
- all Class IE buses down to the 120/208 volt level, to at least 30%;
- 2) record the existing grid and Class IE bus voltage and bus loading down to the 120/208 volt level at steady state co 'itions and during the starting of both a large Ciass 1E and Non-Class 1E motor (not concurrently);
- 3) using the analytical techniques and assumptions of 4 the previous voltage analyses cited above, and the measured ' existing grid voltage and bus loading con-ditions recorded during conduct of the test, a new set of voltages for all the Class IE buses down to the 120/208 volt level will be established.
The voltage sensors will be designed to satisfy the applicable requirements of IEEE Std. 279-1971. b(/ Amend 63 8.3-13 Dec. 1981
The Technical Specifications, Chapter 16, will include limiting condition for operation, surveillance require-ments, trip set points with minimum and maximum limits, and allowable values for the second-level voltage pro-tection sensors and associated time delay devices.
- 3. Each radial feeder into and out of the 4.16KV Class 1E switchgear buses is provided with phase and ground over-current protection. Motor protection is provided by relays that alarm in the Control Room on moderate overloads and trip on short circuit and locked rotor conditions.
- 4. When the diesel generator is supplying rwer to maintain safe shutdown of the plant, a line-to-ground fault on the 4.16KV Class 1E bus will be annunciated in the Control Room. No tripping is provided for this situation as the diesel genera-tor grounding system is designed as a high resistance grounding system. The neutral of the generator is grounded through a single distribution transformer. A resistance is connected to the secondary winding of this transformer. The magnitude of the line-to-ground fault current will be limited to a very low value, which will not affect the safe operation of the diesel generator unit. Since possibility of damage to the equipment is minimized, continuity of service can be maintained.
- 5. Operation of a protective relay or the tripping of a 4.16KV circuit breaker will be annunciated in the Control Room.
480 Volt Switchgear
- 1. Each 480 volt switchgear bus is provided with an under-voltage relay to detect an undervoltage condition.
- 2. Each 480 volt switchgear circuit breaker is equipped with solid state trip devices for overcurrent and short circuit fault protection.
- 3. Operation of the undervoltage relay and tripping of the 480 volt circuit breakers are annunciated in the Control Room.
480 Volt Motor Control Centers Molded case circuit breakers will provide time overcurrent and/or instantaneous short circuit protection for all connected loads. For motor circuits, the molded case circuit breakers will be equipped with an instan-taneous trip only. Motor overload protection will be provided by heater-element trip units in the motor starter. Class 1E motors for the motor operated valves are also provided with thermal overload protec'.lon which will be bypassed under plant emergency conditions. Testing and Inspection The equipment will be inspected and tested at the vendor's facili-ties prior to delivery. The equipment will also be inspected during installation to confirm that the design requirements have been met. When Amend 63 8.3-14 Dec. 1981
installation is complete, pre-cperational equipment tests and inspections will be performed. h) b' Initial pre-operational tests will be performed with equipment and components installed and connected to demonstrate that the equipment is within design limits and the system meets performance specifications. This test will also demonstrate that loss of the Plant Power Supply and Offsite (CRBRP Preferred and Reserve Power) AC power supplies can be detected. Periodic equipment tests will be performed to detect any degrada-tion of the syster: and to demonstrate the capability of equipment which is normally de-energized. Periodic tests on the Class 1E 4 RKV switchgear and 480 volt switchgear circuit breakers will be pe, formed by utilizing the following test methods:
- a. The operability of circuit breakers carrying current under normal plant operation will be demonstrated by their perfor-mance in supplying power. In addition, the circuit breakers will be tested in " Test" position at regular intervals.
During this test, the proper operation of the circuit breakers and the control circuits will be verified,
- b. Testing of circuit breakers of the standby equipment will be performed by racking the circuit breakers in the " Test" posi-tion. In the " Test" position, the main contacts of the cir-cuit breaker are disconnected, but the auxiliary and the control circuits are maintained. This facilitates functional O)
(, tests of the circuit breaker and its control circuit,
- c. When a safety-related circuit breaker is in the " Test" posi-tion, an indication is provided in the Control Room regarding its status. In the case an emergency signal is generated during the testing, the circuit breaker cannot be closed .
immediately. It can only be closed when the circuit breaker is put in the fully racked-in position by the operator.
- d. An operating procedure will also be applied to verify the availability of the redundant division of the safety-related equipment before the safety-related breaker is racked into
" Test" position.
Periodic tests of the transfer of power between the CRBRP Prefered Power Supply and Reserve AC Power Supplies will be performed during pro-longed plant shutdown or during refueling to demonstrate that:
- a. Sensors can properly detect loss of the CRBRP Preferred Power Supply and the Reserve AC Power Supplies,
- b. Components required to accomplish the transfer from the CRBRP Preferred Power Supply to the Reserve AC Power Supply are operable.
O C) Amend 63 Dec. 1981 8.3-15
- c. Components required to accomplish the transfer from the Reserve AC Power Supply to the Standby On-Site AC Power Supply are operable,
- d. Components required to accomplish the transfer from the Off-site Power Supply (simulating the unavailability of the of f-site AC power supplies) to the On-Site Standby AC Power Supply are operable,
- e. Instruments and protective relays are properly set and operating correctly.
Solid State Programmable Logic System (SSPLS)
. The SSPLS is a Class 1E System.
. The SSPLS controls and actuates safety-related, Class 1E equipment of the CRBRP. The types of equipment controlled are circuit breakers, reversing and non-reversing motor starters and solenoid valves.
. The SSPLS replaces conventional electromechanical relays with solid state alectronic logic.
. The SSPLS cor.sists of three Class 1E systems which are physi-cally separated and electrically independent.
. SSPLS functions are performed in two types of cabinets; a logic cabinet (which contains the control logic, signal con-ditioning, auxiliary circuits and power supplies) and field termination cabinets (which contain field output relays and field wiring terminal blocks).
. The paired SSPLS cabinets are strategically located in dif-ferent buildings of the plant with their associated equipment.
. Operator control functions interface with the SSPLS from Control Room panels or Local Stations.
. The diesel generator load sequencers are part of the SSPLS.
8.3.1.1.2.1 Division 3 Power Distribution System The Division 3 Power Distribution System is a Class 1E system which distributes power to Loop 3 Primary Heat Transport System (PHTS) and Intermediate Heat Transport System (IHTS) Pony motors and Protected Air Cooled Condenser (PACC) blowers, and a Class 1E, Division 3, 120/208V Vital AC power distribution bus as indicated in Figure 8.3-2. Cables ef the Division 3 Power Supply are separated from cables of the remaining Class 1E Plant AC Power Supplies by routing them in conduits or cable trays in separate fire hazard areas. Amend 63 Dec. 1981 8.3-16
All components of the Division 3 Power Distribution System are located in Seismic Category I structures, h) N/ Cables and raceways of the Division 3 Power Supply System are marked in a distinctive manner as described in Section 8.3.1.5. Circuit Protection Each supply circuit breaker of the Division 3 Power System is protected similarly to Divisions 1 and 2 system power distribution. 480 Volt Motor Control Centers Molded case circuit breakers will provide time overcurrent and/or instantaneous short circuit protection for all connected loads. For motor circuits, the molded case circuit breakers will be equipped with instan-taneous trip only. Motor overload protection will be provided by heater-element trip units in the motor starter. Testing and Inspection The equipment will be inspected and tested at the vendor's facili-ties. The equipment will also be inspected during installation to confirm that the design requirements have been net. When installation is complete, preoperational equipment tests and inspections will be performed. Initial pre-operational tests will be performed with equipment and components installed and connected to demonstrate that the equipment is within design limits and the system meets performance specifications. pb Periodic equipment tests will be performed to detect any degrada-tion of the system and to demonstrate the capability of equipment which is normally de-energized. 8.3.1.1.3 Plant Power Supply The Plant Power Supply generates and delivers AC power to the TVA 161KV grid. In addition, the Plant Power Supply is the normal source of AC power for the Class IL and Non-Class 1E auxiliary loads when the plant is operating. l The Plant Power Supply includes the main generator, the generator circuit breaker, the interconnecting isolated phase bus, the two unit sta-l tions service transformers and associated power distribution system equip-I ment. The main generator is connected to the main power transformer and unit station service transformers through the generator circuit breaker. Voltage from the main generator is stepped up by the main power trans-former. Power is supplied to the 161KV transmission system as described in Section 8.2. When the plant is operating, power will be supplied from the main generator to the Plant AC Distribution System through the generator circuit breaker and the unit station service transformers. Connections and ratings of major equipment for the Plant Power Supply are shown in Figure 8.3-1. Amend 63 Dec. 1981 8.3-17
8.3.1.1.4 Plant AC Distribution System The Plant AC Distribution System distributes power from the Plant Power Supply or the off-site AC power supplies to all facility auxiliaries that require AC power. Power is distributed to auxiliary loads at four voltage levels: A. 13.8KV and 4.16KV for large and medium size motors for motor driven auxiliaries. B. 480 volt for motor driven auxiliaries, lighting, ventilation systems, and other miscellaneous loads. C. 480/277 volt for lighting and sodium heat tracing loads. D. 120/208 volt for control, alarm, instrument power, lighting, and other miscellaneous loads. The Non-Class 1E Plant AC Distribution System is a two division distribution system, each division has its own equipment, components, raceway and cables, each distributing power to its own load group. Connections and ratings of major equipment of Plant AC Distribution System are shown in Figure 8.3-1. Power to the 13.8KV loads is distributed from the 13.8KV switchgear buses which are supplied from the 13.8KV windings of the two unit station service transformers. The 13.8KV switchgear buses can also l receive power from the 13.8KV windings of the two reserve station service transformers. Power to the 4.16KV loads is distributed from the 4.16KV switchgear buses which are supplied from the 4.16KV windings of the two unit station service transformers. The 4.16KV buses can also receive power from the 4.16KV windings of the two reserve station service transformers.
/
The 13.8KV and 4.16KV switchgear buses distribute power to large and medium size motors and to 480 volt switchgear through transformers. Power to the 480 volt loads is distributed from 480 volt switchgear. The Class 1E switchgear are supplied through the Safety-Related AC Distribution System. The 480V switchgear distribute power to larger 480 volt motors and to motor control centers. Operation When the unit is operating, the Plant AC Distribution System receives power from the main generator through the generator circuit breaker and the two 507, capacity (100% capacity for one safety-related Division's loads) unit station service transformers. In the event of a turbine or reactor trip, main generator fault or a fault in the isolated phase bus system between the main generator and generator circuit breaker, the generator circuit breaker will automatically open. The CRBRP Preferred ! Amend 63 Dec. 1981 8.3-18
3 AC Power Supply will remain connected and provide uninterrupted power to the Plant AC Distribution System through the main power transformer and the
~
unit station service transformers. An electrical fault downstream of the generator circuit breaker will cause tripping of the 161KV circuit breakers V in the generating switchyard. This will result in the loss of the power supply from the unit station service transformers. Similarly, an event which trips the turbine or reactor concurrent with the loss of CRBRP Preferred Offsite Power from the generating switchyard will also result in the loss of the power supply from the unit station service transformers. Upon loss of the power supply from the unit station service trans-formers, undervoltage sensors at each 13.8KV and 4.16KV switchgear bus will i detect the loss of power and initiate the following: A. Trip the supply circuit breakers from the unit station service transformers. B. Close the Reserve AC Power Supply circuit breakers from the twc 50 percent capacity reserve station service transformers by means of a fast dead bus transfer scheme. Provision is included in the design for testing the transfer of power between the unit station service transformers and the reserve sta-tion service transformers. These tests are performed during prolonged plant shutdown periods by simulating loss of the AC power suply from the unit station service transformers as described in Section 8.3.1.1~.2. 8.3.1.1.5 120/208 Volt Vital (Uninterruptible) AC Power System The 120/208 volt Vital (Uninterruptible) AC Power System is a - Class 1E system which is required to supply AC power to the Plant Protection System (PPS) controls, alarm and indication and other Class 1E loads for safe shutdown of the plant. The Plant Protection System (PPS), described in Chapter 7., generates signals to actuate reactor trip, and performs other supporting functions in the event of an emergency condition. i The system is divided into three separate and independent load groups (Divisions 1, 2 and 3), each receiving AC power from a separate inverter through a static transfer switch. Connections for the 120/208 I volt Vital AC Power System are shown in Figure 8.3-2. The normal source of power for the Vital AC Power Distribution i buses are the inverters which are supplied from their associated division , DC power supplies described in Section 8.3.2. - 1 I Each 120/208 volt Vital AC Power System Distribution bus can also , receive power from a Class IE 480 volt motor control center which serves as a backup power source. Each of the distribution buses is connected to this motor control center through a static transfer switch and 480-120/208V AC l regulating transformer. . Failure of an inverter or its DC power source is g -
- sensed and the associated distribution bus is transferred automatically by" '
the static transfer switch to the backup transformer supplied by the Class 1E 480 volt motor control center. The transfer is accomplished at high ' 4 speed and does not degrade the performance of control and instrumentation - eQ loads. -s l () 7 mend 63 Dec. 1981 8.3-19 N _ l
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- r Pchr for the svitit AC loads'is distributed from the three vital AC dist[ilation buses through distributi_on panels. i Equipment'in each of the three separate load groups of the 120/208
' (1 volt Vital AC Power System (inverters, static transfer switches, distribu-tion buses, distribution panels and backup transformers) are installed in
;ll Seismic Category I structures. Cables for the PPS are installed in Class s 1E raceways in accordance with PPS separation requirements described in Section 8.3.1.4. Cables and raceways of the' Class 1E system are marked in a distinctive manner as described in 8.3.1.5.
The following types of prot'ective devices are used: A. 120/208 Volt Vital 'AC Inverter Supply
- 1. The DC supply feeder to each iaverter is protected by a
, power circuit breakeryhich operates without external control. The circuit breaker is equipped with a thermal magnetic trip device which provides fault protection for the circuit.'-
- 2. Each inverter is provided with an incoming circuit breaker equipped with a magnetic trip device to provide protection against internal fault. In addition, a current limiter is provided in the inverter output cir-cuit to protect the inverter against overloads and to limit fault current contribution to external faults.
B. 480-120/208 Volt AC Suoply Feeders Each backup 480-120/208 Volt AC supply feeder to the 120/208 volt Vital AC ~ ^ System is protected by a molded case cir-cuit breaker 'perates without external control . The circuit brea. ., equipped with a thermal and magnetic trip device which provides short circuit and overload protection for the circuit. C. Vital AC Distribution Bus Each feeder from a Vital AC distribution bus to a distribu-tion panel is protected by a fuse. In addition, each inverter is equipped with an undervoltage relay to annunciate a low voltage condition on the Vital AC bus. D. Feeders from Distribution Panels The outgoing feeders from each distribution panel are pro-tected by fuses. , The protection system of the 120/208 volt Vital AC Power System is analyzed to ensure tnat the various adjustable devices are selective in their operation. Amend 63 3 Dec. 1981 8.3-20 s t e
l 1 Testing and_ Inspection The equipment is inspected and tested at the vendor's facilities.
/)
(m / - The system is also inspected during installation. When the installation is coniplete pre-operational equipment tests and inspections are performed to
, . demonstrate that:
y A. Components are correct and properly mounted. L- ~A E. Connections are correct and the circuits are continuous. s C; , Components are operational. D. Instruments and protective devices are properly calibrated
,, and adjusted.
]j The initial system tests will also demonstrate that while supplied by the DC Power System or the backup 480 volt motor control center, the 120/208 volt Vital AC Power System can supply power to the design load as
. j required.
~
Periodic tests will be performed to detect any deterioration of the equipment and to demonstrate the capability of equipment which is nor-
- mally energized.
A manual bypass switch is provided to facilitate maintenance and
- ? testing of each static transfer switch and the inverter on a periodic
# basis. By using the bypass switch, the static transfer switch, and the inverter is isolated and taken out of service without power interruption.
O Oal'y one inverter and static transfer switch will be tested at a time to ensure that any pcstulated failure of the components during test will result in the loss of only one vital; bus.
~
In the unlikely event that an accident signal is generated during the te:t and if vital AC power from the bus under test is lost to the PPS, vital' AC power from either of the , remaining two buses enables the PPS to th rtorm its function. Loss of two vital buses would cause the PPS to trip the Plant. 8.3.1.1.6 Remote Multiplexing System (RMS) 6
. The RMC is a Non-Class 1E system.
. The RMS is used as a wire-repiecer. Signals enter the RMS,
\ are converted to a digital data stream and replicated (under S control of a Central Control Unit)'at a predetermined multiplexer (field or Control Room) for presentation to logic panels for control purposes or at the main control panel (or local panel) for display or feedback inforeation.
. Field Multiplexers (FMs) are located throughout the plant for interfacing field signals.
Amend 63 O 8.3-21 Dec. 1981 s - M _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ ]
. are located in the Main Control Room Room Multiplexers (CRMs)h for interfacing wit Control Room signals.
. RMS functions are performed in two types of cabinets; an electronics cabinet (which contains signal conditions, modems, common iogic and power supplies), and termination cabinets (which contain the field wiring terminal blocks).
. Two separate and independent RMS divisions are provided, (Non-Class 1E Division A and Non-Class 1E Division B). Each division uses redundant data transmission cables carrying time multiplexed signals between plant instrumentation alarm and control signals.
8.3.1.1.7 Motors The following criteria will be used in sizing and selection of motors for safety-related loads: a) Motor Size Motor size will be greater than the maximum horsepower required by the driven load under all operating conditions. b) Starting Voltage Motors will be designed to start and accelerate their loads with 70 percent terminal voltage. This starting voltage will be consistent with the diesel generator limits. c) Insulation Proper winding insulation will be selected for the spe-cific environmental condition where the motor will be used. d) Temperature Monitoring Large motors (250hp or larger) will be provided with thennocouples at each bearing. Motors 1000hp or larger will be provided with RTD's .n the stator winding. All motors (irrespective of size) driving ASME code pumps will have bearing temperature determination. 8.3.1.2 Analysis The plant power systems are in compliance with CRBRP General Design Criteria 15 and 16 as described in Section 3.1. On-site AC Power Systems are discussed below in regard to conformance with NRC Regulatory Guides 1.6, 1.9, 1.22, 1.29, 1.30, 1.32, 1.40, 1.41, 1.47, 1.53, 1.63, 1.68, 1.73, 1.75, 1.89, 1.93, 1.100, 1.106, 1.108, 1.118, 1.131 and IEEE Standards 308-1974, 317-1976, 323-1974, 334-19/?, 383-1974, 384-1974 and 397-1977. Amend 63 Dec. 1981 8.3-22
J r 8.3.1.2.1 NRC Regulatory Guide 1.6, Rev. 0 (3/71) The Class 1E safety-related loads are physically and electrically
' separated into three load groups (Divisions 1, 2 and 3) such that loss of l'. any one group will not prevent safe shutdown of the plant. Class 1E divi-sions 1 and 2 provide the two redundant load groups while Division 3 provides power to. Loop 3 decay heat removal system.
1 ! Each AC load group will have connections to the CRBRP Preferred Power Supply, Reserve Power Supply and a Standby On-site AC Power Source.
- The Standby On-site AC Power source will have no automatic connection to any other redundant load group.
, When operating from the Standby On-site sources, redundant load groups and the redundant Standby On-site sources will be independent of each , other as follows: ' I a. The Standby On-site source of one Class 1E load group will not [ be automatically paralleled with the ftandby On-site source of another Class 1E load group under normal or emergency con-ditions.
- b. No provisions exist for automatically connecting one Class 1E j load group to another Class 1E load group. "
l c. No provisions exist for automatically transferring loads between l redundant Class 1E power sources.
- d. Manually connecting redundant load groups together will require at least one interlock to prevent an operator error
.O that would parallel such Standby On-site power sources.
l Each Diesel Generator unit consists of one diesel engine, one ! generator and required accessories. i The Standby On-site Power Sapply network has a provision to manually cross-connect the 4.16KV buses of the Division 1 and 2 power supplies in case of an extreme emergency. This connection will be put into l service thiough strict administrative controls and must satisfy the l following prerequisites: j a) There shall be a total loss of off-site power. b) One of the two redundant diesel generators failed to start and it is determined to be inoperable. i c) Critical safety-related loads associated with the operative diesel generator have failed and become unavailable. 4 If the above prerequisites are met, loads of either redundant Division 1 or 2 can be connected to the diesel generator of the other divi-sion for . safe shutdown of the plant and to maintain the plant in a safe shutdown condition. Key and electrical interlocks and administrative controls will be O provided to ensure: Amend 62 Dec. 1981 ] 8.3-23 i
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The two standby power supplies will never be paralled.
- The breakers for the cross connection are physically not in place and are located in locked compartments separate from the operative switchgear compartments.
There will be an alarm in the Control Room when either or both tie breakers are in the operating switchgear compartment (s). The connection will be disabled if any one of the off-site power supplies or the disabled diesel generator becomes available. See Figure 8.3-3 for details. 8.3.1.2.2 NRC Regulatory Guide 1.9, Rev. 1 (11/78) Diesel Generator units are designed, qualified and tested in accordance with IEEE Std. 387-1977 supplemented by Regulatory Guide 1.9 recommendations as discussed below: Each Diesel Generator unit has a continuous load rating (as defined in Section 3.7.1 of IEEE Std. 387) greater than the sum of the conservatively estimated loads needed to be powered by that unit at any one time. For mechanical equipment such as pumps, the electric motor drive ratings are calculated using conservative estimates of performance characteristics, e.g., pump runout con-ditions and motor efficiencies of 90 percent or less and power factors of 85 percent or less. The predicted loads will not exceed the short-time rating (as de-fined in Ser tion 3.7.2 of IEEE Std. 387) of the Diesel Generator unit. In conjunction with Section 5.1.2 of IEEE Std. 387, each Diesel Generator unit is capable of starting and accelerating to rated speed, in the required sequence, all the needed Class 1E loads as indicated in Tables 8.3-1A, 8.3-1B and 8.3-1C. The Diesel Generator unit design is such that at no time during the loading sequence will the frequency and voltage detrease to less than 95 percent of nominal and 75 percent of nominal, respectively. Voltage will de restored to within 10 percent of nominal and fre-quency will be restored to withia 2 percent of nominal in less than 4 seconds for each load sequence time interval. Curing reco-very from transients caused by step load increases or resulting from the disconnection of the largest single load (1050 HP) or of the complete loss of the continuous rated load, the speed of the Die ;el Generator unit will not exceed the nominal speed plus 75 percent of the difference between nominal speed and the overspeed trip set point or 115 percent of nominal, whichever is lower. In Section 5.4 of IEEE Std. 387, the qualification testing requirements of IEEE Std. 323 are u;ed subject to the regulatory position of Regulatcry Guide 1.89. (See Section 3.10 for seismic design criteria and 3.11 for envir-onmental qualification criteria ) Amend 63 8.3-24 Dec. 1981
In conjunction with Section 5.5 of IEEE Std. 387, each Diesel Generator unit is designed to be testable during operation of the plant as well as while the plant is Aut down. The design inclu-des provisions so that the testing of Oe units will simulate the (^') V parameters of operation, outlined in Reg.latory Guide 1.108, that would be expected if actual demand were to be placed on the system. Testability is considered in the selection and location of instru-mentation sensors and critical components (e.g., governor, starting system components) and the overall design includes status indication and alarm features. Instrumentation sensors are readily accessible and, where practicable, designed so that their inspection and calibration can be verified in place. In conjunction with Section 5.6.2.2 of IEEE Std. 387, each Diesel Generator unit is protected against abnormal conditions as described in Section 8.3.1.1.2. After automatic start under a plant emergency condition, all protection circuits will be bypassed except the generator differential overcurrent and encine overspeed protection circuits. In conjunction with Section 5.6.3.1 of IEEE Std. 387, in order to facilitate trouble diagnosis, each Diesel Generator unit sur-veillance system indicates which of the Diesel Generator protec-tive trips is activated first. In Section 6.3 of IEEE Std. 387, the requirements of IEEE 344-1975 for seismic analysis or seismic testing by equipment manufacturers p y is used subject to the regulatory position of Regulatory Guide 1.100. The option indicated by "may" in Section 6.3.2(5)(c) of IEEE Std. 387 is treated as a requirement.
- Section 6.5 and Section 6.6 of IEEE Std. 387 are supplemented by Regulatory Guide 1.108 as described in Section 8.3.1.1.1.
In Section 6.3.1 of IEEE Std. 387, the order of sequence of load tests described in parts (1) and (2) is as follows: Load equal to the continuous rating will be applied for the time requireo to reach engine temperature equilibrium, at which time, the rated short-time load is applied for a period of 2 hours. Immediately , following the 2-hour short-time load test, load equal to the con-tinuous rating will be applied for 22 hours. 8.3.1.2.3 NRC Regulatory Guide 1.22, Rev. 0 (2/72) Design of the plant electrical power system will permit Class 1E components, which are part of Plant Protection Systems, actuation de! ices, l auxiliary supporting systems, or actuated equipment, to be periodically tested to verify satisfactory protective device / system actuation. Components will be designed to permit testing of the actuation devices both during reactor operation and routinely, when the reactor is shutdown. Each of the Regulatory Guide recommendations for testing, testing methods, 9 system response to bona-fide accident signal (s), and reliability of (d equipment not tested during reactor operation will be implemented. Amend 63 Dec. 1981 8.3-25
8.3.1.2.4 NRC Regulatory Guide 1.29, Rev. 3 (9/78) The Class 1E Electric Systems, including the auxiliary systems for the Onsite Electric Power Supplies, that provide the Class 1E electric power needed for functioning of nuclear safety related equipment are designated as Seismic Category I. All electric devices and circuitry involved in generating signals that initiate protective action are designed as Class 1E. All electrical equipment in the Control Room is designed as Seismic Category I. Those portions of structures, systems or components whose con-tinued function is not required but whose failure could reduce the func-tioning of any nuclear safety related equipment to an unacceptable safety level will be designed and constructed so that the SSE would not cause such a fail ure. Seismic Category I design requirements will exter.d to the first seismic restraint beyond the defined boundaries. Those portions of struc-tures, systems, or components which for... interfaces between Seismic Category I and ncn-Sei:mic Category I features will be designed to Seismic Category I requirements. For seismic design classifications, refer to Section 3.2.1. 8.3 1.2.5 NRC Regulatory Guide 1.30, Rev. 0 (8/72) The Quality Assurance requirements for the installation, inspec-tion and testing of instrumentation and electrical equipment during the plant construction, are those included in ANSI N45.2.4 supplemented by Regulatory Guide 1.30 as follows: ANSI N45.2.4 will be used in conjunction with ANSI N45.2-1977. ANSI N45.2.4 requirements will be considered applicable for the installation, inspection and testing of instrumentation and electric equip-ment during the plant operatim. 8.3.1.2.6 NRC Regulatory Guide 1.32, Rev. 2 (2/77) The electrical separation and independence of redundant (Divison! I and 2) and Division 3 Standby AC Power Supplies conform to IEEE Standard 308-1974 supplemented by Regulatory Guide 1.32 as follows: Electrical independence between redundant Standby AC Power Supplies will be in accordance with Regulatory Guide 1.6 as described in Section 8.3.1.2.1. Physical independence between redundant Standby AC Power Supplies will be in accordance with IEEE Standard 384-1974 supplemented by Regulatory Guide 1.75 as described in Section 8.3.1.2.14. Amend 63 Dec. 1981 8.3-26
The selection of the diesel generator capacities will be made in accordance with Regulatory Guide 1.9 as described in Section 8.3.1.2.2. 8.3.1.2.7 NRC Regulatory Guide 1.40, Rev. 0 (3/73) Class IE motors in Heat Transport System (HTS) are the only Class 1E motors which are located inside the containment. Where test programs are required in the Liquid Metal Fast Breeder Reactor (LMFBR) design to verify the adequacy of specific design features in lieu of other verifying processes, these test programs will include qualification tests on proto-type continuous-duty Class 1E motors installed inside the containment. The procedure for conducting these qualification tests are those specified by IEEE Std. 334-1974. When these qualification tests are used, they vill be in agreement with Regulatory Guide 1.40, as follows:
- 1. A Liquid Metal Fast Breeder Reactor (LMFBR) auxiliary equip-ment that will be part of the installed motor assembly will be qualified in accordance with IEEE Std. 334-1974 to the extent applicable.
- 2. The qualification tests will simulate as closely as prac-ticable those design basis events which:
- a. Require the motor to either drive equipment which miti-gates the consequences of the event or provide auxiliary support to such equipment, and;
- b. Affect operation of the motor's auxiliary equipment.
8.3.1.2.8 NRC Regulatory Guide 1.41, Rev. 0 (3/73) Preoperational tests will be performed to verify the independence of the redundant Standby AC Power Sources and of the Division 3 Standby AC Power Sources and between the redundant load groups described in Section 8.3.1.1. The tests will be performed as follows:
- a. The power sources to the Class IE 4.16KV AC, and 125 Volt DC power distribution buses of the redundant load group not under tests are disconnected to verify that the operation of equipment under test is not affected,
- b. The load group of the Safety-Related AC Power Distribution System under test is isolated from the Plant Power Supply and the Offsite AC Power Supplies, simulating an emergency actuation signal which starts the diesel generator under test.
- c. The emergency actuation signal causes sequantial starting of Class 1E loads as described in Section 8.3.1.1.
Amend 63 8.3-27 Dec. 1981 U
The tests will be of sufficient duration to attain steady-state operation of the Standby AC Power System as well as steady-state operation of the loads under test. During the test, the Class 1E AC and CC power distribution buses not under test will be continuously monitored to verify absence of voltage at these buses. The tests will be repeated for the redundant load group and source. Functional performance of loads will be verified as follows: During preoperational testing, functional performance of the auxi-liaries will be verified by tests. 8.3.1.2.9 NRC Regulatory Guide 1.47, Rev. 0 (5/73) Automatic indication of inoperability or bypassed conditions for standby AC power supplies, Class 1E DC power supplies and safety related components and systems will be provided in the Control Room. 8.3.1.2.10 Regulatory Guide 1.53, Rev. 0 (6/73) The Class 1E electrical power systems will be designed to meet single failure criteria. The design will be in accordance with guidance provided in IEEE Standard 379-1972 as supplemented by Regulatory Guide 1.53. The following describes compliance with Regulatory Guide 1.53 requirements:
- a. Section 5.2 of IEEE Std. 379-1972 is adopted as follows:
The detectability of a single failure is predicated on the assumption that the test results, in tt.e presence of a failure are different from the results that would be obtained if no failure were present. Thus, inconclusive testing procedure such as " continuity checks" of relay circuit coils in lieu of relay operation is not considered as an adequate basis to classify as detectable all potential failures which could negate the functional capability of the tested device.
- b. Section 6.2 of IEEE Std. 379-1972 is adopted as follows:
Where a single mode switch applies signals to redundant chan-nels, it is considered that the single-failure criteria is not satisfied if either (a) individual switch sections supply signals to redundant channels, or (b) redundant circuits controlled by the switch are separated by less than six inches without suitable barriers. Amend 63 Dec. 1981 8.3-28
- c. Sections 6.3 and 6.4 of IEEE Std. 379-1972 are interpreted as 4
not permitting separate failure mode analyses for the protec-tien system logic and the actuatr system. The collective protection system logic-actuator system as. applicable for the . Class IE electrical power systems is analyzed for single-y failuro modes which, though not negating the functional capa-bility of either portion, act to disable the complete l Protective function. 8.3.1.2.11 NRC Regulatory Guide 1.63, Rev. 2 (7/78) ., The electrical penetration assemblies in the containment vessel will be designed, constructed, qualified. installed and tested in accordance . with IEEE Std. 317-1976, supplemented by Regulatory Guide 1.63 positions as
, discussed herein. >
The conductors of the penetration are designed to withstand the [ maximum short-circuit currents based on the interrupting capability of the 4 protective device associated with the penetration assembly conductors. The duration of rated short circuit current are based on the operating time of the secondary (backup) protective device or apparatus. The penetrations i are required to maintain their mechanical integrity in accordance with IEEE Std. 317-1976, IEEE Std. 279-1971 and Regulatory Guide 1.63. The dielectric-strength test qualification for medium voltage 1 power conductors is in accordance with IEEE Std. 317-1976 supplemented by the impulse voltage test as described in Regulatory Guide 1.63. Regulatory positions C1, C2, C3 and .C4 place additional restric-tions on maximum short-circuit current, x/r ratios, maximum short-circuit
- g current duration and impulse voltage qualification testing on the electri-cal penetration assemblies in addition to the requirements of IEEE Std.
317-1976. The project will comply fully with the requirements as set forth in IEEE Std. 317-1976 and as modified by Regulatory Guide 1.63.
'8.3.1.2.12 NRC Regulatory Guide 1.68, Rev. 2 (8/78)
-Written procedures for preoperational and ,startup testing for.the Plant AC Power Distribution System, Class 1E AC Power Distribution System, Standby AC Power Supplies and DC System will be developed. ' Format and con-tent of these procedures will conform to the guidance given in Regulatory Guide 1.68. For test program description, see Chapter 14.
8.3.1.2.13 NRC Regulatory Guide 1.73, Rev. 0 (1/74) All Class 1E electric valve operator assemblies, fer installation inside the containment vessel, will be designed, constructed, qualified.. installed and tested in accordance with IEEE Std.~382-1972 supplemented by.- , Regulatory Guide 1.73 requirements.
- Each-electric valve operator-assembly will be designed and constructed to withstand tne worst local environmental requirements (during t
normal or accident conditions) such as temperature, humidity, radiation 'and ( sodium aerosol condition. Amend 63 pd Dec. 1981 8.3 ,
+ ___ _ - _ _ _ _ _ _ ___._:____ __ __._._._ __.___.___ _.__.___m__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ . _ . . _ _ _ _ . .
8.3.1.2.14 NRC Regulatory Guide 1.75, Rev. 2 (9/78) The electrical equipment and circuits comprising or associated with the Class 1E power system, Class 1E protection systems and Class 1E equipment will be designed, qualified and tested in accordance with IEEE Std. 384-1974, supplemented by Regulatory Guide 1.75, " Physical Independence of Electric Systems", positions as discussed herein. The system will be designed so that the redundant equipment and circuits are separated in accordance with the criteria set forth in paragraph 8.3.1.4. The AC loads which are not Class 1E but are required for plant availability will not be connected to the redundant Class 1E, Divisions 1 and 2 4.16KV buses, but will be connected to Division 3 switchgear through isolation devices, which are designed as follows:
- a. Each isolation system will consist of a 4.16KV circuit breaker, a 4.16KV/480V high impedance transformer and a 480V circuit breaker as shown in Figure 8.3-5. The isolation system will be qualified as Class 1E up to the load terminals of the 480V circuit breaker.
- b. The impedance of the isolation system will be high enough so that for the worst possible fault on the Non-Class 1E 480V bus, the following conditions will be met:
(1) The pick-up value of the overcurrent relays protecting the main Class 1E supply circuit breaker will exceed the maximum current (combined maximum load current and maxi-mum fault current contribution) flowing through the supply circuit breaker by a 2:1 margin. This will be achieved through relay coordination. (2) When the 4.16KV Class 1E bus is being supplied from off-site power, the voltage will remain above the level required (80% of nominal) to start and run the safety-related motors. The 4.16KV undervoltage relays will not get de-energized. (3) When the Class 1E bus is being supplied from on-site power, the voltage will remain above 70% of nominal to preclude stalling of Class 1E motors which have been started and are running.
- c. The isolation system 480 volt and 4.16KV circuit breakers will perform redundant isolation functions. They will be stored energy devices and will be physically separated.
- d. Diverse means (electro-mechanical and solid state) will be used for fault sensing and tripping of the isolation system.
Amend 63 Dec. 1981 3.3-30 J
- e. The isolation system will be able to accept any single com-ponent failure concurrent with the worst fault on the Non-Class 1E 480V bus _without unacceptable consequences.
4 (This does not include short circuits on the 4.16KV por-tion of the isolation system since this is considered an extension of the Class 1E bus).
- f. Undervoltage sensing will be provided on the 480V side of the transformer. Its function will be to isolate the Non-Class-1E loads if an undervoltage condition, caused by a fault on a Non-Class 1E load, exists on the 480V bus.
The system is designed to keep the number of associated circuits to a bare minimum. The associated circuits as defined in paragraph 4.5 of
-IEEE Std. 384-1974 are installed in accordance with the requirements placed on Class 1E circuits such as cable derating, environmental qualification, flame retardance, splicing restrictions and raceway fill limitations described in paragraph 8.3.1.4. The analyses and testing of associated circuits will be performed in accordance with paragraphs 4.5(3), 4.6.2 and 5.1.1.2 of IEEE Std. 384-1974. The cable installation design prohibits the use of cable spicing inside the cable tray or conduit raceway system.
The physical identification of Class 1E equipment, cables and raceway systems are described in Section 8.3.1.5. The design provides two separate cable spreading rooms, one above the Control Room and one below it. The design does not permit location of ' any high energy equipment in the cable spreading rooms as required by IEEE Std. 384-1974. The criteria for routing of circuits in the cable spreading rooms is given in Section 8.3.1.4. The Divisions 1, 2 and 3 Class 1E Standby Diesel Generator units are described in Section 8.3.1.1.1. The diesel generator units and asso-ciated auxiliaries and control equipment are located in separate Seismic Category. I structures having independent ventilating systems. The physical separation of circuits related to redundant Standby Diesel Generators are routed in accordance with the criteria specified in Section 8.3.1.4'. The Non-Class 1E and Class.1E DC batteries and related uninterrup-tible power supply (UPS) equipment are described in Section 8.3.2. DC battery and associated UPS equipment of each safety division is separated from equipment of the other safety division by reinforced concrete walls. The Class 1E batteries and UPS equipment are' located in Seismic Category I structures. The physical separation of circuits related to each separate division of batteries and UPS system is in accordance with the criteria described in Section 8.3.1.4. Amend 63 Dec. 1981 8.3-31 V-
Regulatory Positions C.2, C.3, C.4, C.7, C.8 and C.12 place addi-tional restrictions on adequacy of separation of redundant circuits in addition to Section 4 and Section 5 of IEEE Std. 384-1974. The project will comply fully with the requirements as set forth in IEEE Std. 384-1974, as modified by Regulatory Guide 1.75. 8.3.1.2.15 NRC Regulatory Guide 1.89, Rev. 0 (7/74) For a description of environmental qualification of Class 1E equipment, see Section 3.11. 8.3.1.2.16 NRC Regulatory Guide 1.93, Rev. 0 (12/74) CRBRP design consists of two off-site power sources for the CRBRP Preferred Power Supply and two physically independent power sources for the Reserve Power Supply. Each one of these power sources is continuously available for the plant distribution system for safe shutdown. Further, On-site AC Power Supplies are available continuously from three physically separate and electrically independent diesel generators. Three physically separate and electrically independent On-site DC Systems are available to feed Class 1E Divisions 1, 2 and 3 loads, respectively. Divisions 1 and 2 AC loads are redundant to each other. This design satisfies the CRBRP General Design Criterion 15 (GDC 17). The limiting conditions of operations (LCO) are met by the CRBRP design in accordance with Regulatory Guide 1.93. In the event of degrada-tion of the electric power sources below the LC0 conditions, restricted plant operations will be followed in accordance with the recommendations of Regulatory Guide 1.93. 8.3.1.2'17 NRC Regulatory Guide 1.100, Rev. 1 (8/77) Seismic qualification of Class 1E equipment will be in accordance with IEEE Std. 344-1975 supplemented by Regulatory Guide 1.100, as described in Section 3.10.1. 8.3.1.2.18 NRC Regulatory Guide 1.106, Rev. 1 (3/77) Motor thermal overload protection devices for safety related motor operated valves, which are in force during testing and normal operation, will be bypassed under plant emergency conditions. The bypass circuitry will conform to IEEE Std. 279-1971. 8.3.1.2.19 NRC Regulatory Guide 1.108, Rev. 1 (8/77) The preoperational tests and periodic testing, after the diesel generator units are placed in service, will be performed in accordance with Regulatory Guide 1.108, as described in Section 8.3.1.1.1. Amend 63 Dec. 1981 8.3-32 1
m 1 8.3.1.2.20 NRC Regulatory Guide 1.118, Rev. 1 (6/78) CRBRP Design Criterion 16 (GDC 18) has been established to satisfy N the requirements of IEEE Std. 279-1971 and 338-1977 and Regulatory Guide
- 1.118. This requires the design to provide for appropriate periodic inspection and testing of important areas and features, such as wiring, insulation, connections and switchboards, to assess the continuity of the systems and the condition of their components to check the operability and functional performance of the system components such as on-site power sour-ces, relays, switches, buses and the system as a whole under conditions as close to design as practical.
CRBRP design will comply with the above criteria and as a result, it will comply with IEEE Std. 279-1971, 338-1977 and Regulatory Guide 1.118. For details of compliance refer to Sections 8.3.1.1, 8.3.1.2, 8.3.1.2.1 and 8.3.1.3. 8.3.1.2.21 NRC Regulatory Guide 1.131, Rev. 0 (8/77) The electric cables, field splices and connections will be designed, qualified and tested in accordance with IEEE Std. 383-1974, supplemented by Regulatory Guide 1.131, positions as discussed herein. The medium voltage cables, low voltage power and control cables, and instrumentation cables are specified to be type tested and qualified to the requirements of IEEE Std. 383-1974 and IEEE Std. 323-1974 supplemented by Regulatory Guide 1.131 and to the design basis events described in Table 8.3-3. The field splicing of cables inside the cable tray or conduit
^ raceway system is prohibited in accordance with the requirements of IEEE
( Std. 384-1974 supplemented by Regulatory Guide 1.75. The environmental conditions for all cables include the maximum sodium oxide aerosol con-centration, along eith the values of pressure, temperature, radiation, che-mical concentrations, humidity and time, and are specified as applicable to the design of the power plant. 8.3.1.2.22 IEEE Standard 308 - 1974 Class 1E AC and DC Power Supplies and distribution systems will be designed to conform to the requirements of Class IE electrical system as discussed below. The Class 1E systems will be designed to assure that a design basis event does not cause the following: , a. A loss of electric power to more than one Class 1E load group or Plant Protection System channel at any one time.
- b. A loss of electric power to equipment that could result in a reactor power transient capable of causing significant damage to the fuel or to the plant operation. (See Section 15.1.2)
The Class 1E system is capable of performing its function when subjected to the effects of a design basis event at its location. (See Table 8.3-3) No significant radiation hazard to Class 1E loads has been identified for either normal or emergency conditions. O Class 1E loads are designed to perform their intended functions U adequately for the variation of voltage or frequency in the Class 1E electric system. Amend 63 8.3-33 Dec. 1981
Circuit breaker controls and indicating lights are provided both in the Control Room and locally for the incoming line and the diesel generator supply circuit breakers of the Class IE 4.16 KV switchgear buses. Also, controls to start and operate the diesel generators are furnished locally and in the Control Room. Each type of equipment used in the Standby AC Power Supply is qualified to perform its design function under normal and emergency environmental conditions as described in Section 3.11. Supplementary design criteria of IEEE Std. 308 are addressed in the applicable section describing specific Class 1E equipment. The tests and inspections performed for the equipment are described in Section 8.3.1.1. 8.3.1.2.23 IEEE Standard 317 - 1976 The electrical penetration assemblies which pass cables through the containment vessel are designed and testad in conformance to IEEE Std. 317 - 1976. 8.3.1.2.24 IEEE Standard 323 - 1974 The Class 1E AC and DC Power Supply and distribution systems will conform to IEEE Std. 323 - 1974 which includes requirements for an equip-ment qualification method and documentation. The qualification method establishes that each type of equipment is suitable for its application. The documentation will include the application requirements, the equipment specifications, and the data from the qualification methods used. 8.3.1.2.25 IEEE Standard 334 - 1971 Where qualification tests are required for prototype continuous-duty Class 1E Motors installed inside the containment, the procedures spe-cified in IEEE Std. 334 - 1971 and NRC Regulatory Guide 1.40 will be followed. 8.3.1.2.26 IEEE Standard 383 - 1974 Electrical Catles, field splices, and connections will be in con-formance with IEEE Std. 383 - 1974 supplemented by Regulatory Guide 1.131, Rev. O. Type tei t will demonstrate satisfactory performance of the cable (cable assembly) ty electrical and physical measJrements appropriate to the type of cable during and after CRBRP's DBE. Environmental parame-ters specified in IEEE St.1, 323 do not represent acceptaole limits for CRBRP. The actual enviror..aental parameters specific to CRBRP will be uti-lized in cable specifications. 8.3.1.2.27 IEEE Standard 384-1974 The separation criteria of IEEE Std. 384 - 1974 will be applied to insure that the physical independence of redundant Class 1E electrical systems is maintained. (See 5ection P,3.1.4.'; Amend 63 Dec. 1981 8.3-34
8.3.1.2.28 IEEE Standard 387 - 1977 The Standby AC Power Supply conforms to IEEE Standard 387-1977 which includes requirements for capability rating, independence, redun-dancy, testing, analyses, quality assurance, and identification. 8.3.1.3 Conformance with Appropriate Quality Assurance Standards Assurance that equipment and workmanship quality is maintained throughout the construction process is provided by conformance to IEEE Standard 336 - 1971, " Installation, Inspection, and Testing Requirements for Instrumentation and Electric Equipment during the Construction of Nuclear Power Generating Stations". The methods used to accomplish confor-mance are described by construction procedures and instructions and in Chapter 17.0 of this PSAR. 8.3.1.4 Independence of Class 1E Systems The following criteria is used to preserve the independence of Class 1E systems. A. General Separation of Cables by Voltage Class A raceway contains cables of only one class. Classes are based on the nominal utilization voltage of the cable and/or vulnerability to spurious signals. Voltage Classes are: 15KV Class - 13.8KV AC nominal power SKV Class - 4.16KV AC nominal power 600V Class - 480-277~ volt AC and 250 volt DC nominal power Control - 120V/208V AC,125V DC,120V AC nominal power and control Low level instrumentation including digitial and analog signals When cable trays are arranged in a vertical stack, the preferable arrangement is in order of voltage class, with the highest voltage at the top. B. Cable Derating i Ampacity rating and group dorating factors of cables are in accor-dance with the Insulated Power Cable Engineers Association Publications IPCEA:.P54-440 and INEA-P46-426, Qbbs are selected to minimize deterioriation due to temperaturc, hmidity, and radiation during the design life of the plant. Environmental type tests will be performed on
, cables and terminations that are required to function in a hostile environ-ment. The tests will include radiation exposure, heat aging, and electri-cal measurements to assure that the cable will function in the design ; environment for the required time.- Cable derating as a result of fire stops / seals are included in the design.
Amend 63 Dec 1981 s' 8.3-35 i
C. Raceway Fill Cable tray fill will be limited such th<tt the summation of the crosssectional areas of cables in a tray sectwi will in general be not more than 407 of the usable cross-sectional area of that tray section. Conduits will be sized for a maximum percent fill of the inside area of the conduit in accordance with ?!FPA 70 " National Electrical Code" Art. 346. D. Sealing Raceway Blockouts and Wall and Floor Penatrations Fire stops will be installed for cable trays wherever ti:a cables pass through fire walls and floors other than the Reactor Containment vessel. Cable and cable tray penetrations of fire barriers are sealed to provide protection at least equivalent to that required of the fire barrier. Penetrations are qualified to meet the requirements of ASTM E-119, and IEEE Std. 634-1978. The actual fire ratings of stops and penetrations is determiner by the fire hazards analysis. Fire stops, fire barriers, and air seal: will be constructed of mastic type materials or elastomer modular conetruction materials qualified in accordance with IEEE Std. 634 and ASTM E-119. Fire stop/ seal material will be compatible with insulation and conductor materials and will be shock, vibration, seismic, and radiation resistant in accordance with the area (s) penetrated. E. Physical Separation Criteria for Cables of Class 1E Systems The separation design descripticn for raceways, Class 1E circuitry and associated cabling given below incorporates the requirements of IEEE Std. 384-1974, Regulatory Guide 1.6 and NRC Regulatory Guide 1.75. Load groups, cables, and raceways of a safety-related system will be separated from load groups, cables, or raceways of other safety-related groups in accordance with the separation criteria described herein. This separation criteria will preclude a single failure within the safety-related system from preventing proper protective action at the system level when required. Raceways and cables will be classified by separation groups, namely Class IE Division 1, Class 1E Division 2, Class 1E Division 3, and Plant Protection System. Cables designated in each division will be run in raceways separated from cables designated in other divisions and from Non-Class 1E cables. Associated cables will be separated as if they were Class 1E pursuant to the Class 1E aivision associated with these cables. Amend 63 Dec. 1981
The minimum separation maintained between cables of each division varies according to cable location with respect to potential hazards. The design intent is to provide separation greater than the mimimum listed where consistent with a practical plant layout. Six general classifica-h.
'd tions of hazard zones or areas are defined for electrical separation consideration:
- 1. Non-Hazard Zones Areas in which the only potential hazard is a fire of an electri-cal nature.
II. Fire Hazard Zones Areas in which a potential fire hazard could exist as a con-sequence of the credible accumulation of a significant quantity of flam-- mable material. III. Equipment Hazard Zone (Pipe Break Hazard Zone) Areas in which a potential hazard could exist as a consequence of postulated pipe break events in high energy lines. IV. Cable Sprcading Rooms Areas just above and below the main control room where control and instrumentation cables converge prior to entering the control room. V. Containment Electrical Penetration Areas The areas and assemblies that allow cable passage through the Containment Building pressure boundary. VI. Control Room Continuously manned room utilized by plant operators to monitor and control the plant. Non-Hazard Zones Redundant cables entering panels, cabinets or other equipment enter through separate openings. Harnesses for redundant cables within Control Boards and other panels are provided with a minimum of six (6) inches free air separation, otherwise barriers are provided. Non-Class 1E cables are not harnessed together with Class 1E cables and do not provide a combustion path between harnesses of different divisions. In Non-Hazard Zones no minimum vertical or horizontal physical separation is provided between conduits of the same division beyond that required for construction, installation or access clearances between con-duits and/or metal enclosed ducts. O 8.3-37
In Non-Hazard Zones, a minimum horizontal clear space of three feet is maintained between cable trays of different divisions. If a hori-zontal clearance of less than three feet is unavoidable, a fire barrier or a cover (top and bottom) on the trays is provided between the divisions. Vertical stacking of cable trays of different divisions is avoided wherever possible. Where cable trays of different divisions are stacked vertically, a minimum clear space of five feet is provided between tne divisions. Fire Hazard Zones In fire hazard zones, Class 1E conduits, trays, wireways or raceways of only one safety division are routed. This division is suitably protected by fire barriers and fire protection systems to mitigate the effects of fire in this zone on the safety function of the other safety groups. Equipment Hazard Zone (Pipe Break Hazard Zone) To the extent practical, Class 1E cables are routed in areas remote from high energy piping or areas of potential sodium fires; if una-voidable, the following precautions are taken: a) Raceways are not less than fifteen feet from a high-energy pipe-line unless the pipeline is suitably restrained so as not to whip and strike the raceway. This spacing applies regardless of whether the high energy pipeline is a safety system ar non-safety system pipeline. The exception to this consideration is the acceptability of the mechanical failure of one safety system damaging the cable that provides service to components / systems of the mechanical system that has failed. Under no circumstances do safety-related raceways run less than fifteen feet from high-energy pipelines of the opposite safety system. b) Redundant Class 1E circuits are routed or protected such that a postulated event in one system and division cannot preclude the operation of the other redundant system or division. c) In all areas of the plant, the separation between redundant Class 1E cable raceways takes into consideration the presence of rotating equipment, monorails and equipment removal paths and the possibility that heavy equipment could be lifted and dropped and possibly cause failure of two raceway channels. Where this is the case, the minimum separation is such as to preclude this possibility. d) In general, Class IE electrical distribution equipment (e.g., switchgear, motor control centers, etc.) is not located in areas where high energy piping or other similar hazards are located. Amend 63 Dec. 1981 8.3-38
c) In general, no Class IE raceways are installed in equipment hazard zones or potential missile areas. Where this is not practical, only one Class IE division is installed in the area. O O f) In all areas, Class 1E raceways of adequate construction are installed so as to minimize or eliminate the possibility of damage due to potential missiles or pipe whip. The damage potential of the missile or pipe whip is evaluated, and the physical separation between different safety division raceways is specified accor-
.dingly or the raceways are relocated. When physical separation is not practical, appropriately designed barriers are installed bet-ween redundant raceways. The separation of redundant Class 1E division circuits and equipment make effective use of inherent plant design features such as using different rooms or opposite sides of rooms or areas.
Cable Spreading Rooms a) Two cable spreading rooms are provided, one above the Control Room for Division 1, Division 3, and Non-Class IE Division A and one below the Control Room for Division 2, and Non-Class IE Division B. b) Circuits routed in cable trays in the cable spreading rooms are limited to control and instrument functions. No power cables are routed through the cable spreading rooms or the control room. c) The cable spreading rooms are protected agair st external missiles (there are no internal sources of missiles) such as high-pressure (n piping or rotating heavy machinery. The only potential source of damage to redundant division cables would be from fire generated by the cabling itself. A fire detection and suppression system is installed ensuring that potential for fire damage to cables is - minimized in the cable spreading room. d) A minimum clear separation of one foot horizontal and three feet vertical is maintained between trays carrying cables of different divisions. If the minimum horizontal or vertical separation does not exist, a fire-resistant barrier or covered cable trays without barriers are provideo, e) There is no cable tray or conduit connection between the upper and lower cable spreading rooms. Containment Penetration Areas Three separate penetration areas are provided for all cables that - must pass through the containment wall. Where possible, redundant Class IE cables utilize electrical penetrations spaced horizontally rather than vertically. Cables through penetracion of the primary containment, are grouped such that failure of all cables in a single penetration will not Amend 63 Dec. 1981 v 8.3-39
prevent a protective action. Separation of Class 1E circuits is maintained through penetrations. No Class 1E cables share penetrations with Hon-Class l 1E systems, other than associated Class 1E cable systems. l Control Room Cables in the Control Room are kept to the minimum necessary for l operation of the Control Room. All cables entering the Control Room ter-minate there. Cables are not installed in culverts or floor trenches. Cables are not routed in concealed ceiling or under floor spaces unless installed in a solid enclosed steel raceway. l Plant Protection System (PPS) Separation The PPS will neet the separation requirements of IEEE Std. 384-1974 and Regulatory Guide 1.75 and the following: a) All PPS wiring external to control panels is run in conduit, with wiring for redundant channels run in separate conduits. Only PPS wiring is included in these conduits. Primary shutdown system wiring is not run in the same conduit as the secondary shutdown system wiring. b) Wiring for each Primary PPS instrument channel (RIA, R1B, RIC) is routed in separate conduits. c) Wiring for each Secondary PPS instrument channel (S2A, S2B, S?C) is rcuted in separate conduits. d) There are dedicated containment penetrations for each of the three Primary PPS instrument channels and each of the three Secondary PPS instrument channels which pass through containment. All requirements for separation of PPS wiring in raceways are utilized for separation ,0f PPS wiring through containment penetrations. e) All wiring for the three Containment Isolation System instrument channels is routed exclusively with the three Primary PPS instru-ment channels, or exclusively with the Secondary PPS instrument channels or through three independent conduits. f) The Primary PPS Logic Train Actuation wiring is routed through at least three separate conduits from three separate Primary PPS Logic Train Pancis to the Primary PPS Scram Breakers. One conduit contains wiring fron only one Primary PPS logic train. g) The Secondary PPS Logic Train Actuation wiring is routed through at least three separate conduits from the Secondary PPS Logic Panels to the Secondary Control Rod Solenoid Valve Actuation wiring in the Head Access Area. Amend 63 Dec. 1981 8.3-40
h) Containment Isolation System (CIS Logic Train Actuation wiring is routed through two independent conduits. One conduit contains wiring from only one CIS Logic Train. No intermixing of CIS Logic f] trains within a conduit is permitted. CIS Logic Train I wiring is C/ routed from CIS Logic Panel 1 to CIS Breaker 1 in the Intermediate Building. CIS Logic Train 2 is routed from CIS Logic Panel 2 to CIS Breaker 2 in the Intermediate Building .
- 1) The wiring from a PPS buffered output which is used for a non-PPS purpose may be included in a PPS rack. The PPS wiring is separated from the non-PPS wiring. The amount of separation is defined on an individual case basis; however, it is designed to meet the requirements of IEEE Std. 384 and Regulatory Guide 1.75.
j) Containment Isolation Valve actuation wiring (for either manually or automatically initiated actuation) to the Inside Containment and the Outside Containment Isolation Valves are separated as Division 1 and Division 2 cabling, respectively. k) Rigid, metallic, completely enclosed and unvented raceways are considered acceptable for any of the above applications as they are equivalent to rigid metal conduit, as defined in IEEE Std.100 and NFPA 7_.
- 1) The physical separation between PPS conduits, containment penetra-tions, or panels is in accordance with IEEE Std. 384-1974 and Regulatory Guide 1.75 to provide assurance that a credible single event cannot simultaneously degrade redundant protection channels or shutdown systems.
m) The Primary Steam Generator Auxiliary Heat Removal System (SGAHRS) channels and logic outputs are treated and separated as Primary PPS signals. The primary SGAHRS logic output is kept separated from the Seccndary SGAHRS logic output channels. The Secondary SGAHRS channels and logic outputs are treated and separated as Secondary PPS signals. The Secondary SGAHRS logic output is kept separated from Primary PPS, CIS and non-PPS outputs. Redundant SGAHRS logic train autputs are separated from each other. The manual trip and reset inputs to each SGAHRS divisional latch logic is routed and separated as redundant PPS signals separated from the automatic SGAHRS logic outputs and all other PPS and non-PPS channels. F. Cables Within Control Board and Other Panels Within control boards and other panels, harnesses of different divisions are provided with a minimum of 6 inches free air separation. Otherwise barriers are to be installed. Metal conduit, fire barriers, or steel wire ducts are acceptable barriers to maintain independence without additional spatial separation over that required by Regulatory Guide 1.75. Non-Class IE wiring is not harnessed together with Class IE cable and is not permitted to provide a combustion path between harnesses of different Divisions. Penetrations through barriers are permitted if fire stops are provided. V Amend 63 Dec. 1981 8.3-41
Sharing of Cables Trays and Routing of Non-Class IE Cables There are two classes of medium voltage cable trays,13.8 KV and 4.16 KV, these cable trays carry only 15KV and 5 KV rated cables, respec-tively. 480/277 volt power cables, 120/208 volt AC and 125 volt DC cables carrying more than 20 amperes, and 250 volt power cables are run in common low voltage power (LV) trays. Instrumentation trays carry the following cables: input and output cables for the computer, shielded annunciator cables used with solid-state equipment and signal cables for thermocouples, strain gauges, vibration and radiation detectors, thermal converters and RTD's. All other cables are run in control trays. Within a load group division, the minimum spacing between trays stacked vertically is 9 inches, tray bottom to tray bottom. The minimum spacing between trays installed side by side, within a load group division shall be 6 inches. The trays will be constructed of steel. All cable tray systems located in Seismic Category I structures will have supports designed to meet Seismic Category I requirements. All PPS cables are run in conduit or enclosed raceways. PPS ana-log circuits may be routed together in the same raceways, provided the cir-cuits have the same characteristics, such as power supply, shutdown system (primary or secondary), and ;.nannel identity ( A, B or C). Vital instrument cables for the PPS may be routed together in the same raceways, provided the circuits have the same characteristics, such as power supply, shutdown system (primary or secondary), and channel-identity ( A, B or C) Automatic actuation and control power circuits for the PPS may be routed in the same raceways, provided the circuits have the same charac-teristics, such as power supply, shutdown system (primary or secondary), and train identity (PPS logic train I, II or III). The circuits associated with the Standby AC Power System (Class IE electric systems) are separated into three independent divisions. Administrative Responsibilities and Control for Assuring Separation Criteria l The raceway channel identification facilitates and ensures the maintenance of separation in the routing of cables and the connection of control boards, panels and other equipment. Class 1E cables will be inspected upon installation by construction personnnel for consistency with the design documents. Color identification of equipment and cab! ?ng will be used in this effort. Amend 63 Dec. 1981 , 8.3-42
i 8.3.1.5 Physical Identification of Class IE and Non-Class 1E Egipment Each Class IE and Non-Class 1E cable and raceway is given a unique i T identification. This identification provides a meals for distinguishing a circuit or raceway associated with a particular voltage or class as well as with a particular channel or division. The channel or division is provided J by a coded digit of identification and is assigned on the basis of the following criteria: Division 1_ i A Class 1E instrumentation, control, power cable or raceway 4 associated with Load Group of Division 1 Division 2 , A Class IE instrumentation, control, power cable or raceway associated wth Load Group of Division 2 Division 3 A Class IE instrumentation, control, power cable or raceway - associated with Load Group of Division 3 There will be redundant divison color identification provided for all Class 1E cables. Color-coded markers will be provided at both ends of each Class 1E cable. Cables in Class IE raceways will be color coded at a maximum of 5 foot intervals. Within control panels where more than one division is present, wiring will be identified by that division designation; or, if enclosed by conduit, the conduit will be identified by division designation. Within a cabinet or panel which is associated and identified with a single division, the internal wiring will be exclusively associated with the same division, and therfore, requires no further division iden-tification. Conduits, trays, and electrical equipment, of Class 1E and Non-Class IE systems, will be identified by self-sticking markers with the color associated with its division. The raceway system will be marked prior to installation of cables in a distinct permanent manner at intervals not to exceed 15 ft and at points of entry to and existing from enclosed areas. ! Class 1E electric equipment labels will be color coded with the ! same division color coding used for Class 1E cables and raceways. Color coding will be permanent and prominently displayed. Design drawings, operating documents and maintenance documents will provid.e distinct identification of Class 1E equipment. The applicable channel or division designation.will also be identified. The iden-tification scheme for Non-Class 1E cables and raceways will, in general, be O ::imilar to that used for the Class IE circuits and raceway except that dif-ferent color-coded markers will be used. Amend 63 Dec. 1981 8.3-43
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l l 8.3.1.6 Grounding RQquirements The following criteria will be used in the design of electrical system grounding: a) Recommendations of IEEE Standards 80 and 142 will be followed in the design of the grounding system, b) Generator step-up transformer will be grounded using a grounding reactor. c) 4.16KV and 13.8KV windings of the Unit Station and Reserve Station Service Transformers, will be low resistance grounded. d) 480V Non-Class 1E system will be solidly grounded. e) Class 1E system will be high resistance grounded. f) DC system will remain ungrounded. g) Ground grid design will meet safe touch and step potential requirements. h) The plant grounding system will provide grounding for all electrical equipment and metallic objects subjected to acci-dental electrical connection. 8.3.2 DC Power System U.3.2.1 Description The CRBRP DC Powar System as shown in Figure 8.3-2 is comprised of the following separate and independent power supplies: o Three Class 1E 125 volt DC syrce.cs, (Divisions 1, 2 and 3) o Two Non-Class 1E 125 volt DC systems, dedicated for plant control, alarm, indication and instrumentation (Divisions A and B) o One Non-Class 1E 250 volt DC system, Division A o Two Non-Class 1E 125 volt DC systems, dedicated for switchyard control, alarm, indication and instrumentation. (Divisions A and B) o Two Non-Class 1E 48 volt DC systems, dedicated for the Plant Communication System (Divisions A and B) o Two Non-Class 1E DC systems dedicated for the Plant Physical Securitv System. (Not shown in Fig. 8.3-2) Amend 63 Dec. 1981 8.3-44 l
8.3.2.1.1 Class IE DC Power System The Clar.s IE DC Power System as shown in Figure 8.3-2 is comprised of three independent DC Systems, rated at 125 volt DC. Each DC System con-Q sists of a battery, battery chargers, DC switchgear and distribution panels. All DC Systems are ungrounded and are pr aided with ground detec-tors to indicate if there is a ground positive or negative on the battery. A ground on one side of the battery will not cause equipment to malfunc-tion, and will be annunciated in the control room. Each DC System is pro-vided with undervoltage detection to annunciate in the control room for low voltage condition or power interruption at the buses. In addition, each battery charger is provided with an alarm relay which annunciates in the control room failure of AC supply to the charger. Battery chargers, distribution buses and distribution panels are fur-nished with individual metal enclosures. Physical separation, and where required, fire barriers are provided between components and cabling of the redundant divisions so that a fire could not cause simultaneous interrup-tion of power to the load groups. Ventilation for DC equipment is described in Section 9.6.1. The Class 1E DC System provides a reliable source of continuous power for control, instrumentation, vital bus inverters and other plant DC loads. This system is comprised of three independent redundant Division 1, 2 and 3125 volt DC Systems. Each Division supplies power for control of a redundant load group. See Tables 8.3-2A, 8.3-2B and 8.3-2C for listing of loads and figure 8.3-2 for system configuration. Each 125 volt DC system consists of one battery, two solid state O battery chargers, one DC switchgear and necessary instrumentation for O system monitoring. The system is arranged so that the battery or any one battery charger can independently supply the system bus load. Each battery is provided with a 100 percent capacity spare battery charger. Power for the 125 volt DC system is normally supplied through the battery charger from a 480V AC motor control center (MCC). This MCC will automatically be supplied from the standby diesel generator on loss of Plant and Offsite AC Power Sources. The battery chargers, for each divison, are powered from the associated diesel generator of that safety division. Since the Division 1, 2 and 3,125 volt DC Power Systems are totally independent and serve redundant Class 1E loads, the complete loss of a division wil! not affect the ability of the plant to achieve safe shutdown and/or micigate the consequences of an emergency condition. The battery chargers for each division are 480V AC to 125V DC solid state chargers. Each Division has one u tive and one spare battery charger. Each battery charger is capable of carrying the normal steady state DC load for its division while simultaneously maintaining its battery in a fully charged " float" condition. The chargers are capable of supplying the Amend 63 Dec. 1981 8.3-45
125 volt DC power r quirements for all modes of plant operation while restoring the batteries from a discharge condition of 1.75 volts per cell to full charge within 12 hours. The charger size and instrumentation con-form to the requirements of IEEE Std. 308. Each battery charger is provided with an integrally mounted, incoming AC circuit breaker, and an output DC breaker with magnetic trip to isolate the charger from the DC bus in case of an internal fault in the charger. The output current of each battery charger will be monitored in the Control Room. A battery charger failure will be annunciated in the Control Room. In the event of a loss or interruption of battery charger 125 volt DC output, the station batteries will maintain power to their respec-tive DC systems. The ampere-hour capacity and duration of the batteries is in accordance with IEEE Std. 308. Batteries are capable of supplying for at least 2 hours, all DC power required to safely shutdown the plant and/or to limit the consequences of a design basis accident without recharging. Batteries are connected to the DC bus through a circuit breaker. The current output of each battery will be monitored in the Control Room, and a high battery discharge will be annunciated in the Control Room. Cables for the three redundant load groups of the Class 1E DC power systems will be installed in separate divisions of the Class 1E raceway system. The Class 1E cable and raceway independence criteria are described in Section 8.3.1.4. Cables and raceways of the Class 1E DC power system will be marked in a distinctive manner as described in Section 8.3.1.5. 8.3.2.1.2 fion-Class 1E DC Power System The fion-Class 1E DC system is comprised of nine separate DC systems, six systems are rated at 125 volt DC, two systems are 48 volt JC and one system at 250 volt DC. See Figure 8.3-2 for system configurations. Two of the 125 volt DC systems are dedicated for plant control, alarm and instrumentation. Each of these systems are comprised of one bat-tery, three solid state battery chargers, one DC switchgear, distribution panels and the necessary instrumentation for system monitoring. The system is arranged so that the battery or any two battery chargers can indepen-dently supply the system bus load. Each battery is provided with one spare battery charger. Power for the 125V DC Systems is normally supplied through the battery chargers from the 480V AC motor control centecs. The battery chargers are capable of supplying the 125V DC power requirements for all modes of plant operation while restoring the batteries from a discharge condition of 1.75 volts per cell to full charge within 12 hours. Each battery except those for the Plant Security System is sized to power required loads for a period of 2 hours without recharging in the event of loss of all AC power. The DC batteries for the Plant Security System are not described herein. Amend 63 Dec. 1981 8.3-46 l
-s Two 125 volt DC systems are dedicated for switchyard ' power and control. Each of these systems are comprised of one battery, one solid ,
state battery charger, one DC power panel and the necessary instrumentation O V for system monitoring. The system is arranged so that the battery or, bat-tery charger can independently supply the system bus load. Power for the .. 125V DC systems is normally supplied through the battery charger from a . 480V motor control center. The battery charger is capable of supplying the ' 125V DC power requirements for all modes of plant operation.while restoring ( the batteries from a discharge condition of 1.75 volts per cell to full , charge within 12 hours. Each battery is sized to power the required loads for a period of 2 hours without recharging in the event of loss of all A* _ power. One 250 volt DC system is used to provide power for DC mot' ors of the back-up oil bearing pumps associated with the main turbine generator, ~' the motor generator sets of the sodium pump drive system, and an, AC inverter for loads of the fire protection and other systems. This system ' is comprised of one battery, three solid state battery chargers, cne DC - switchgear and the necessary instrumentation for system monitoring. The system is arranged so that the battery or any two battery chargers can independently supply the system bus load. One spare battery charger is provided for this battery. Power for the 250V DC systems is normally supplied through the battery chargers from 480V AC motor control centers. The battery chargers are capable of supplying the 250V DC power require-ments for all modes of plant operation while restoring the batteries from a discharge condition of 1.75 volts per cell to full charge within 13 hours. The battery is sized to power required loads for a period of 2 hours s ,' without recharging in the event of loss of all AC power.
") Two 48 volt DC systems are dedicated for the Plant Communic'ation System. Each of these systems are comprised of one battery, one solid state battery charger, one DC power panel and the necessary instrumentation '
for system monitoring. The system is arranged so that the battery or bat-tery charger can independently supply the system bus load. Power for the 48V DC system is normally supplied through the charger from 480V AC motor control center. Each battery charger is capable of supplying the 48V DC power requirements for all modes of plant operation while restoring the batteries from a discharge condition of 1.75 volts per cell to full charge within 12 hours. The battery is sized to accommodate all connected loads for a period of 2 hours in the event of loss of all AC power. 8.3.2.1.3 System Operations, Testing and Inspection System Operations The system steady-state voltage during normal operation will be determined by the output voltage of the battery charger. The output voltage level will be manually set to a predetermined value for float-charging the battery. When restoring charge to a discharged battery, the output voltage level of the battery charger can be manually increased, to the maximum permissible system voltage, for battery cell voltage equali-zation. Amend 63 O O Dec. 1981 8.3-47
When the battery charger (s) is (are) unavailable, the battery supplies power to the system loads and the system voltage decays as the battery approachas its d n ign Mnimum charge. The system voltage can vary from the low lev'cl associated witi: the design minimum charge of the bat-tery, to a , maximum 61evel ' established by the battery charger. All loads are designed to operate satisfactorily over the full operating range of the system voltage described above. A voltmeter and ammeter will be mounted on each battery charger to monitor cutput voltage and current. The battery voltage and current will be monitored by indicating instruments located at the associated
, Class IE DC distribution bus.
A ground detector will be provided for each channel of the Class lE DC power systen to annunciate, in the Control Room, the existence of a circuit ground in the battery supply, the output circuit of the battery charger, or the associated distribution system. An undervoltage relay will be connected to each Class 1E DC distribution bus to annunciate, in the Control Room, a low voltage condition or power interrupt 300 at the DC buses. In addition, each battery charger will be providei with an alarm relay which orovides annunciation in the Control Room for Yailure a; the AC supply to the charger. ,- Each Class 1E battery and certain Non-Class 1E batte6es are pro-vided with spare battery chargers. The spare battery charger will be put in service in the event the active battery charger is under maintenance, testing or has failed. , Testing and Inspection Periodic maintenance tests will be performed in accordance with IEEE std. 308-1974, 450-1975 and Regulatory Guides 1.32, on all DC system components to determire the condition of each individual subsystem. Batterdes and battery ' chargers will be tested and inspected as follows: A. The specific gravity, voltage, and temperature of the pilot cell and the overall ba'.tery voltage of each battery supply y are measured ard logged weekly during normal plant operation,
- 8. Cells are visually checked weekly for possible cracks, electrolyte leaks, or corrosion of terminals.
~ C. Vol tage, specific gravity, and the liquid level of each cell and electrolyte temperature of every fifth cell are measured and logged monthly. D. Each Class 1E battery will be subjected to a performance discharge test at three year intervals, during a refueling period, to ascertain that it is capable of delivering its ratea capacity. The specific gravity and voltage of each cell will be measured and logged after the discharge. Amend 63 Dec. 1981 S.3-48
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e Battery chargers in continuous service will be tested to demon-strate their operability and performance by supplying power to the loads. The standby battery charger will be tested during nornal plant operation by puttina, the unit in service to derconstrate that it is operable and performs O V properly. Each battery charger will also be subjected to a weekly visual inspection and a performance stest during each refueling period to ascertain that it-is capable of oper9 ting within design limits. Circuit breakers in continuous service will be tested to demon-strate their operating capability and performance by carrying electrical load. < Gircuit breakers of standby equipment will be tested for their operability by putting the standby equipment in service when plant operating conditions permit. All circuit breakers will be subjected to inspection, operational tests, and maintenance (if required) during pro-longed plant shutdown periods. 1 For Class 1E DC System components, the manufacturer will perform operational tests or calculate data which will substantiate the capability of the equipment to carry their DC loads. Preoperational testing will be performed to verify that all components, automatic and manual controls and functions of the DC systems perform as required. 8.3.2.2 Analysis Compliance with CRBRP General Design Criteria 15 and 16 is discussed in Section 3.1. The Class 1E DC Power Systems are discussed below to indicate the degree of conformance with: NRC Regulatory Guides 1.6, 1.32, 1.41, 1.47, 1.68, 1.75, 1.128, 1.129 and IEEE Standards 308, 317, 323, 384, 450, 484 and 485. 8.3.2.2.1 NRC Regulatory Guide 1.6, Rev. 0 (3/71) Safety-Related DC Distribution System provides separation of the DC powered Class 1E loads into two redundant load groups so that loss of one group will not prevent the safe shutdown of the plant. Each DC redundant load group is powered by a battery and a battery charger supply. The combined battery and battery charger supplies assigned to one redundant load group have no automatic or manual connection to the other redundant load group. 8.3.2.2.2 NRC Regulatory Guide 1.32, Rev. 2 (2/77) The battery charger supply will have the capacity to furnish electric energy for the largest combined demands of the various steady-state loads, and the charging capacity to restore the battery from the design minimum charge state to the fully charged state, irrespective of the status of the plant during which these demands occur. - 8.3.2.2.3 NRC Regulatory Guide 1.41, Rev. 0 (3/73) Preoperational tests will be performed to verify the independence of the redundant DC power sources and between the redundant load groups described in Section 8.3.2.1. During these tests the power sources to the 8.3-49 Amend 63 Dec. 1981
Class 1E DC power distribution bus of the redundant load group not under test will be disconnected and the bus voltage continuously monitored to verify the absence of voltage at the bus. The tests will be repeated for the redundant load group and sources. The tests will be of sufficient duration to attain steady-state operation of the DC power sources as well as steady-state operation of the loads under test. 8.3,?.2.4 NRC Regulatory Guide 1.47. Rev. 0 (5/73) Class 1E systems will be designed to meet the guidelines of this Regulatory Guide as described in Section 8.3.1.2. 8.3.2.2.5 NRC Regulatory Guide 1.68, Rev. 2 (8/78) Written procedures for preoperational and startup testing for electrical distribution system will be developed to meet the guidelines of this Regulatory Guide as described in Section 8.3.1.2. 8.3.2.2.6 NRC Regulatory Gide 1.75, Rev. 2 (9/78) Class 1E systems will be designed to meet the guidelines of this Regulatory Guide as described in Section 8.3.1.2. 8.3.2.2.7 NRC Regulatory Guide 1.128, Rev. 1 (10/78) The Class IE DC power system will be designed to conform to the requirement of IEEE Std. 344-1975 and 484-1975 supplemented by Regulatory Guide 1.128 per the following: a) The location of the Class IE DC system meets the design cri-teria of IEEE Std. 344 and supplemental Regulatory Guide 1.100. b) Battery area ventilation system will limit hydrogen con-centration to less than two percent by volume, c) Fire protection in battery areas is in accordance with Regulatory Guide 1.120. d) Any cell which, when unpacked, exhibits an electrolyte level 1/2 inch or more below the top plates will be replaced. e) Class 1E batteries will be stored such that cells will not be exposed to low ambient temperatures or localized heat sources. 8.3.2.2.8 NRC Regulatory Guide 1.129, Rev. 1 (2/78) Class 1E systems meet the guidelines of this Regulatory Guide as described in Section 8.3.2.1.1. Amend 63 Dec. 1981 8.3-50 t
8.3.2.2.9 IEEE Standard 308 - 1974 The Class 1E DC power systems will be designed to conform to the requirements of Class 1E electric systems as indicated in Section 8.3.1.2. 8.3.2.2.10 IEEE Standard 317 - 1976 The electrical penetration assemblies which pass cables through the containment exterior wall will be designed and tested in conformance with IEEE Standard 317 - 1976. 8.3.2.2.11 IEEE Standard 323 - 1974_ The Class 1E DC Power Systems conform to this standard as described in Section 8.3.1.2. 8.3.2.2.12 IEEE Standard 384 - 1974 The separation criteria of IEEE 384 - 1974 will be applied to 4 insure -the physical-independence of redundant Class 1E electrical systems.
- (See Section 8.3.1.4) 8.3.2.2.13 IEEE Standard 450 - 1975 Periodic tests on the Class lE 125 DC batteries will be performed in conformance with this standard. The periodic tests and test intervals are described in Section 8.3.2.1.1.
8.3.2.2.14 IEEE Standard 485 - 1978 Batteries are sized in accordance with IEEE Std. 485 with battery capacity temperature correction and aging factors. Each. battery is sized for its maximum expected load duty cycle including a margin for load growth. Amend 63 Der; 1981
)
_ v 8.3-51
TABLE 8.3-1A CtASS lE DivlS10N 1 DIESEL GENERATOR LOAD LIST IHE MACHINE SHALL UN RECLIPT OF START SIGNAL, (T14F 0). START AND ATTAIN RAlfD SPEEu AND VOLTAGE WITillN 10 SECONDS, AND ACCEPT LOADS IN ANY OF THE SEQUENCES STATED BELOW. SEQUENCE UURAllON APPLICABLE CONDITIONS UF UPERATION NAME PL ATE KW OF 0F UV SGAHRS OMS THW _ LOAD DESCRIPil0N HP (IN) OPERATION OPERATION _ (KW1 (KW) 1KWl (FWJ _ SIANDBY LIGHilNG SYSTEM PANELS 50 10sec Continuous 50 50 50 50 115 10sec Continuous 115 115 115 - UAITERY CHARGER (130VOC) t:ATitRY CHARGER (130VDC) 115 10sec Back Up - - - - ,c0 futL Oil TRANSFER PUMP 5 4.2 10sec Inter. 4.2 4.2 4.2 4.2 w 4.2 f5ack up 4 FULL OIL TRANSFER Pul4P 5 10sec - - - - N CON 1ROL ROOM UNIT SUPPLY F AN 75 52.0 10sec Continuous 52.0 52.0 52.0 52.0 CONTRUL ROOM FIL TER UNIT FAN 20 11.6 10sec Continuous 11.6 11.6 11.6 11.6 CONTROL ROOM RETURN FAN 30 17.6 10sec Continuous 17.6 17.6 17.6 17.6 ANNULUS FILIER FANS 30 17.1 10sec Continuous 17.1 17.1 17.1 17.1 ANic;LUs PRESS. MAIN 1. FAN 7.5 4.9 10sec Continuous 4.9 4.9 4.9 4.9 ON 85 c_. 8.
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i i a 1 TABLE 8.3-1A CLASS lE DldlSION 1 DIESEL GENERATOR LOAD LIST (Cont'd) I SEQUENCE DURATION APPLICABLE CONDITIONS OF UPERATION NAME PLATE KW OF 0F uv swJtR5 0118 5 IMBDB LOAD DESChlPilUf4 HP (IN) OPERATION OPERATION (KW) (KW) _(KW ) (KW) i _ SYST. 56 PANEL UNIT CCOLER 1.5 a.8 10sec Continuous 0.8 0.8 0.8 - SYST. 56 PANEL UNIT CuoLER 1.5 0.8 10sec Continuous 0.8 0.8 0.8 - REACTOR CONTAINMENT BLOG.1%T. DIVISION 1 0.4 10sec Continuous 0.4 0.4 0.4 0.4 REACTOR CONTAINMENT TM808 INST. DIVISION 1 1.5 10sec Continuous 1.5 1.5 1.5 1.5 co 1.5 10:ec Continuous 1.5 1.5 1,5 1.5 u REACTOR CONTAINMENT IMBD8 INST. DIVISION 1 1.5 1.4 10sec Continuous 1.4 1.4 1.4 1.4
$ UMP DISCHARGE CV [SULATION VALVE (INNER) 1050 833 10sec Continuous 833 833 - -
5GAHR5 AUX. FEED WATER PUMP DR. MTR. 0.6 10sec Continuous - 0.6 0.6 - f ' SYSTEM 81 I&C ?ANEL A 1.3 10sec Continuous - 1.3 1.3 - SYSTEM 81 !&C PANEL A 1.6 10sec Continuous - 1.6 1.6 - SYSTEM 81 ISC PANEL A Continuous 1112 1115 282 161 TOTAL LOAD FOR 10 SEC BLOCK EN P@' i 8a
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TABLE 8.3-1A CLASS lE DIVISION 1 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE OURATION APPLICABLE r.uNulTIONS OF OPERATION NAME PL ATE KW OF OF UV %TES UHRS IH6DB __ LUAD DESCRIPIl0N __ HP (IN) OPERATION UPERATION (KW) (KW{ 1Fg (KW) _ BATTERY ROOM EXH. FAN 0.33 0.3 20sec Continuous 0.3 0.3 0.3 U.3 BATTERY ROOM EXH. FAN 0.33 0.2 20sec Continuous 0.2 0.2 0.2 0.2 DIESEL RM "A" EMERG. SUPPLY F AN 20 10.6 20sec Continuous 10.6 10.6 10.6 10.6 p OlESEL HM "A* EMERG. SUFPLY F AN 20 10.6 20sec Continuous 10.6 10.6 10.6 10.6 Y AUX. FLEO PuttP UN!i COOLER 7.5 5.2 20sec Continuous 5.2 5.2 5.2 - $ AUX. FEED PUMP UNIT COOLER 7.5 4.0 20sec Continuous 4.0 4.0 4.0 - EISC CU8ICLE UNIT COULER 2 1.1 20sec Continuous 1.1 1.1 1.1 - El&C CUBICLE UNIT COOLER 2 1.1 20sec Continuous 1.1 1.1 1.1 - Art 10LUS FILTER HEA1ERS 133 20sec Continuous 133 133 133 133 UAY TANK CELL ExH. FAN 0.125 0.18 20sec Continuous 0.18 0.18 0.18 0.18 AIR COOLED Cut 4 DENSER BLOWER MOTOR 60 45 20sec Continuous 45 45 - - AIR COOLED CONDEf4SER BLOWER MOTOR 60 45 20sec Continuous 45 45 - - FF F e '2-O O O
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TABLE 8.3-1A CLASS 1E OlvlS10N 1 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE DONATION APPLICABLE CONDITIONS OF OPEHATION OF OV SGAHR5 DHR5 IMBDB NAME PLATE KW OF HP (lN) OPERATION OPERATION (KWJ (KW) (KW) JKW1 LOAD DESCRIPi!ON 20sec Continuous 18.6 18.6 18.6 - 75 18.6 Piti$ Na. POMP PONY MOTOR 20sec Continuous 18.6 18.6 18.6 - lHIS Na. PUMP PONY MOTOR 75 18.6 Continuous 2 2 2 - 2 2 20sec ARD BEARING FAN MIR. PRIM Continuous 2 2 2 - 2 2 20sec Co ARD BEARING FAN MTR. INTERM 108 108 108 108
- 150 108 20sec Continuous m EMtHGENCY PLANT SEHVICE WATLH POMP 15 15 15 15 25 15 20sec Continuous C00 LING TOWER FAN Continuous 15 15 15 lb 25 .15 20sec C00 LING TOWER FAN Continuous 15 15 15 lb 25 15 20sec COOLING TOWER FAN Continuous 5.7 5.7 5.7 5.7 7.5 5.7 20sec EMERGENCY PLANT SEHVICE WATER MAKEUP POMP 1568 1571 648 475 ;
20 SEC BLOCKS Continuous i TOTAL LOAD FOR 10 SEC Ai' m ~
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'l CLt.SS lE DIVISION 1 DIESEL GENERATOR LOAD LIST (Cont'd) i J
SEQUENCE DURATION APPLICABLE CONDITIONS OF OPERATION l NAME PLATE KW OF OF ~V( SCAHR5 DHRs TKtW LOAD DESCRIPT!0N HP (IN) OPERATION OPERATION (KW) (KWJ (KW) (KW) __ 1 i SWGR A/C UNIT "A" (SUPPLY FAN) 25 15.2 1 min Continuous 15.2 15.2 15.2 15.2 SWGR RETURN FAN "A" 10 6.1 1 min Continuous 6.1 6.1 6.1 6.1 ! SG LOOP 1 SUPPLY FAN 200 137 1 min Continuous 137 137 137 - i 1 i SG LOOP 1 SUPPLY FAN 200 137 1 min Back up - - - - 1 i C,0 l w SG U)0P 3 SUPPLY FAN 200 149 1 min Continuous 149 149 149 -
$ SG LOOP 3 SUPPLY FAN 200 149 1 min Back up - - - -
SGB-18 SUPPLY F AN 40 22 1 min Continuous 22 22 22 22 SGB-IB $UPPLY FAN 40 22 1 min Back up - - - - SG LOOP 1 EXH. FAN 75 44 1 min Continuous 44 44 44 - 5G LOOP 1 EXH. FAN 75 44 i min Back up - - - - (D n m
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t TABLE 8.3-I A CLASS lE DIVISION 1 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE OURATION APPLICABLE CONDITIONS OF OPERATION I NAME PLATE KW OF 0F uv ~5N UHRs IN LUA0 DESCRIPTION HP (IN) OPERATION OPERATION (KW) (KW1 (KW) (KW) SG LOOP 3 EXH. FAN 75 51 I min Continuous 51 51 51 - SG LOOP 3 EXH. FAN 75 51 1 min Back up - - - - 15 10 1 min Continuous 10 10 10 10 1 SGB-IB EXil. FAN SG8-IB EXH. FAN 15 10 1 min Back up - - - - W 3 2.1 1 min Continuous 2.1 2.1 2.1 2.1 ABHX CELL UNIT COOLER 2 1.2 1 min Continuous 1.2 1.2 1.2 1.2 ELECT. EQUIPMENT UNIT COOLER a 63 1 min Continuous - 18 E3 - MI:4ARY SUDIUM MAKEUP PUMP *A" 75 150 117 1 min Continuous - 77 117 - EVS1 NaK PUMP "A" EVST NaK PUMP "A" BLOWER 15 12.5 1 min Continuous - 12.5 12.5 - EVST AIR BLAST HEAT EXCHANGER "A" 125 !!2.5 1 min Continuous - 63 112.5 - Continuous 2006 2179 1391 531 TUTAL LOAD FOR 10 SEC THROUGH 1 MIN BLOCKS 7 Sk Pe"
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TABLE 8.3-1A CLASS lE Divis10N 1 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE OURAll0N APPLICAHLE CONDITIONS OF OPEHATION NAME PLATE KW OF OF UV SGAliRS UtiRT TMuDB'- LOAD DESCRIPTION _ HP (IN) OPERATION OPERATION _(KW ) (KW) _ _ _ _ _(KW) (KW) _ EMERGENCY CHILLED WATER PUMP 75 54 3 min Continuous 54 54 S4 $4 TOTAL LOAO FOR 10 SEC THRU 3 MIN BLOCKS Continuous 2060 2233 1445 585 co EMERGENCY CHILLER 667 KW 469 4 min Continuous 469 469 469 469 EMERGLNCY CHILLER CON 1;;0L y CENTER PANEL 5 4 min Continuous 5 5 5 5 TOTAL LOAD FOR 10 SEC THR00GH 4 MIN BLOCKS Continuous 2534 2707 1919 1059 s EMERG. CHILLER ROOM UNii COOLER 0.75 .53 5 min Continuous .53 .53 .53 .53 FAN n) TOR 100 55 5 uiin Continuous 55 55 % 55 EN o is 1 5* 5$ O O O
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~_./ %j TABLE 8.3-1A CLASS lE OlVISION 1 DIESEL GENERATOR LOAD LIST (Cont'd)
SEQUENCE OURATION APPLICABLE CONDITIONS OF UPERATION NAME PLATE rW 0F OF UV 5GAlfR5 UHR5 TrEI)T~ LOAD DESCRIPTION HP (IN) OPERATION OPERATION (KW) (KW) (KW) (KW) FAN MOTOR 60 35 5 min Continuous 35 35 35 35 Ev5T S001UM PUMP "A" 75 63 5 min Continuous - 63 63 - TOTAL LOA 0 FOR 10 SEC THROUGH 5 ' MIN BLOCKS Continuous 2624 2861 2012 1150 C3 ANNULUS COOLING FAN 300 215.4 manual Continuous - - - 215.4
$ ANNULUS COOLING FAN 300 215.4 manual Continuous - - -
215.4 AnttOLUS COOLING FAN 300 215.4 manual Continuous - - - 215.4 CUNT. CLEAN-UP SCRB E1H. FAN 250 154 manual cont inuous - - - 154
- CLEAN-UP FILTER HEATER 60 manual Continuous 60 60 60 60 CLEAN-UP FILTER FAN 40 22.6 manual Continuous 22.6 22.6 22.6 22.6 ANNULUS FILTER UNIT COULER 1 0.8 manual Continuous 0.8 0.8 0.8 0.8 CLEAN-UP FILTER UNIT COULER 1.5 5.3 manual Continuous 5.3 5.3 5.3 5.3 (D F PZ'
TABLE 8.3-1A CLASS lE DIVISION 1 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE 00 RAT 10N APPLICABLE CONDITIONS OF OPERATION NAME PLATE KW OF Of UV 5GAHR5 DHRS IMiiT)T-LOAD DESCRIPfl0N HP (IN) OPERATION OPERATION (KW) (KW) (KW) (KW) CLEAN-UP PUMP UNIT COOLER 3 1.9 manual Continuous - - - 1.9 CLE AN-UP SCRUBBER CELL UNIT COOLER 3 1.6 manual Continuous - - - 1.6 CLEAN-UP CHASE UNIT COOLER 0.5 .4 manual Continuous - - -
.4 SEISMICALLY QUAL. FIRE PUMP CONTROLLER 25 13.1 manual Continuous 13.1 13.1 13.1 13.1 PANEL. LEAK MONITOR 1.14KW 0.76 manual Continuous 0.76 0.76 0.76 0.76 00 PA14EL, LEAK MONITOR 2.77KW l.9 manual Continuous 1.9 1.9 1.9 1.9
$ PANEL, LEAK MONITOR 2.78KW 1.9 manual Continuous 1.9 1.9 1.9 1.9 TMBOB CIRCULATING WATER PUMP (HOLD 300 220 manual Continuous - - - 220 75001590) TUTAL LOAD Continuous 2731 2967 2.79 2277 FUTURE LOAD (15% GROWTH) Continuous 410 445 327 341 TOTAL LOAD INCLUDING FUTURE LUAD Continuous 3140 3412 2506 2618 m I3 Pe
- F 0 0 0
! : T Q ) h}) -
\ 4 4
TABLE 8.3-1A CLASS lE DIVISION I DIESEL GENERATOR LUAD $UMMARY LOAD
SUMMARY
LOAD TIME BLOCK ON BUS UNDERVOLTAGE SGAHR$ OHRS TMUUB LDAD COMUL. LOAD COMUL. LOAD COMUL. LOAD CUMUL. KW kW KW KW KW kW KW KW l 10 sec 1112 1112 1115 1115 282 282 161 161 1 2 20 sec 4 56 1568 456 1571 366 648 314 475 1 , 3 1 min 438 2006 608 2179 143 1391 56 531 ca 4 3 min 54 2060 54 2233 54 1445 54 585 Y m 5 4 min 474 2534 474 2707 474 1919 474 1059 4 6 5 min 90 2624 154 2861 153 2072 91 1150 ,
- Manual 107 2131 106 2967 107 2179 1127 2277 i
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TABLE 8.3-1B o CLASS lE DIVISION 2 tilLSEL GENERATOR LOAD LIST THE MACHINE SiALL ON REuEIPT OF START SIGrtAL, (TIME 0), START AND ATTAIN liATLD SPEED AND VOLTAGE WITHIN 10 SECONDS. AND ACCEPT LOAUS IN ANY Of THE SEQUENCES STATED BELOW. SEQUENCE DURATION APPLICABLE CONDITIONS OF OPERATION NAME PLATE KW OF 0F UV SGAHRS DHR5 IMBDB LOAD DESCRIPTION HP (IN) OPERATION OPERATION (XW L (KW) (KW) (KW) STAND 6V LIGH!!NG SYSTEM PANELS 50 10sec Continuous % 50 50 50 CATTERY CHARGER (130VDC) 115 10sec Continuous 115 115 115 - p BATTERY CHARGER (130VDC) 115 10sec Back up - - - - Y FUEL Olt TPANSFER PUMP 5 4.2 10sec Inter. 4.2 4.2 4.2 4.2 m N FUEL Ott TRANSFER PUMP 5 4.2 10sec Back up - - - - CouTROL ROOM UNIT SUPPLY FAN 75 52 lusec Continuous 52 52 52 52 CONTROL RUOM FILIEW UNIT FAN 20 11.6 10sec Continuous 11.6 11.6 11.6 11.6 CONTROL ROOM RETORN FAN 30 17.6 10sec Continuous 17.6 17.6 17.6 17.6 ANNULUS FILIER FANS 30 17 10sec Continuous 17 17 17 11 ANNULUS PRESS. MAINT. FAN 7.5 4.9 10sec Conti,suous 4.9 4.9 4.9 4.9 SYST. % PANEL UtilT COOLER 1.5 0.8 10sec Continuous 0.8 0.8 0.8 - Ek Pe O
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-. . - - - . _ .- -. .. ~ . _ - .
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\d -V 6 j TABLE 8.3 18 CLASS lE DIVISION ! DIESEL GENERAL s LOAD LIST (Cont'd) i SEQUENCE OURATION APPLICABLE CGNDITIONS UF OPERATION i NAME PLATE KW OF OF UV SGAllR5 DHR5 fiGW LOAD DESCRIPTION HP (IN) OPERATION . OPERATION (KW) (KW)
(KW) (KW) j REACTOR CONTAINMENT BUILU. INST DIVISION !! 0.5 10sec Continuous 0.5 C.5 U.S 0.5 i REACTOR CONTAINMENT TMuGB INST. DIVISION !! 1.5 10sec Continuous 1.5 1.5 1.5 1.5 j REACTOR CONTAINMENT TMBDB INST. OlVISION 11 1.5 Continuous 1.5 1.5 10sec 1.5 1.5 l + m SUMP DISCHARGE CV ISOLATION VALVE (00TER) 1.5 1.4 10sec Continuous 1.4 1.4 1.4 1.4 , Y cn SGAHRS AUX, FEED WATER PUMP DR. MTR. 1050 833 10sec Continuous 833 d33 - -
" SYSTEM 81 1&C PANEL 'B' .25 10sec Continuous . .25 .25 -
; SYSTEM 81 15C PANEL 'B' .75 10sec Continuous -
.75 .75 -
) j SYSTEM 81 15C PANEL 'B' l.25 10sec Continuous - 1.25 1.25 - e I LOAD FOR 10 SEC BLOCK Continuous 1111 1114 281 161 } NN n m
- . 3 i
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TABLE 8.3-1B CLASS 1E DIVISION 2 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE OURATION APPLICABLE CONDITIONS OF UPERATION NAME PLATE KW 0F OF UV SGAHR5 UHR5 Il4ilDT LOAD DESCRIPil0N HP (IN) OPERATION OPERATION (KW) ]KW1 (KW) (KWJ BATTERY ROOM EXH. FAN 0.5 0.21 20sec Continuous 0.21 0.21 0.21 0.21 BATIERY ROOM EXH. t AN 0.5 0.3 20sec Continuous 0.3 0.3 0.3 0.3 DIESEL RM "B" EMERG. SUPPLY FAN 20 10.6 20sec Continuous 10.6 10.6 10.6 10.6 UIESEL RM "B" EMERG. SUPLY FAN 20 10.6 20sec Continuous 10.6 10.6 10.6 10.6 Co AUX. FEED PUMP UNIT COOLER 7.5 5.2 20sec Continuous 5.2 5.2 5.2 - Y cn AUK. FEED PuttP UNIT COOLER 7.5 4.0 20sec Continurus 4.0 4.0 4.0 - El&C CUBICLE UNIT COOLER 2 1.0 20sec Continuous 1.0 1.0 1.0 - ANNULUS FILTER tE ATERS 133 20sec Continuous 133 133 133 133 UAY TANK CELL EXH. FAN 0.125 0.10 20sec Continuous 0.18 0.18 0.18 0.18 AIR C00 LED CONDENSER BLOWER MOTOR 60 45 20sec Continuous 45 45 - - AIR COOLED CONDEN$ER BlouCR MOTOR 60 45 20sec Continuous 45 45 - - Sk Pe 2 scn
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4 TABLE 8.3-1B CLASS lE DIVISION 2 DIESEL GENERATOR LOAD <!5T fConi'd) a i SEQUENCE UURATION APPLICABLE CONLiTIONS OF OPERAll0N NAME PLATE KW OF OF UV SGAliR5 DHR5 RitF LOAD DESCRIPi!0N _ HP (IN) OPERATION OPERATION (KW) (KW) (KW) (FW) PHTS Na PUMP PONY MOTOR 75 18.6 20sec Continuous 13.6 18.6 18.6 - IHTS Na. PUMP PONY MOTOR 75 18.6 20sec Continuous 18.6 IP.o 18.6 - . ARD BEARING FAN MTR. PRIM 2 2 20sec Continuous 2 2 2 -
,00 ARD BEARING FAN HTR. INTERM 2 2- 20sec Continuous 2 2 2 -
Y
$ EMERGENCY PLANT SERVICE WATER PUMP 150 103 20sec Continuous 108 108 108 108 i COOLING TOWER FAN 25 15 20sec Continuous 15 15 15 15 COOLING TOWER FAN 25 15 20sec Continuous 15 15 15 15 COOLING TOWEH FAN 25 15 20sec Continuous 15 15 15 15 3
EMERGENCY PLANT SERVICE WATER MAKEUP Put*P 7.5 5.7 20sec Continuous 5.7 5.7 5.7 5.7 TOTAL LOAD FOR 10 SEC IHROUGH 20 SEC BLOCKS Continuous 1567 1570 647 475 5$ Pe P 8m
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TABLE 8.3-1B CL ASS lE O! VISION 2 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE OURAi10N APPLICABLE CON 01110h5 OF OPERATION NAME Pt BTE KW OF 0F UV SGAHRS UiRS TMBOB LOAD DESCRIPil0N HP (IN) OPERATION OPERATION (KW) (KW) (KW) (KW) SWGR A/C Unit "B" (SUPPLY FAN) 25 15.2 1 min Continuous 15.2 15.2 15.2 15.2 SWGR RETURN FAN "B" 10 o.1 1 min Continuous 6.1 6.1 6.1 6.1 SG LOOP 2 SUPPLY FAN 200 141 1 min Continuous 141 141 141 - SG LOOP 2 SUPPLY FAN 200 141 1 min Eact up - - - - Co w SG8-18 SUPPLY FAN 60 37 1 min Continuous 37 37 37 37 SG8-IB SUPPLY FAN 60 37 1 min Back up - - - - 53 LUUP 2 EXH. FAN 60 37 1 mir. Continuous 37 37 37 - SG LOOP 2 EXpi. FAN 60 37 1 min Back Up - - - - i SGS-!B EXH. FAN 30 20 1 min Continuous 20 20 20 20 SCB-!B EXII. FAN 30 20 1 min Back up - - - - EN Pe F e CD Cn ww
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l l ' r I I I, ! f I ! i 4 l 4 3 TABLE 8.3-1B i CLASS lE DIVISION 2 DIESEL GENERATOR LOAD LIST (Cont'd) i , a t d l l ! 1 SEQUENCE 00 RAT 10N APPLICABLE CONDITIONS OF OPERATION l ) NAME PLATE KW OF Of UV SGAllR5 UHR5 iMc W - _ LOAD DESCRIPTION HP [IN) OPERATION OPERATION (KW) (KW) (KW) (KWJ a A8HX CELL UNIT COOLER 3 2.1 1 min Continuous 2.1 2.1 2.1 2.1 i ' ELEC EQUIPMENT UNIT COOLER 2 1.2 1 min Continuous 1.2 1.2 1.2 i.2 PRIMARY S0010M MAKEUP PUMP 'B' 75 63 1 min Continuous - 18 63 - t EVST NaK PUMP 'B' 150 117 1 min Continuous - 77 117 - i j y EVST N K PUMP 'B' BLOWER 15 12.5 1 min Continuous - 12.5 12.5 - j Cn N
- EWST AIR BLAST HEAT EXCHANGER *tt' 125 112.5 1 min Continuous - 63 112.5 -
i 5 TOTAL LEAD FOR 10 SEC THROUl.H I MIN BLOCKS Continuous 1827 2000 1211 581 6 I i (D Pg 4
-D .a 1'
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TABLE 8. 3-lH CLASS lE OlVISION 2 DIESEL GENERATOR LOAO LIST (Cont'd) SEQUENCE UURAi!ON APPLICABLE CONDITIONS Of OPERAll0N NAME PLATE KW Of Of UV SGAHHS OHR5 TMBud LOAO DESCRIPTION _ _ HP (IN) OPERATION OPERATION _(KW[ (KW) _(KWL_ _(Kg EMERGENCY CHILLED WATER P9MP 75 54 3 min Continuous 54 54 54 54 TOTAL LOAD FOR 10 SEC IHROUGH 3 F11N BLOCKS Continuous 1881 2054 1266 610 Y cn M EMERGENCY CHILLER 667KW 469 4 min Continuous 469 469 469 469 EMLHGENCY CHILLER CONTROL CENTER PANEL 5 4 min Continuous 5 5 5 5 TOTAL LOAO FOR 10 SEC THROUGH 4 MIN BLOCKS Continuous 2355 2528 1140 IUa4 Ek P El a e-a
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l I i i ) i 3 TA8LE 8.3 18 CLASS lE DIVISION 2 DIESEL GENERATOR LOAD LIST (Cont'd) i SEQULNCE DURATION APPLICABLE CONolTION$ Of OPERAllON , NAME PLATE KW of of uv 56AHR's uuR3 Irf3DB~ i
- LOA 0_DESCRIPTIUN HP (IN) OPERATION OPERATION (KW) (KW) [KW) (KW)
, EMERG. CHILLER ROOM UNIT COOLER 0.75 0.53 5 min Continuous 0.53 0.53 0.53 0.53 J I FAN H) TOR 60 36 5 min Continuous 36 36 36 36 FAN M) TOR 60 38 5 min Continuous 38 38 38 38 i I C) EVST SoulUM PUMP 'B' 75 63 5 min Continuous - 63 63 - ! w l :. i
- l TOTAL LOAD FOR 10 SEC THROUGH 5 MIN BLOCKS Continuous 2430 2666 1878 1159 6
l REFUEL COMM CHILLER A/C UNii 3 2.3 manual Continuous 2.3 2.3 2.3 2.3 1 I l-l i
?N nm
. 3 Q
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TABLE 8.3-1B LLASS lE DIVISION 2 DIESEL CLNERATOR LOAD LIST (Cont'd) SEQUENCE UURAil0N APPLICABLE CONulTIONS OF UPERATION NAME PLATE KW OF 0F UV SGAliRS DHRS IMdOB LOAD DESCRIPTION HP _[lN) OPERATION OPERATION (KW)
,__ _ _ _ (KW1 (KW1 ___ (KW)
ANNULUS COOLING FAN 300 215.4 nunual Continuous - - - 215.4 ANNULUS COOLING FAN 300 215.4 manual Continuous - - - 215.4 ANNULUS COOLING FAN 300 215.4 manual Continuous . - - 215.4 CGNT. CLE AN-UP SCRB EXH. FAN 250 154 manual Continuous - - - 154 ! CLEAN-UP FILTLR HEATER 171 manual Continuous 111 111 171 171 b o CLEAN-UP FILTER FAN 40 22.6 manual Continuous 22.6 22.6 22.6 22.6 ANNULUS FILTER UNIT COOLER 1 0.8 manual Continuous 0.8 0.8 0.8 0.8 CLEAN-UP FILTER UNIT COULER 7.5 5.3 manual Continuous 5.3 5.3 5.3 5.3 CLEAN-UP PUMP CELL UNil COOLER 3 1.9 manual Continuous - - - 1.9 CLEAN-UP SCHUB6ER CELL UNIT COOLER 2 1.6 manual Continuous - - - 1.6 CLEAN-bP CHASE UNIT COULER 0.5 0.4 manual Continuous - - - 0.4
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L/ l () N-TABLE 8.3-lu CLASS lE DIVISION 2 DIESEL GENERATOR LOAD LIST (Cont'd) SEQUENCE ObRATION APPLICABLE CONDITIONS OF OPERATION NAME PLATE KW OF OF uv 5GNtRs UHR5 IlW LOAD DESCRIPTION HP (IN) OPERATION OPERATION (KW) (KW) (KW) (KW) SEISMICALLY QUAL. FIRE PUMP CONTROLLER 25 13.1 manual Continuous 13.1 13.1, 13.1 13.1 EARTHQUAKE MONITORING INST. .5 manual Continuous .5 .5 .5 -0 4 PANEL LEAK MONITOR 3.86KW 2.57 manual Continuous 2.57 2.57 2.57 2.57 PANEL LEAK MONITOR 2.72KW l.84 manual Continuous 1.84 1.84 1.84 1.84
?
ta PANEL LEAK MONITOR 2.61KW l.73 manual Continuous 1.73 1.73 1.73 1.73 " O w CONTROL PANEL , 0,15 manual Continuous .15 .15 .15 .15 TMBOB CIRCULATING WATER PUMP (HOLD 300 220 manual Continuous - - - 220 75001590) TOTAL LOAD Continuous 2649 2385 2097 2402 m I FUTURE LUA0 (181 GRUWTH) Continuous 397 433 315 360
- IUTAL 1.0AD INCLUDING FUTURE LOAD Continuous 3046 3318 2412 2762 4 E ki nm 4
a
I O L 1 5 1 0 4 9 2 U 6 7 8 1 8 5 0 MW 1 4 5 6 0 1 4 UK 1 1 2 C B u u M I D 1 4 6 9 4 5 3 AW 6 1 0 2 7 7 4 OK 1 3 1 4 2 L 1 L U 1 7 1 6 0 8 7 MW 8 4 1 6 4 7 9 UK 2 6 2 2 7 8 0 C 1 1 1 1 2 S R H D D Y AW 1 6 4 5 4 8 9 OK 8 6 6 5 7 3 1 R L 2 3 5 4 1 2 A M M U S 6 1 3 D A O L R O L C UW MK U 4 1 1 1 0 7 5 1 0 0 0 2 4 5 0 2 8 2 5 2 6 6 6 2 5 8 8 2 O T 8 A S R R E E H L N A B E G A G S T D L E TW 4 6 0 4 4 8 9 S ~D L K 1 5 3 5 7 3 1 E 1 4 4 4 I 1 2 1 D . 2 N O I . S E L I V G J 1 7 7 1 5 0 9 A MW 1 6 2 8 5 3 4 I T UK 1 5 8 8 3 4 6 D L C 1 1 1 1 2 2 2 0 E v l R E S D S N A U L D 1 6 0 4 4 5 9 C S AW 1 5 6 5 7 1 1 U OK 1 4 2 4 2 B L 1 E c c l IMN T O s e e inm imn mi mni s n a u n Y 0 0 a R 1 2 1 3 4 5 M A M M U K S DC l 2 3 4 5 6 AO D A OL LB $BP $ O DP $ e L ( yNno I
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TABLE 8.3-lC CLASS lE DIVISION 3 DIESEL GENERATOR LOAD LIST THE PMCHINE SHALL ON RECEIPT OF START SIGNAL, (TIME 0), START AND ATTAIN RATED SPEED AND VOLTAGE WITHIN 10 SECONPS, AND ACCEPT LOADS IN ANY OF THE SEQUENCES STATED BELOW. SEQUENCE DURATION APPLICABLE CONDITIONS OF OPERATION NAME PLATE r.W 0F OF UV 5GAHR5 UHR5 IMSDB OPERATION OPERATION (KW) (KW) (KW) (KW) LOAD DESCRIPTION _ HP (11) 1% 10 see Continuous 115 115 115 BATTERY CHARGER (130VUC) _ BATTERY CHARGER (130VDC) 115 10 sec Back up _ _ _ _ LOAUS REQUIRED TO SUPPORT UPERATION OF DIVISION 3 Later 10 sec Continuous p OlESEL GENERATION UNIT y AIR C00 leu CONDENSER BLOWER MOTOR 60 45 10 sec Continuous 45 45 - - w
- W AIR COULED CONDENSER BLOWER MOTOR 60 45 10 sec Continuous 45 45 - -
75 18.6 to sec Continuous 18.6 18.6 18.6 - PHTS Na. PUMP PONY I4) TOR IHTS Na, PUMP PONY MOTOR 75 18.6 10 sec Continuous 18.6 18.6 18.6 - 2 2 10 sec Continuous 2 2 2 - ARD BEARING FAN MTR. PRIH ARD BEARING FAN MTR. INTERM 2 2 10 sec Continuous 2 2 2 - FF Fe
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TABLE 8.3-10 CL ASS lE DIVISION 3 OIESEL GENERATOR 10A0 LIST (Cont'd) SEQUtNCE OURATION APPLICABLE CONDITIONS OF OPERATION N44E PLATE KW OF 0F UV %AHR 5 DHR5 IMI LOAD DESCRIPTION _ _HP (IN) OPERATION OPERATION (KW) (KW) (KW) _(KW) ACS ISOLATION VALVES (3 Valves Each 1/2 hp) 1.5 1.2 10 sec Interinittent 1.2 1.2 1.2 1.2 ACS ISOLATION VALVES (3 Valves Each 1/2 hp) 1.5 1.2 10 sec Backup - - - - i RCS CONTROL POWER .3 10 sec Intermittent .3 .3 .3 .3 ACS CANTRUL POWER .3 10 sec Back Up - - - - 10 sec Continuous 10 10 10 10 P FHC SECONDARY COOLANT PUMP A 15 10 FHC SECONDARY COOLANT PUMP B 15 10 10 sec Continuous 10 10 10 10 FHC ARGON COOLING BLOWER 50 41 10 sec Continuous 41 41 41 41 FHC ARGON COOLING bl0WER 50 41 10 sec Back up - - - - STARTING AIR COMPRESSOR SJ 25 Later Inter. 25 25 25 - STARTING AIR COMPRESSOR 30 25 Later Backup - - - - Sk Pa P 0 0 0
.._. __ _-~ __ _ _ ___- __ _ -- -_ _.__.-_ _ _ __ -___ _ . _ . . _ _ . _ . _ _ . . _ _ . _ . _
i 9 9 9 t TAHLE H.) lC CL Ass IE DIVISION 3 DlL$EL GENERATOR LOAD LI5I (Cont'd) l SEQUENCE DUHAlluN APPLICABLE CON 0lTIONS OF OPlWAllON NAME PLATE FW OF Of UV 5GAlfR5 GiR5 Il4sTAI-LOAD DESCRIPil0N _ _. _ . HP _ __(INL OPfRATION OPERAll0N IEW{_(kg_ (kW)_. _ _(F WJ___ t STAHilNG AIR COMPRESSOR 30 25 Later Inter 25 25 ?i - STARilNG AIR COMPRESSOR 30 25 Later Back up - - - - STARilNG AIR COMPR($50R 30 25 Later Inter 25 25 25 - STARilNG AIR COMPRE5SOR 30 25 Later Back up - - - 3 3.0 Later Continuous 3.0 3.0 3.0 3.0 V ACUUM PUMP l W VACUUM PUMP 3 3.0 tater Back up - - - - i
% 3.0 3.0 ci v ACUUM PUMP 3 3.0 Later Continuous 3.0 3.0 VACUUM PUMP 3 3.0 Later Back up - - - -
VACUJM PUMP 3 3.0 Later Continuous 3.0 3.0 3.0 3.0 I VACUUM PuttP 3 3.0 Later Back up - - - - 3 3.0 Later Continuous 3.0 3.0 3.0 3.0 I VACCUM PUMP VACUUM PUMP 3 3.0 Later Back up - - - - O nc b, e 3 . , pLC
~ > - _ . . . _ - _ _ _ . . _ . . . . . . - , , _ . . , _ _ , . . , _ . _ _ . , . .-,_~r .-.-_ . _ _ , . _ - - ,._.~,.-_,_.-.,....--r___.-,_.-~m.,,,_,,. _my., ,o --% _. ,...m , , , _ - . _ . .__m..,.
i I AllL L 11.3-1C CL ASS If DIVISION 3 DIE SI L Cf NI R ATOH L OAD l lSi (Cont'd) i
,_. _. _ ___ ._ ~-
SE QUE NCf; DURATION APPLICAlil E CONDITIONS OF OPf RAllON NAML PLATE rW Oi of W SCAlms 7TE5 TRT0B- _ _l0A0 DESCRIPT10N_ ___ _ ,_, __ _ _ _ _ _ , __ _, _ _ _HP___(I N [_ OP E R A T I ON OPfRAll0N _(K_W }_ __ _(K W)_ _ ..(F WJ_ _(F W } _ _ VACUUM PUMP 3 3.0 Later Continuous 3.0 3.0 3.0 3.0 i VACUUM PUMP 3 3.0 Later P,a c k up - - - - VACCUM PUMP 3 3.0 Later Continuous 3.0 3.0 3.0 3.0 i VACUUM POMP 3 3.0 Later ba(.h up - - - - VACUUM PUMP 3 3.0 later Continuous 3.0 3.0 3.0 3.0
; y VACUUM PUMP 3 3.0 Later liack up - - - -
N
@ TURNING GE AR MOTOR 20 17.2 Later Continuous 17.2 17.2 17.2 17.2 l ! TURNING GE AR O!L PUMP 50 42.53 later Continuous 42.53 42.53 42.53 42.53 i
- ;PILGV BACK MOTOR 7.5 1.0 later Continuous 7.0 7.0 1.0 7.0 Eb nm
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(% )s TABLE 8.3-1C CLASS lE DIVisl6h 3 DIE 5EL GFNERATOR LOAD LIST (Cont'd) l SLl#JENCE DORAT10N APPLICABLE CONDITIONS OF OPEWATION i NAME PLATE KW OF 0F TV SGATES OffRS THBiTF l LOAD DESCRIPTION HP (IN) OPERATION _0PERATION (FW[ _ (KW) ,(KW L _ j g _ MISCELLANEOUS UPS SYSTEM 82 Later Continuous 82 82 82 82 l MISCELLANEWS UPS SYSTEM 82 Later Continuous P2 82 82 82 l BATTERY CHARGERS (48VOC) 11 Later Continuous 11 11 11 - (29 5.5 KW) BATTERI CHARGERS (130VDC) 8.8 Later Continuous 8.8 8.8 8.8 - (29 4.4 KW) U BATTERY CHARGERS (130VDC) 600 Later Continuous 600 600 600 - 4 N (49 150 KJ) BATTERY CHARGERS (130VOC) 300 Later Back up - - - - (29 150 KW) BATiERY CHARGERS (260VDC) 112 Later Continuous 112 112 112 - BATIERY CHARGERS (260VOC) 112 Later Back up - - - - Continuous 1361 1361 1211 314 TOTAL LOAD Continuous 205 205 192 41 FUTURE LOAD (157, GROWTH) TOTAL LOAD INCLUDING FUTURE LOAD Continuous 1572 1572 1469 361 WF Pe
~P L_-- - - . _
TABLE H.3-10 DILSEL GENERATOR LOAD LIST NOTES l Sil/JtHCE UURAll0N APPLICABLE CONDITIONS Of OPfkATION NAML PLAIE rw of Ot 'JV 5CAliR5 DI{RS TMUEf~ LOAD DESCRIPil0N _ _ _ _ HP _(IN) OPERATION _ _ 0PENATION _ _ {(W_} _ j kW) (KW) (F{ NOTES: 1. Future Load Growth of 15% is propcttionally distributed to each load block.
- 2. For all mutors assume full voltage starting current to be 6$0% of motor's full load current.
3 Motor starting puwer factor and running power factor will be assuined as list bt> low: HORSEPOWER STAR 11NG POWER FACTOR RUNNING POWER FACTOR 5 HP and Below .62 ' .19 Co w 7 . '2 # - 15 HP .54 19 20 HP - 30 HP 45 ./9 40 HP - 60 t'P .37 .81 75 HP - 125 HP .32 55 150 HP and 200 HP .26 .85 250 HP - 350 HP .22 .85 400 HP '90 HP .19 .85 600 HP and Above .17 . ti 5 900 IF and Above .16 .85 40iES: 4. The 1050 HP '.GAHRS auxillary feed water pump drive motor will be started autoinat*<. ally at 10 sec. However, while the Diesel Genarator is fully loaded this pump could tw tripped and restarte,d. Oh (D M 5. At 9 seconds the magnetizing inrush current associated with two 1500 KVA (4160/430V. DELTA 41YE, 2 5.75%) and one 1000 KVA (41bO/480V, P2 oat A-wye. i.5.iS%) substation transf ormers wiii be imposed on each ot vision 1 and 2 Otesei Generator unit. w ." CO Ch Hw O O O
. _ _ . . _ _ _ _ _ __.m _ _ . . . _ . . - - - _ . . . . . . . . . - , . _ .
- . - . _ m _ . . _ . . _ . _ . _ _ - _ . _ . . . . _ . _ ._ . _ _ _ . _ .
!i @ O e i 4
+
TABLE 8.3-2A CLASS lE DIVIsl0N 1 125V DC LOAD LIST 4
~ ~
l NtTRMAL MA C CUN(jl T. EMtRGENCV (2) LOAu l LOAU. AMPS. AMPS. DURATION REMARKS ,8 DESCRIPi!ON 4.16 KV SWGR. AND 480 V USS BREAKER LOAD 22 156.8 flHST I MIN. 22 NEXT 119 MIN. C.G CONTROL PANELS 11.2 11.2 0-120 MIN. j LOCAL AND MCR (0.7 KW) 0.G FIELD FLASHING (7.5 KW) - 60 FIRST 1 Mih. i D.G. GOV. OIL B00$iER PUMP, I HP - 40 FIRST 1 MIN. , Co 10 NEXT 119 MIN. j I y PHIS 1 UR PPS BRE AKERS - 12 FIRST 1 MIN. 68 LAST 1 MIN. PHTS 2 UR PPS UREAKERS , 12 FIRST 1 MIN. PHIS 3 DR PPS BREAKERS _ 12 FIRST 1 M1N. PHIS 1 DR PPS TEST BREAFERS _ PHIS 2 UR PPS TEST BREAKERS _ PHIS 3 UR PPS TLSI BREAKERS _ IHTS 1 OR PPS BREAKERS _ 12 FIRST 1 MIN i i og IHTS 2 DR PPh BREAKERS 12 FIRST 1 MIN i. 4 $. ms 0- IHIS 3 DR PPS BHEAKERS 12 FIRST 1 MIN. j _ To m
-w i
4 - - - ._. _ _ _ _ _
I AltL E ti.3-2A CLASS lE DIVISION 1 125V DC (UA0 LIST (Cont'd) pgggg7_(7 L LOA 0 HA C CDNT. DESCRIPil0N LOAD-AMPS. (MikGENCY l'MVS . DU (2)iiATi6N REMARKS IHTS 1 LM PPS TESI BREAKERS - - - (HIS 2 DR PPS TL5I BREAKERS - - - IHIS 3 lM PPS IESI BRE AKERS - - - CIS BRE AKER PANEL 1 (0.15 KW) 1.2 1.2 0-120 HIN. 120 VAC BUS 12N1f008A AS INVERitd LOAD 391 429 FIRST I MIN. NOTE (3) P 393 NEXT 14 MIN. La 319 NEXT 105 MIN. b o _ 10lAL IN AMPS 425 782 flRST 1 MIN. 4 31 NEXT 14 MIN. 403 NLXT 104 MIN. 411 LAST I MIN. )
- Pa P
I
- G G G
O D TABLE 8.3-28 CLASS IE DIVISION 2 12SV DC LOAD LISI LOAD EMERGENCY (2 DESCRIPIlON LOAD-AMPS. XWS. 6i ATIUN REMARKS 4.16 KV SWGR. AND 480 V USS BREAKER LOAD 20 136.8 FIRST I MIN. 20 NEXT 119 MIN. D.G CONTWOL PANELS 11.2 11.2 0-120 MIN. LOCAL #40 ftM (0.7 KW) D.G FIELO FIASHING (7.5 KW) - 60 FIRST 1 MIN. D.G. GOV. OIL BOOSTER PUN , I HP - 8 40 FIRST 1 MIN. 10 NEXT 119 MIN. cu PHTS 1 DR PPS uHEAKERS ~ 12 FIRST 1 MIN. 68 LAST I MIN. Y a PHTS 2 DR PPS BRE A(ERS _ 12 FIRST I MIN. PHTS 3 DR PPS BRE AKED.S _ 12 FIRST I MIN. PHTS 1 OR PPS TEST BREAKERS _ PHTS 2 OR PPS ILSI BREAKERS _ PHIS 3 L't PPS TEST BREAFER5 _ IHT5 1 DR PPS UHEAKERS _ 12 FikST 1 NIN gg C lHTS 2 UR PPS bdEAKERS _ 12 FIRST 1 MIN nm FIRST I MIN. g IHTS 3 UR PPS BREAKERS _ 12 G-SS 1 i
TABLE H.3-28
. CIA 55 IE O! VISION 2 12SV DC 10AD LIST (Cont '<1)
~
tiCRMXl ~ Ul LOAD 6)N T . 2) DESCRIPil0N LOAO-AMPS. [Mt PGE NC Y (DURATTUN 7J4P5. RLMARKS 1HIS 1 OR PPS TESI HREAKERS - - - IHIS 2 OR FPS TEST BREAKERS - - - IHTS 3 OR PPS TEST BREAKERS - - - CIS BREAKER PANEL 1 (0.15 kW) 1.2 1.2 0-120 MIN. 120 VAC BUS 12NIE008A AS INVERTER LOAD 332 420 FIRST 1 MIN. NOTE (3) C3 385 NEXT 14 MIN. w 354 NEXI 105 MIN. i N TOTAL IN AMPS 414 141 FIRSI 1 MIN. 421 NEXT 14 MIN. 396 NEXT 104 MIN. 464 LAST I MIN. i i l l P8" 1 O O . O
G @ @ TABLE 8.3-2C CL ASS It DivlSION 3 125V DC LOAD LIST NORMAL (1) LOAD MAI. CUfH . EMERGENCY (2) DESCRIPTION LOAD-AMPS. XMP S. DUR ATIOf4 REMARKS SGAHR5 - STEAM TURBINE GOVERNOR CONTROL 4 4 0 120 FIN. (1 KW) 120 VAC uus 12NIE008C 208 221 FIRST I MIN. (NOTE 3) A5 INVERTER LOAD 182 NEXT 14 NIN. 165 NEXI 105 MIN.
,m TOTAL IN AMPS 212 23I F135T 1 MIN.
u 186 NEXT 14 MIN. g 169 NEXT 105 MIN. w f l l l l 1 P! P
_i_ABL E 8. 3 20 DC L O AD L I S T N'))Q (1) Noruta; - (Maanmma continuous load) plant nonaal operating 'oad with power supply either f rtw the battery or through the battery charger. (2) Emergency - DC tus load during the caergency operation for specific time duration following a complete loss of AC system and with the tuttery supplying power to the load. (3) The inverter connected to DC ous as load is considered the actual KW load and is converted to inverter input D.C. current as p r " Application uf Exide Static Uninterruptible AC Power Systems" Section 56.004, Exide Bulletin 212, April 1911. 1000 DC Input Current = TIE [ Efficiency) Load FVA) (PF) (1.75 //C) (No. of Cells) co
. 1000 Y
- 103I(load Il]M/KW{W(No. of Cells) m 4
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TABLE 8.3-3 00etit0Nf 4T ARRANriMENT_,CRITtHp 1 Applicable Criteria for
- Equipment Design Basis Event Considered Arrrangement or Design ,
Diesel generator units Tornado-wind, missiles and earthquake The diesel generator units will be located in the diesel genera-a tor butiding which is Setsmic I Category 1. The structure is designed to protect the diesel 1 generator units fraa any cre- ! dlble tornado wind, missile and earthquake damage. The crt-teria applied to Category I
, structures associated with the
.! co design tornado are given in g Chapter 3. s CD Flood (natural) The diesel generator units will
- be located above design flood
- 1evel given in Section 3.4
- Temperature and humidity Proper ambient temperature or humidity is maintained in the Diesel Generator rooms as described in Section 9.6.5.
Fires The diesel generator units will be located in individual rooms, within I the diesel generator building, separated by concrete wall barriers. The roons will be individually pro-gg tected by fire extinguishing systems as described in Section 9.13.1 o
- n. ::s CL s W*
O
-m
TABLE H.3-3 (Continued) Applicable Criteria fo. Equipment D_es_ign_Hasis Event Considered Arrrangement or Design 3 Diesel generator units Accident-generated missiles The concr ete wall barrier s bet-ween the diesel generators will be designed to withstand any credible missile generated by a diesel generator casualty. The location and design of the diesel generator building will protect against any credible accident gererated enternal missile. Fire protection systein operation The fire protection piping located in the individual CO diesel generator rouns is ca 8 Seismic Category I. Each diesel is individually pro-E$ tected so that a fire in one diesel generator ro#a will not actuate the cunponents of the f'.re prutection system in any othee space. Accident-generated floods, sprays, or jets The Diesel Generator Buil lir.g is located away f r au any L.e. dible piping, and will be j designed to protect the diesels from the worst cre-dible accident-generated floud. E?b[ nm o :3
- p. .CL
'O CD ch EdLO O O O
rs O O lV U LJ TABLE 8.3-3 (Continued) e Applicable Criteria for Design Basis ivent Considered Arrrangement or Design Eguipment s 4.16 KV AC Power Distribut ton System Tornado wind missiles, earthquake The 4.16 KV Class IE systen f-a) 4.16 KV Class IE Switchgear located in the Diesel Generating Butiding. Reactor b) 4.16 KV/480 V Class IE Unit Service Building a.id the Steam Substations (including 480V Generator Building. These butidings Switchgear) are 5alsmic Category I structures, de$lgned o protrct against any credible wind-toriado damage and j earthquake. CO Floods (natural) The above buildings will be ca c) Cable grotected against design flood e level. f Temperature and humidity Proper ambient temperature or humidity is maintained in the Class IE switchgear room as described in Section 9.6.5 Fire A description of the non-sottum fire and sodium fire protection and detection s system for Category I struc-tures is given in Sections 9.13.1 and 9.13.2. E?bi , eg l .c2. I C l l l
T ABLE 8.3-3 (Cont inued) Applicable Criteria for Egtipment Destyn Basts Event Considered Arrrangement or 0* sign s Category I structures are designed t: .itnstand eater-nally generated missiles. Physical separation of com-ponents in different power divisions will be such that no credible intctnal accident-g acrated missile will disable more than one safety dt vision. m Accident-generated floods,. sprays, or jets The arrange >rient of Class IE
" systems will be such that no credible accident-generated Co spray or Mt will disable more than one power divis1on. The a rra ngem.m t will also provide protection against the saaxt>Jm j posstble a:cident-generated flood.
s 430 V Class IE AC Power Distribut ton System a) 44J V tbtor to.itrol Center Tornsdo wind, earttgaake The 430 V Class IE MCCs are located in Olesel Generator b) Contain4.ent Electrical y Building, Reactor Service Q oo Penetrations But iding, Steam Generator Butiding, Control Scilding and { c) C.bles Emergency Cooling to crs. All
~. of these butidings are Seismic Category ! striactures, .$ wm , designed to protect agalikst any credible winJ-tornado danage and eart 1 quake.
l i e G 9
-I O O O I l
i TABLE 8.3-3 (Continued) 3 Applicable Criteria for Equipment Uestyn Rasis Event Considered Arrrangement or Oestun
> Floods (natural) ' temperature, humidity. Identical with the 4.16 .;f fire and Accident-generated missilet, floods, System.
sprays, er jets. s Class IE DC & Vital Plant s Power Distributton System a) 125V UC Battery Chargers Tornado wind, earthquake Identical with the 480 V system. b) 125V DC Battertes Floods Ideat* cal with the 4.16 KV system. c) 125V DC Switchgear Temperature-hurnidity Identical with the 4.16 KV system. c3 w d) 480-120/208V AC Transformers e -
@ e) 120/208 AC Inverters f) 120/208 vttal AC Distributton >
Pa..eIs g) Cables Fire Identical with the 4.16 KV system. Accident-generated missiles Each DC battery is separated from all others by a concrete wall con- I partment. The conpartment will be j ventilated to dissipate hydrogen 3 given of f by the battery in order to t, l preclude a fire or explusion. The i battery will also be separated frLa , ctop g=. its' associated DC and UP5 equipment. P$cL Accident-generated floods, sprays, or jets identical with the 4.16KV ,ystem. e-* = ; O
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- 2. FOR EI ECTRICat ORael40 INDElt. SEE CondPUTERIZED ora # LNG LIST i K S. AL L EEVICES AM LOCATED IN Leelf Stattf af!0NS U0S
- a. ELECtelCat EQUtPENT TO BE
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5 4 3 2 l l l l 1 GENERAL NOTES
- 1. FAMOLS S 48BEVI&T10NS Raf4HH3038
- 2. FOR ELECTRIC at ORARING lt0EX. SEE CO@viERIZE0 DRAE14 Ll$Y 5 S. g CE AM LOCATED TN Laelf e 4. ELECTRICAL (2119WNT TO BE INSTALLED PER ELEC(BICat i IN5f attdNT SPECIFICaf 8 CMS =j E ALL ELECTRfCALLY OPERATED 15EMENs 4 am R FRONT FOR TEST ING R,55MS j'2 E. T@iCATED w 0F uoTORS AM h&E DLATE RATIssGS j S 7. EacM CIRCUf f IFEMER 94LL BE 2 EQutppfD RITN aN ADJUST &SLE
] 2 Sul f D S T A TE Tv9E SE R IES OVER j pyfppga WNY MIWING DEvlCE mf 0 LNG
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W/ Ah 40U5 OvE h f10 am SHORT CIRwlY PROTECTION (FCNR Ou MOTOR FEEDER E ALL gamaLLY OPERATED SNEMERS. E ECEPT INCOMIW CIRCt!T INE MEJtS. g paF p 2ge L EQUIPPED RITN Staf W.iN CQs m 0 SRitor. UTILIZES u!NI ATWIZED CONTROL V SRI TC4 5 RI TN INTERPOStea6 LOGIC. YQ 8 0R DE T a [LS SEE TNIviDuaL ELEENT ARY bl&GRauS IDID I' 9. OEYa! LED PROTECTfvf MLATING TRIP 91NG anE) atases FUpstTIOp6 ASE S>EJ8De ON ELEENT&RY CNLARINDS NOTES
- 1. CLASS IE. SEISulC CATE9 CRY: 1
- 2. RADIATION 20hEt UNFFJTRICTED 3 CQuPamTENT mamER 94LL SE _
PNF I AED AS 61vLm BELLee US3 Corf N0 94713 PS I S 12.N.! i2 a02E0294 s PS . . .
- 4. BREMEn SvenETalCat (NTEmLp?!se C& TING CQmeSPOPOS TO TbE $
#0Lt0 RING emuER FRauE Sins.
SvteETR a rR.E azE RIN, mE
.NTE-Ti ICAL.n R i800 meS so,Cm 3000 auPS 6%000 A.e9 FS E CLASS IE FEEDER INEAKERS FOR CLASS-Y 9em R L E
9 i LEGEND fJ2 CLASS it SYSTEW LDAD SEDDING
'" ' - - ~ SvuBOLS 2 TA-DEv!CT TRfPS ON LOSS OF j(2pt/ppgg v0LTat.E, flECLOSES AUTomaflCALLV p 480- 4 20V Tu-DEVICE TRIPS ON LOSS OF VOLT AGE, CLOSES M488MLLY Tse-CEv!CE TDTP DES NOT OCCLA
,,, Oh LOSS OF YOLTAGE
$ CLASSIE DWI m culi ,E Du a M-) F" e a
i - e FIGURE 8.3-5 480V Unit Substation One Line Diagram j Sheet 2 of 4 8.3-102 Amend. 63 (NE530-2) Dec. 1981 6 i
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d 3 2 I I 1 l 3 GENERAL NOTES
- g. Svamais a masqvgaf tgeS saRD-0-00Se
- 2. FOR Et ECTelCE DaaSING f tOER. E!
CwPUTDIZED ORaelse LIST K . S. EL DEvtCES Ast LOCATED IN L8ert St.SST A T I:Pf5 UDS
- 4. EL ECTRICE EQUIRE NT TO GE INSTE160 PEP EuCTRICat j INSTALLATION SPECIF ICAT10h L att ELECTarCALiv OPERATED SHEaaERS Sett BE EavlPPED SITH ST AEARD PU'selvTTONS ON T4 BEaAER FRohY FOR TESTING REFOMS
- s. factCaTED ie or u0 TORS ARE had PL ATE RATINGS j
- 7. E 4CM Cis10)i f WE MER Det L M 2 E WIPPE 0 s t TN aN afutef am E S(I I; Statt T'PE SE RIES OVERCla5ENT
'/PS2a TRIPPf 40 CDICE PRnv10lNo Lceso N 20y T iet /SMasti TlalE OvtRCts5ENT aac Sees? CIRCUlf P880'ECY ices s FCm gafN.
sad if0 TOR CONT 8k1 CENTER FEEMR 814 aalDS n. a*O LOsso T ItE/ INST &NT&at OtsS OvERCutsu es7 ape 9(NT CIRCul f PHOTECY l0N ( FOR
- l A'O l v iotsat es0TGt LL wa80Riv FEEEER OPEmafE0 SEEMERS) 85EskRS.
E RCE P T lesCOulIG CIRCUt? Bss asEOS. S>w L SE EQUIPPED WITH H 3J2 Spe ssT TRIP C0!L S. mafM CrosTROL 80asO Set 1Cwf 40 UT!LI?ES WINiaft5alZIO CostTROL S#1TCHS #1TM INtEEPOS!NG LC*3tC. FOR [ eta!LS. *lE E 18elv!OuaL ELEhE hT ARY DI AGRaasS - S. OEYaILED PRO'ECTTvt RE1aY!No. gg YRIPPInsG asO at ares FUNCTIOpsS ARE S*E41*s ON ELEnEhf ART (snasteso$ NOTES o
- n. Ct ASS sE. SEISu!C CATEGopvil UDS 2 RAClaT10h Zorns I UDS
- 3. Coup ARTesENT *eAeER 94 L BE PMF isED AS SivkN BEL 0sh -
USS Comet eso PREFlu 12h! E C12A PS2 8 12 hie 0328 PS22
- e. 85447ER SvingTetCat (NTE RsaFTiess ReTIase CCss455905 TO T4 I 8 0LL0st!ss3 BMARER FRaaE SIZE $a BRE uta SvtaKTDICat FRain SITE INTEHfpT!sse siaf tess IfnOO assP5 50,000 aaPS 3300 aaFS 6L 000 aarS L
- LASS st FEEDER BREMER FOR -
class IE tsCC SMALL BE EQulPPED elTM $>4As? TRIP CCIL E
~
LEGEND CLASS If SYSTEu LOAD SED 01NG S VlBOL $s - - Ta-CEvtCE TRIPS Oss LOSS OF v0LTaaE. SIECLOSES iD2 AJTOtsa f ICALL V O t /pSpg Tu-MVICE TRIPS ON LOSS OF D- t 20V v0LT AGE. CLOSES has0 ALLY TieMv!!1 TRIP DNS 8s07 OCCIAI CDs LOSS CF vtLT AGE _ e etau n sv t E n Ass it av ? u2e l' t C @i FIGURE 8.3-5 480V Unit Substation One Line Diagram , Sheet 3 of 4 (NES31-2) 8.3-103 Amend. 63 vec. 1931 - A J
*c' '
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4 i . i i c QENERAL NOTES
. 5,.a3 . a oiafio e ea804H103b
- 2. Tom ELfWitat tsaalg teEIEn, WK CouruTEAE.'W Dhasi4 LI5f E
- 3. EL NVICIS aar LOCafED I4 Unit SASf afloudS WDS
- a. ELECTWICat (31Tresw? TO K
!*MiaLLED pea itaticitat lesSf ak.Laf ttes WECIF itat t0Bs -
5 ALL FLECTelCALif praafED NREMERS DenLL BE thatsW(D alfW Stamase puhelf fCD5 Oh inE WEmpEn Fn0NT FCub TESfine map 0KS
& f*CTCaffy ne y oFJt0MS aat samen PLafg saflasst j
- 7. Each CT80/17 Outa8ta SeaLL E
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faippfee OEv1M #EDv10f Lt3E9 fief /DCpf flE OufMWT afe Sce? Clacuf f WWOftCTttas Efem gaf4_ asc ascf0h CONTEEE. CintEB FEEMR WIE aaE8DS L asc L<3e f ts/ EQJ pgIQ tF IncinfChat esotOD FIEDER WEAREESS ALL isaamatty cygaaTED SIEas0ES. OE Eat!PPED #ifM DeAT g S. maru Ctsstaa 30aAD SelfDstas ufILIZES ul=InfuD! LED CohTAtt Self0ES egime twTEWCeles LOS!4 FCst mistLS, ME lactylguag ELgaEnfest? 01aemaan _
& NTafLED pa04CTTvt EElevite.
Taiselme aos aLang FUICfitas aK Does oss ELKsEnf am? OmasteeS NOTES o
- 4. CLASS af MI5astC Catteceva 8 USS-42anikO3Sa a s2hlt333 astse-class sf. 9EISu!C Caft90Rvt III 12enIE034a e BasaltaSet
- 2. naciaf!Cas 2t>E: LeelESTRICTED
~
S. Cwa 8'aEmT usagra DeaLL M PEES J EEL as D]vEm KLOGa USS CCapt ac sugF!g 12h1ECSM PS25 628stEOSE PS24 8 2m !E0344 PS25 g s 2hlE r,Sas PSJS eftat Tw a- WENTS marine CORsIESW'p0*CS s to 'Etut#f 74 tse FR.LOeIne 8AEARED FRaef SIZESs OREpin Svtaf falCAL FaaaE SIFE INTEEDILFflagg aal[ggg - 800 assPS 30,000 aerS
#600 asps 50.000 asps E
!. E'GEND D class st SYS4m LCa0 SEDCIMO S fie0LSs Ta-Mv!G TaloS Cps LOSS W FOLiaot, eECLOSES auftasaf!CALLY -
TM-MV f E 79199 081 LOSS F v0LTaGE. CLOSES eweALT TW-CEv1CE TBip DOES 807 OCCW Oss LOSS OF 90LiaoE c FIGURE 8.3-5 480V Unit Substation ~One Line Diagram e Sheet 4 of 4 (NE528-0) 8.3-104 hnend. 63 Jec. 1981 _ A
9.4- ' PIPING AND EQUIPMENT ELECTRICAL' HEATING 9.4.1 Design Basis , The piping and Equipment Electrical Heating _ System provides the ( electrical heaters, electrical heater mounting hardware, heater power con-
! trollers and the related temperature measuring and controlling instrumenta-tion and equipment required to heat the following sodium containing process systems and components:
Reactor Enclosure Reactor Refueling (Storage Tank)
, Reactor. Heat Transport (Primary and Intermediate) Systems 47l Steam Generation System (Dump Tanks and Sodium Water Reaction Product Tanks)
Auxiliary Liquid Metal System Inert Gas Receiving and Processing System Sodium Impurity Monitoring System This heat is required to preheat these sodium process systems prior to fill, to prevent sodium freezing when system heat sources such as reactor i decay heat and pumping heat become insufficient, and to maintain pre-established temperature differences in the system. , To perform the dry heat-up function, the Electrical Heating System a shall be capable of preheating the sodium process systems from ambient tem-perature (70 F) to any temperature between ambient and a' maximum of-
, aoproximately 450 F before the system is filled with sodium, at a rate cetermined by the particular sodium process system requirements.
The Electrical Heating System shall also be capable of providing the applicable heatup rate for the particular system or components when filled with sodium, and of holding process system temperatures when filled with i sodium. Heat provided by this system can be used to melt frozen sodium-in piping or components. Freezing of sodium in major systems or components is ' considered unlikely and is an abnormal event. Melting of frozen sodium is not safety related. l The heater physical mounting arrangement and the electrical protec-l tion of the heater circuitry shall be designed to preclude damage to the components being heated. Heaters and the associated mounting hardware that are applied to components which are safety related shall be designed not to impair the ! ability of these components to perform their safety function during or after a_ design basis event. Those safety related components which require heaters are listed in Table 9.4-1. i l i i Amend. 47 Nov. 1978 9.4-1 i l C __
9.4.2 System Descriotion The electrical heating and control system provides oower to the tubular O heaters or mineral insulated (MI) heating cable mounted on the piping and/or components of the systems indicated in Section 9.4.1. The heat rates required by different components are controlled by using thermocouples to monitor piping and component temperatures and to adjust the power supplled to the heaters, by means of 3 mode proportional temperature controllers and solid state relays. Tubular heaters apply heat via a spiral wound nickel-chromium alloy resistance wire Insulated from its containing metal tubular sheath by tightly packed Magnesia (Mg0) powder. Several inches on each end of each heater are unheated having a heavy electrical conductor to the electrical termination. In certain cases, i.e., selected piping smaller than 10 inches 0.D., the heat is applied by mineral insulted heating cable that consist of a metal sheath drawn down over a MG O Insulated single heating element of nickel-chromium-Iron wire. The heaters will be stood off from the sodium containino metal boundary for the safety-related piping and equipment which is listed in Table 9.4-1. The heater sheath is not electrically insulated from the metal boundary. For systems and components not listed in Table 9.4-1, the heaters may be c!tNr stoodoff or applied directly in contact with the sodium containing metal boundary. Groundfault interrupt (GFI) circuits prevent metal damage in the unlikely event of heater arcing. Chromel-alemel tirermocouples are used throughout the systems for controlling the operation of the electric heaters and for monitoring the temperature of the metal boundary of the sodium containing piping and equipment. Thermocouple compensation is provided for all thermocouples. Thermocouples on piping are located on the opposite side of the pipe from the-heaters and at a control temperature point to control the average heat-up rate of the pipe within specified limits. On equipment, the thermocouples are located in the spaces between heaters for both monitoring and control purposes. Control of any heater or bank of heaters is by automatic control. This centrol providos for continuous and automatic adjustment of heat based on an error signal generated from the differsuce between the temperature setpoint, as set by the plant operator, and the temperature feedback signal from the thermocouple monitoring the temperature of the sodium containing metal boundary. The controller compares the temperature control setting (ramp rate in heat-up mode and setpoint in hold mode) as set by the plant operator; to the actual temperature of the sodium process metal, as measured by a O 9.4-2 Amend. 63 Dec. 1981 < )
thermocouple, and generates en error signal. The error signal Is converted (] Q- Into a corresponding "on" to "off" ratio of output voltage which is applled to a solid state relay which controls the AC power to the heaters. The required power is controlled by conducting a fraction of the cycles of the 60 hertz. For example, 50 percent power would be conducting every other cycle, 90 percent power would be omitting one cycle of every ten, 10 percent power would be conducting every tenth cycle only. Heaters are arranged in a particular control circuit according to the uniformity of heating required by a bank of heaters. This type of heat application is called zoning. A heater zone is an area that can be heated with the same unit beat input and can be controlled from a single temperature Indicating point that is representative of the zone. The temperature feedback thermocouple is located in a representative position within the pipe run or area within the heated zone. All heaters are in operation continuously during dry heat-up, (system completely empty). Some heaters will be in operation continuously for the occasional fill and drain situations in some piping and components such as cold traps, dump tanks, gas equalization lines and other components. For all other normal operations (start-up, hot standby and shut-down) the heaters will be in operation only intermJttently to make up for the heat loss through the insulation. p) Loss of off-site AC power is the only abnormal condition for electrical (V l heating. It mght, if of sufficient duration, and lacking other heat sources (e.g. decay heat) result in sodium freezing in pipes and components. Melting of frozen sodium will necessitate the sequential operation of heaters from free sodium surfaces in order to avoid undesirable pressure build-up in piping or components. A dedicated, pre-programmed direct digital control system is provided, on an Individual loop basis, for the Reactor Containment Building, Steam-Generator Building, and Reactor Service Building. The system is modular, to permit physical distribution of the various functional componenti and to facilitate future expansion and The upgrading. The panels and Operator. Control Centers are located in these three areas of the plant. An additional Operator Control Center (Master) is located in the Main Control Room. The system arrangement is shown in Figure 9.4-1. 9.4.3 Safety Evaluation ' As discussed in PSAR Section 3.2.3, the piping and equipment electrical heating and control system has no specific safety classification. The heating system is not essential for the safe shutdown and Isolation of the reactor,
/3 b
9.4-3 Amend. 63 Dec. 1981 l
nor will failure of the system result in e release of radioactive material. In those cases where heaters are applied to safety related components, the heaters are not required for the component or the associated system to perform its safety function. Heaters and supports affixed to Category I components are qualIfled to that category to assure physical integrity. Heater failures originate at the heater element wire, promoting arcing which propagates outward to the heater sheath. This is the worst single failure mode for the System. The faliure mechanisms that can cause thIs falIure mode can be attributed to operational and design factors. Operationally, the f ailure mechanism can be caused by (1) excess current application, (2) cross over in mounting of adjacent heaters, and (3) Improper setting of protective devices. For the design factor, the failure mechanism can be caused by irrproper heating wire design, fissures in the magnesium oxide and minimum bend radii. The effect of the fallere will not affect the system It is heating. In the event a trace heating element in the HTS or auxiliary system falls, a thermal gradient in the piping or component will be produced. This thermal gradient would then Induce a thermal stress in the piping or component. The design process will evaluate these potential thermal stresses in order to identify trace heater locations so that a loss of one heater will not result in unacceptable stress levels. The design process will also identify the number of trace heaters that could fall before corrective action is required. The design evaluation will include dry heat up, heat up with sodium, and normal operation for both sodium containing and any normally dry portions of the system. Oi 9.4-3a Amend. 59 Dec. 1980 1
S O G T ABL E 15.1.3-3 SYSTEMS ASSUMED OPERABLE TO MITIGATE THE CONSEQUENCE S FOLLOWING THE OCCURiiNCE OF EACH ACCIDENT EVENT 1 l Required Operabia ! f.rcats . ___$ystem hlmary Jocondary 1 15.2.1 Anticipated Events I 15.2.1.1 Control Assembly Withdrawal et PPS followed in long Flux-Pressure flux-Total F low Startup term by decay heat Flux-Delayed Flux removal (1) l*, 2.1.2 Contrcl Assembly Withdrawal at FPS f ollowed in long High Flux Flux-Total Flow Power term by decay heat Flux-Pressure removal 15.2.1.3 Selsn.!c Reactivity insertions-00E PPS followed in long High Flux Flux-Total Flow term by decay heat Flux-Pressure removal H 15.2.t.4 Small Reactivity insertions PPS followed in long High Flux Flux-Total Flow fH term by decay heat removal e Co - 13.2.1.5 Inadvertent Drop of a Single Control PPS followed in long Flux-Delayed Flux Mod i f ied uc lear Rod at Full Power term by decay heat Rate f removal i i 15.2.2 Unlikely Events 15.2.2.1 Loss of Hydraulle Holddown PPS followed in long High Flux Flux-Total Flow I term by decay heat Flux-Pressure !
- removal 15.2.2.2 Sudden Core Radial Movement PPS followed in long High F lux flux-Total Flow a
term by decay heat Flux-Pressure removal 15.2.2.3 I i Maloperation of Reactoc Plant PPS followed in long High Flux Flux-Total Flow i
, Controllers term by decay beat Fl ux-Pr essure :
L removal mN an !-
* :'S CL w*
D e Co m - W Gb i 1 1 P n - , , , . . . - - -,.--n _ . _ - _ . - - - . . . _ - . . . . . . . . . , - . _ , _ . - - , - - - - - - . . i
TABLE 15.1.3-3 (Continued) Rojulred Operable Systom Primary recondacy Events 15.2.3 Extremely Unlikely Events PPS f ollowed in long Speed Ratio Flow Ratio 15.2.3.1 Cold Sodlum insertion term by decay heat rmoval Gas Subble Passage through Fuel, PPS followed in long H!gh Flux Flux-Total Flow i 15.2.3.2 i Radial blanket and Control term by decay heat Asserr.b l les ramoval Sel smic Reactivity insertion-SSE PPS followad in long High-Flux Flux-Total Flow 15.2.3.3 term by decay heat Flux- Pressure r moval HTS Pump Electrics Control Assembly withdrawal at PPS followed in Long flux- Pressure Flux-Total Flow 15.2.3.4 Flux-Delayed Flux Startup-Maximum Mechanical Speed term by decay heat removal PPS followed in long High Flux Flux-Totat Flow 13.2.3.5 Control Assemb / Withdrawal at Power term by decay beat rornoval w I 15.3.1 Anticipated Events w HTS Pump electrics Flux-Total Flow b 15.3.1.1 Loss of Of f-Site Electric Power PPS followed in long term by decay heat removal Spurious Primary Pump Trip PPS f of Ic=ed In 1ong HTS Pump E1ectrIcs F1cw Ratio 15.3.1.2 Speed Ratio term by decay heat removal Spurious intermediate Pump Trip PPS followed in long Speed Ratio Flow Patto 15.3.1.3 term by decay heat removal l PPS f ollowed in long Steam-Feedwater Ev ap. Out l et Tor,p. 2> 15.3.1.4 Inadvertent Closure of One Evaporator or Superheater Module term by decay beat O g removal
. s isolation Valve cL Long term by decay None Requir ed None Roquired 00
- 15.3.1.5 Turbine Trip heat renov91 (2)
+-a to i
O O O
f) LRM Quality Assurance management review meetings, held periodically to assess V the implementation of the LRM quality assurance progre, include the CRBRP Project Manager, CRBRP LRM Management, and the LRM Quality Assurance Management. Accomplishments, problems, and corrective actions to resolve the problems, including audit results, are discussed and documented. ARD quality assurance programs, including the LRM quality assurance progrm , are audited on an annual basis by the Westinghouse Nuclear Energy Systems Quality Assurance Canmittee. In addition, the Westinghouse Corporate Headquarters Quality Assurance group perlodically audits the ARD quality assurance programs to assess performance and compliance. No ARD Product l Assurance personnel, including the ARD Product Assurance Manager, are members of the audit teams. Through these activities, independent management assessments are made to determine the adequacy of the scope, impimentation, and ef fectiveness of the LRM quality assurance program. (O b(3 17D-10a Anend. 63 Dec. 1981
. . _ . _ _ _ _ _ _ _ . . _ _ . . . - . _ . _ . - _ . . - _ . _ . - . - . _ _ _ _ _ _ . _ _ _ - _ . . _ _ . _ - . _ , . . , . . . . _ . . ~ _ . _
3.0 DESIGN CONTROL ()
\~/
The overall plant design guidelines and major plant parameters to be incorporated into the design for the CRBRP were established by the Owner. Through contracts with the Owner, the LRM is assigned the l11 design control responsibilities for portions of the NSSS. As such, the LRM is responsible for establishing and specifying the design criteria for each system of the NSSS within his scope of work. The LRM quality assurance program has estaoiished measures to assure effective control of design activities. The execution responsi-bilities for the design, procurement, and manufacture, as applied to each tier of supply will be assigned by applying the appropriate program elements selected from those shown in Figures 17D-4 through 17D-7 and are described throughout this section. The measures include such activities as specifying quality requirements, selection of design verification methods, design change control, and implementation of design procedures. The CRBRP. Project Manager is responsible for identifying the basic technical requirements, and changes thereto, to the RMs, the Architect Engineer (AE), and the LRM aurchasing, Safety and Licensing, and Quality Assurance organizations for the NSSS portion of the CRBRP, These requirements are documented, approved, and issued by the CRBRP Project Manaaer. The LRM performs no primary design; however, the LRM is responsible for preparation and control of the technical requirements
- identified in the Overall Plant Design Description (0PDD-10) which
('v'l forms the basis for primary design. Based upon the technical require-ments, the three RMs and the AE perform the design activity necessary to meet the requirements of OPDD-10 for their assigned responsibilities. The LRM procedures provide for review, approval, release, and distri-bution of principal design data prepared by the RMs and interface control between the responsible design organizations. Design documents used to define and control the design include: e Overall Plant Design Description The Overall Plant Design Description (0PDD-10), prepared and maintained by LRM and approved by Owner, describes the overall CRBRP and its functions. This docunent presents the overall design requirements and includes a description of the major design features of the CRBRP. e System Design Descriptions The principal means to establish, describe, and control the individual system designs from release through operation of the system is done through the use of " System Design Descrip-tions" (SDD). SDDs are standardized and comprehensive documents that define each system requirements. 11 V 170-11 Amend. 11 Jan. 1976
o Eculement Soecifications Equipment Specifications (E-specs) establish the requirements and conditions for the procurement of structures, systems, and components based on SDD requirements. The E-specs are comprehensive documents which define the design, manufacturing, quality assurance, testing, handling, and shipping requirements. An equipment spectfIcation contains all of the requirements of a Design Specification. o Engineering Drawings Engineering drawings are developed to meet the requirements of the SDD and the E-spec, to further identify engineering parameters, and to establish specific design features. The design drawings, with their supporting analyses, are the product of the formal design process. When the design is approved and the component is released for procurement and manufacture, the product and working drawings are prepared to provide details for manufacture, assembly, and inspection. o Procurement Documents in the few cases where equipment specifications or engineering drawings are not used (such as off-the-shelf or catalog items), the specific quality requirements, tests, and acceptance standards are identified in the purchase order. Requirements for review of purchase orders for applicatfor suitability are identified in Section 4.0 of this Appendix. o The Ooerational and Start-Un Test Documents The execution responsibility for the construction and pre-operational test program is retained by the owner. The LRM in conjunction with the RMs, estabilsh within design documents such as construction Test Requirements and Pre-Operational Test Specifications the construction and precperational test requirement. The design documents establish the prerequisites to be satisfied. The test Instrumentation accuracy, the Environmental and operating condition, Equipment calibration standard, Personnel qualification requirements, and test results documentation and verification. The level of authority for review and approval is established in Project requirements documentation for all principal design documents for structures, systems, and components. Levels of approval are based on the importance of the structure, system, or component to overall plant safety and operation. Changes to design documents are approved by a Configuration Control Board which is representative of the same organizations which approved the original document or as otherwise designated by the applicant. Some changes require l higher approval authority than the original document, as stated in procedures, based on characteristics such as cost, degradation of quality requirements, performance, codes and standards requirements, and changes to referenced standards. 17D-12 O Amend. 63 Dec. 1981
(3 The LRM perfor,as its design control and interf ace coordination responsibility (#) using an organizational arrangement of cognizant engineers within separate program groups assigned for the RMs and the AE. The cognizant engineers receive support from functional groups, such as Safety and Licensing, Quality Assurance, Program Control, Construction Liaison, Procurement, and Systems integration. The cognizant engineer is the focal point for the receipt, review, approval or comment, and release of information concerning his area of cognizance. Each cognizant engineer reports to either a first lino manager or directly to a Program Manager responsible for either an RM activity or interfcce Control, Program Managers and functional group managers report to the CRBRP Project Manager. ARD LRM cognizant engineers perform their responsibilities and function only within the LRM scope of work. The LRN design control responsibi Ity !ncludes design document review and approval, design review, and design change review and approval. The LRM also provides coordination to insure adequate RM input for quality assurance program documentation, OPDD-10, Saf ety Analysis Reports, Document Control and Design Interface Control. LRM document review and approval are performed in a ccntrolled and orderly manner in accordance with established procedures. Upon receipt of e design document, or a change thereto, the cognizant engineer performs a review, with other technical support as requirad, to verify that the originating organization has given adequate consideration to applicable requirements for [ ,) regulatory criteria, codes and standards, quality assurance requirements, V suitability of material and parts (including "off-the-shelf" items), reactor physics, seismic, stress, thermal, hydraulic, radiation, und accident analysis; access for in-service Inspection, maintenance, and repair; design adequacy, inspectab!!Ity, and testability, including Identification of acceptance criteria. The cognizant engineer submits the document for review ana approval to his manager, the interfacing Program Managers, the LRM Quality Assurance Manager, the LRM Safety and Licensing Manager, and the Cognizant Program Manager. Each System Design Description (SDD) includes the identification of all physical (geometric), functional, and parametric interface requirements Irnposed by one system upon other systems. Interface Control Documents (ICD) are used for convenience of pictorial or tabular presentation of interface data. Unique document control numbers are used to distinguish an 100 from similar appearing drawings and lists. When an ICD is used to present interface data, the ICD is referenced within each apptIcable SDD. All NSSS ICDS, before initial release for project use, are reviewed and approved by the LRM. Interface data prepared by the AE is reviewed and concurred in by each affected RM and by the LRM prior to approval and release by the AE. Interface data prepared by the RMs is reviewed and concurred in by the AE prior to review and approval by the LRM and subsequent release by the originating RM. The LRM has the continuing responsibility to assure that system to system interfaces are established and maintained current. (
% /
17D-13 Amend. 63 Dec. 1981
Dissemination of working level data is controlled by the use of " Controlled l Information Data Transmittals" (CinDT). This form is normally originated by eitner an RM or the AE prior to formal release of principal design data. A l CinDT may be used after the formal release of principal design data providing an Engineering Change Proposal (ECP) is initiated and processed as described below and detailed in procedures. Overall program controls of CinDTs is maintained by procedures which establish the conditions whereby LRM approval must be obtained. A CinDT received by the LRM is reviewed by the appropriate cognizant engineer. The cognizant engineer assures that the CinDT neither changes released principal design data nor is of a nature to be considered final des!gn data. The results of this review receive approval of the cognizant Program Manager. The LRM may, in limited situations, elect to j originate a CinDT in which case, the CinDT is prepared by the responsible-cognizant engineer, and approved by the cognizant Program Manager. For design verification, the LRM retains the option of performing design reviews. For design reviews which the LRM perform:, procedures are established which assure that the review team has multiple disciplined technical expertise in the subject of the review, objectivity, and is not directly responsible for the design. Results of a design review are l documented to identify all aspects deemed acceptable, unacceptable, or needing additional design effort or verification. Follow-up and corrective action is the responsibility of Design Control. For control of design changes, the LRM has established procedures. The review eno approval of proposed design changes are usually made by an ECP. The ECP suomittal for approval can be Initiated by either tne RMs or within the LRM. The ECP is approved in accordance with procedures through a Configuration Control Board. The LRM-initiated approved ECP is implemented in accordance wiTn procedures. Controls for the distribution, collection, storage, and maintenance of the princip>.0 design documents, and changes thereto, are described in Section 6.0,
" Document Control" of this Append!x.
The control of design changes described in this section also applies when the LRM delegates execution responsibility for design to suppliers. The LRM requires all supplier changes to LRM-approved designs to be processed through the LRM change control system regardless of who performs the design. O 17D-14 Amend. 53 Dec. 1981
)
/N 4.0 PROCUREMENT DOCLNENT CONTROL s-Procurement is perf ormed by the LRM in accordance with established procedures which delineate the sequence of action to be accomplished in the preparation, review, approval, and control of procurement documents. Procurement documents are originated, reviewed, and issued as def ined herein and f urther detailed in Section 6.0 of this Appendix. The procedures require that changes or revisions to contracts be reviewed and approved by the same organizations which reviewed and approved the original contracts, and are controlled to the same extent as the original contract documents. The LRM procurement documents are retained, controlled and maintained in accordance with procedures.
Supplier conformance to the applicable requirements of 10CFR50 Appendix B is achieved by the supplier meeting the quality assurance requirements of government and industry codes and standards either in part or whole or by company specificaticns as applied in the Purchase Order. Conf innation that the applicable 10CFR50 Appendix B requirements are described in the supplier quality assurance program is done by the ARD-LRM review and approval of these documents. Verification of supplier conformance to the LRM approved supplier quality assurance program is accomplished by surveillance and audits. Preprocurement planning is accomplished in accordance with procedures. The RMs preprocurement planning documentation, above establisher dollar limits, is approved by the LRM prior to obtaining the Owner's approval for initiating procurement action. The LRM-initiated preprocurement planning documentation, above established dollar limits, is also submitted to the Owner for approval [s} U subsequent to approval by the LRM cognizant disciplines and the ARD Product Assurance Manager. RMs _subcentracts exceeding estabilshed dollar limits must be submitted to the LRM f or approval for budgeting control purposes, and f or verification that the admFnistrative and technical requirements and controls are properly defined in order to assure adequate quality. The LRM concurs in the subcontracts submitted and obtains Owner approval prior to authorizing placement. Procurement activities f or hardware, components, material, or services f rom suppliers are initiated by the LRM cognizant engineer (the requisitioner) by l preparation of a Purchase Requisition which requires the inclusion, either directly or by reference, of the foilowing: o Descriptive title of the Iton or service desired. o Complete list of applicable drawings (including revision level). o Canplete list of technical specifications, including applicable changes.
/'N i i G
17D-15 Amend. 63 Dec. 1981
o Applicable codes, standards, and regulatory requirements. o Special process requirements. o Acceptance test and inspection requirements. o Material and component identification requirements. o Supplier document submittal with review and approval requirements. Quality assurance provisions, as required, are appended to the requisition to include such items as: o Submittal requirements pertinent to LRM review and acceptance of quality assurance documentatlon. o Reporting and disposition of deviations from requirements. o Cleaning and handling requirements. o inspection and test plan submittals. o inspection and test procedure submittals. o Process procedure submittals. o Quality record submittal and retention requirements (i.e., procedure qualification, personnei qualifications, test reports) along wIth data required to be supplied with the shipment of hardware. The cognizant engineer obtains approval of his manager and forwards the requisition, along with supporting and referenced material, to technical support organizations, as necessary, and LRM quality assurance for review and approval in accordance with procedures. LRM Quc'Ity Assurance provides the necessary review of the procurement package to assure that appropriate technical and quality assurance requirements are adequately and clearly stated prior to signing and dating the appropriate block of the requisition. Detailed procedures are utilized to assure that quality requirements are correctly stated, inspectable, and controllable, and that adequate acceptance or rejection criteria exists. The requisitloa package is then forwarded to Procurement for preparation of the proposal or bid requests. Procurement is required by procedures to include all provisions of the requisition in the contract or purchase order. Procurement documents that are made part of the purchase order provide for access to supplier facilities and records for purpose of audits and surveillance by LRM or LRM designated representatives, and describe methods by which document transmittal is to be made from the suppller to the LRM. The approved requisition is maintained by Procurement as evidence of approval to place an order. O 17D-16 Amend. 63 Dec. 1981
u If f ormal evaluation and/or negotiations are required as a result of bids or 9 proposals, these activities involve Procurement, Quality Assurance, and Engineering as appropriate to the scope of the evaluation. Authorization f or placement of the purchase order is by means of the original requisition unless: o Cither supplier response to the request f or quotation or negotiation with the supplier result in changes to the technical requirements specif ied in the purchass requisition. o The negotiated costs exceed the budgeted authorization on the purchase requisition. o The original requisition requested proposals only. If any of the above conditions exist, the requisitioner prepares a Purchase Requisition Change Notice (PRCN) describing the proposed changes and documents the review and approval actions in the same manner as the original requisition. Either on the basis of the original requisition or upon receipt of an approved PRCN changing a request f or proposal to a request for a purchase order, Procurement prepares the pur "ase order and obtains the Owner approval when the dollar value exceeds a sp;cified limit prior to entering into a contract with the supplier. Copies of released purchase orders are distributed to lhl designated disciplines, including LRM Quality Assurance who reviews the order to assure that all requirements have been included as specified in the requisition. Quality Assurance documents the review of the purchase orders by signing the cover sheet of the Quality Assurance copy of the purchase orders. These copies are maintained in the Quality Assurance files for reference and traceability purposes. Af ter order placement, purchase order revisions are initiated by the cognizani engineers' preparation of a PRCN. These documents are reviewed, approved, and processed in the same manner as described earlier for the original requisition. Procurement issues a Purchase Order Change Notice (POCN) to implement the change. The POCN is numerically identif ied in a sequential manner to the original purchase order and controlled by Procurement. Each POCN is an entity and normal ly does not supercede prior approved P0CNs, unless so stated therein. Copies of the POCN are distributed to designated disciplines, including Quality Assurance, which review the POCN to assure that all requirements have been included as specified in the PRCN. The supplier acknow ledges receipt of the P0CN. All approved purchase requisitions and changes are maintained by Procurement as evidence of appropriate approval. Spare and replacement parts are ordered using the same controls as described in this section f or the original parts and components. O 17D-17 Amend. 63 Dec. 1981
LRM Quality Assurance overviews RM and LRM supplier procure-ment activities by means of periodic surveillance and audits. In addition, the LRM has the right to access to RM subcontractors' facili-ties and will participate, on a selected basis, in RM audits of their suppliers. Supplier records required to be submitted to the LRM are collected and maintained in accordance with records requirements described in Section 17.0 of this Appendix. 11 O l l l r 17D-17a Amend. 17 O
, Apr. 1976
,- y d. Design drawings,
- e. Process procedures.
- f. Supplier recommended disposition of Supplier Nonconformance Reports, i.e., " accept as is," " repair," or " modify," indicating that purchase order requirements have not been met.
Review and approval of submitted plans and procedures by the cognizant engineer and LRM Quality Assurance are mandatory, with additional review and approval by materials, manuf acturing engineering and other disciplines as appropriate. A significant part of LRM surveillance activity is related to the suppiler quality verification plan or inspection and test plan. During review of the supplier quality verification plan or inspection and test plan, procedures i provide f or the quality engineer to identify those steps in the process and inspection where LRM documented release must be obtained prior to f urther processing. The documented release is by a release f orm signed by the Quality Assurance representative. Quality Assurance personnel perf orm the surveillance activities identified in the LRM approved supplier quality verification plan or inspection and test plan in accordance with documented j procedures . Surveillance is perf ormed on supplier receipt inspection to assure conformance with supplier procedures identified in the LRM-approved supplier quality assurance program. The LRM perf orms audits of suppliers, as discussed in Section 18.0 of this Appendix, independent verifications, such as raciographic film review and material overchecks, to assure that the supplier ()T (_ certificates of conformance are valid. The frequency and scope of surveillance depends upon the complexity of the parts and components being manuf actured, the manuf acturing stage, and the supplier perf ormance. All saf ety-related components whose quality characteristics cannot be f ully verif ied at receiving inspection are covered by ARD-LRM surveil lance. The degree of field verification perf ormed by ARD-LRM quality assurance personnel is dependent on the complexity of the component and the suppIIer's perf ormance. The quality release f or shipment of parts and components f rom LRM suppliers and RMs acting as a manuf acturer is issued by LRM Quality Assurance personnel. Prior to the issuance of the quality release, LRM Quality Assurance personnel perf orm the f ol lowing f unctions: o Review of the certif icate of conf ormance, test data, and records to verify that purchase order requirements are met. o Assure that requirements f or handling and shipment have been approved and implemented. o Witness required inspections. o Review packaging and shipping arrangements as required. n
! ) -
s- / 17D-23 Amend. 63 Dec. 1981
b e Review data package to assure that all docundntation iequired by the purchase order, including supplier nonconforma~r reports, is included in the package. e Review the data package documentation to confirm that the material, parts and components meet the purchase order 17 requirements. Documented evidence of the quality release for shipment is by 45l the LRM Quality Assurance representative's signature on a release form. The parts and components are shipped to the site to the attention of the Owner or his representative who performs the required receiving inspection in accordance with the requirements furnished with the 17l material and equipment. ARD-LRM perfonns no receiving inspection. LRM suppliers are required, by LRM review and approval of supplier quality assurance program documentation, to specify the control of purchased material, equipment, and services in purchase orders placed with sub-tier suppliers as appropriate for the subcontracted material, equipment, and services, jj The same controls of purchase material, equipment, and services described in this section are applicable when purchase orders are placed with other Westinghouse divisions. Spare parts and replacement parts are ordered using the same controls for the orignal parts and components as described in this section. 170-23a Artend. 45 July 1978
l Requests f or Cor ective Action (RCAs) are generated by LRM Quality Assurance personnel to document and notify either responsible LRM managment or LRM-supplier management of def iciencies and noncompliances found at the RM and at supplier facilities. The responsible management is required to identify either the corrective action taken, or to be taken within a specified time, and return the request to LRM Quality Assurance. Corrective actions are recorded, eval uated, fol lowed, compil ed, and reported in accordance with procedures. A summary of signif icant def iciencies and noncompliances is identified monthly by the CREP Project Manager in the LRM Quality Status Report to the ARD General Manager along with a corrective action status summary, audit results, and adverse quality trend data as appropriate. Execution responsib!Ilties f or identification and impimentation of corrective action are also delegated to suppliers by purchase order requirements. O O 17D-33 Amead. 63 Dec. 9 81
17.0 QUALITY ASSURAllCE RECORDS Procedures define those records which are necessary to document the quality of f1SSS structures, systems, and components. These records are listed in the applicable LRM procedures along with the LRM organi-zation responsible for their collection, maintenance, storage, and j retrieval. When documents are declared a record they are located and/or secured in such a manner as to prevent destruction of the records by fire, flooding, theft, and deterioration by environmental conditions such as temperature or humidity. The records include, but are not limited to, docu- )' ments and changes thereto, such as OPDD-10, specifications, drawings, stress reports, procurement documents, inspection and test results, quality releases, personnel qualifications, supplier quality assurance documen-tation including inspection, test, and calibration procedures, results of internal and external audits, Owner approvals, nonconformance reports and corrective action reports. During the design, procurement, and manufacture of structures, systems and components, records are maintained and stored at the LRM in an identifiable and retrievable manner and under controlled conditiens. Records identified by the 0wner to be transferred to the plant site, or other repository, will be delivered as directed. Procurenent documents specify records which are to be supplied to the LRM, delivered with products, or maintained in the LRM suppliers' files. Records requirements are imposed on LRM suppliers by purchase order in accordance with applicable codes, standards, and specifications. These requirements include provisions that inspection and test records contain a description of the test performed, verification of work com-pletion for nanufacturing, inspection and test, inspection and test results, identification and disposition of nonconformances, and identifi-cation 01 acceptability of test results. II Duplicate records identified by the Owner to be transferred to the plant site, or other repository, will be delivered or maintained as dir-17 ected. 17D- 34 Amend. 17 Apr.1976
18.0 AUDITS Procedures are established and implemented for conducting com-prehensive, planned, and periodic internal LRM audits and external audits 40 . of LRM suppliers and RMs to verify compliance with all aspects of the quality assurance program requirements, to determine the effectiver.ess of the program, and to assure compliance with the contractual requice-45l ments. Audit scheduling, notification, team selection, conduct of the dudit, reporting, follow-up of audit responses, and Closeout are the responsibility of Quality Assurance. Audit teams are selected by Quality Assurance management based on the members' knowledge, expertise, and experience in the area to be audited. Team leaders are responsible for preparing detailed checklists against which the audit is performed. 40l The audit team members, including the team leader have no direct respon-sibility for the area being c'riited. Types of audits performed are related to activity, product, non-destructive examinations, and records. Audits are conducted to evaluate the implementation of procedures and practices in the areas of program activities, work practices, testing, records, and other portions of the quality assurance program as appropriate to the status of the work. l Activity audits include interface control . Inter nal audits of I LRM activities are conducted to confim compliance with established pro- l cedures for interface control. Internal audits assess the effectiveness of the control of design interfaces between the RMs and the AE. External audits of RMs and LRM suppliers assure that they are conforming to their O procedures in controlling design interfaces. Assessment of the implementation and effectiveness of the indoc-trination and training programs is also an integral part of activity audits, either conducted at the LRM as internal audits or at the LRM supplier and RM locations as part of external audits. In both cases, ' the audits verify that personnel who either perform or verify work are properly trained and qualified to perform their assigned tasks in com-pliance with established procedures to meet the quality assurance program requirements imposed by contract. The salient elements of the internal and external audit programs are:
- 1. Audits are scheduled on a regular basis and are initiated sufficiently in advance to assure effective quality assurance program implementation during design, procurement, manufacturing, inspection, and test.
- 2. Planning of audits results in a documented audit plan which identifies the specific activities to be audited, the re-quirements upon which the audit is based, the team members, and team leader. 11 b
V 17D-35 Amend. 45 July 1978
- 3. Notification of the responsible managment of the work activity to be audited identifying the audit plan, tem members, and audit date.
This notification occurs at least one month prior to the audit.
- 4. Preparation of the documented audit checklists by the audit tean leader and the crientation of team members by the audit tem leader prior to the audit.
- 5. Conduct of audits in accordance with the prepared checklists.
f
- 6. A discussion (critique) of the audit findings at the conclusion of the audit, with the management personnel responsible for the audited activity.
- 7. Documentation of audit results, including critique, to the managment responsible for the work audited.
- 8. Response f rom the managment responsible for the work audited Indicating corrective action taken, or to be taken, to preclude recurrence of deficiencies.
- 9. Evaluation of adequacy of the response and f oi low-up to assess Irapimentation of corrective action.
- 10. Reaudit of def Iclent areas, if necessary, and documented closeout of open items.
- 11. Analysis of audit results for adverse quality trends which, if noted, are reported to the ARD General Manager via the Quality Status Report indicating either the corrective action Impimented or proposed to be implemented within a specified time.
Procurment documents have provisions f or access of the LRM end LRK designated . personnel to suppliers' plants for the purpose of conducting audits. The responsibility for the execution of audits is also delegated to LRM suppliers and the RMs by procurement documents. LRM suppliers and the RMs are responsible for auditing their own Internal progrm and those of sub-tier suppliers. These procurment documents also provide for LRM participation in LRM supplier and the RM audits of their sub-tier suppliers. O s-36 Amend. 63 Dec. 1981
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00 tJa tJa da PROGRAM MAN %E MENT ORG ANilATION DOCUM ENT ATION AUDITS AND HEVIEWS CORRECTIVE ACTION ENGINEE RING HOL DS OUALITY ASSURANCE PROGRAM 1 Responubehty and Authority L Pohcies and Procedures 1 Ouahty Audits UNUSUAL OC;11PRENCE REPORTING
- 1. Planning
- 2. Quahty Assurance Program Inden 2. Trainmg and Indoctrination 2 Quehty Records 2. Management Reviews
- 3. Peisonnel Ouahficatiors 3. Quahty Status Hesmets II DESIGN AND DEVELOPMENT PROCURE ME NT MANUF ACTURING. F ABRICATION AND ASSE MOLY Des.gr Planning Procurement Plannmg Planning Design Defmitron and Control Procurement Requirements Inswction and Test Plan
. Design Criteria Procurement Document Reviews Material identification and Control
- 2. Codes. Standards and Evaluation and Selection of Control of Procesws Practices 1. Fatwicate and Aswmbly Processes Procurement Sources 1 Engineering Studies 1 G'""ai Requirements 2. Process Quahtication
- 4. Parts. Materials and Procesws
- 2. Acceptable Source List 3. Nomtestructive E =ammation 5 Design i)escriptions 3 Preaward Evaluation 4. Cleaning
- 6. Specifications, Drawings and 4 Interchange of Source inspection amt Tests N instructions Capabihty information 1. hM Rwmm f
A 1 (dentification a Acceptance Criteria Control of Configuration 2. Procedures
# 1. Contract Chang
- Control 3 Completed item inspection and Test 9 Interf ace Control l 4 Insper* ion Status indication Document F;eview and Controt 2. As Built Verification.
Equipment Cahbration and Standards i Certibcation
- 1. Document Reviews
- 2. Document Control Source Surveillance amt inspection Document Controt
- 3. Engineering Drawing L.6sts E9d'pment Cahbration and Stam1 aids
[ Rece ving Inspecteor,
**' 1 Equipment Evaluation
- 1. Planning and Inspect.on
- 2. Control of Irwpection Measurmg and Test Development 2. Documentation Equipment 3 04"'5'tionmg of Received item.
Fa lure Reporting and Corrective ' " Act on Control of Noi conforming items 4 Discrepenty Equipment Control of Received items Statirical Quahty Control and Analysis Contral of Nonconforming items Corrective Action Handhng. Preservarion. Paciraging. Siorage and Shipping
- 1. Handhng 2 Preservaten, Pacicaging and Storage
- 3. Shippeng Ik am
- 3 ct ae e
yC Figure 170-7 Major Elements of the LRM Supplier Quality Assurance Program
ATTACHMENT 170-1
SUMMARY
OF LRM QUAL ITY ASSURANCE PROCEDURES INDEX NO. PROCE DURE
SUMMARY
- 1. LRM Quality Assurance Establishes the authority and def ines the riuties of tne Charter LRM Quality Assurance Department.
- 2. Quality Assurance Progran Describes the org.anizationai authority and responsibili-Description ties f or work perf ormance and verIf Ication in accordance with procedures identifled in a progr m index to assure the quality of the NSSS structures, systms, and compo-nents within the LRM scope of work.
- 3. Personnel Indoctrination and Establishes ti,e requirement and methods f or training Training and Indoctrination of personnel who either perform or verify quality-related functions in accordanco with the LRM quality assurance progr m .
w y 4. Quality Records Def ines the responsibilities f or acquisition, Identiff-a cation, maintenance, and retrieval of quality records. 4
- 5. Quality Assurance Progres Establishes the Divisional Policy for Quality Assurance Progres to impiment contractual Quality Assuranca Requirements.
- 6. LRM Quality Status Reports Establishes the procedure for the preparation of the and QA Management Review periodic CRBRP-LRM Quality Status Reports and the con 1uct of the periodic LRM Management Reviews.
- 7. Request for Correction Def ines the methods used to request corrective actions Action (RCA) within the LRM, at LRM suppliers, and at the PNs.
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ATTK2tMENT 170-1
SUMMARY
OF LRM QUALITY ASSURANCE PROCEDURES INDEX NO. PROCEDURE
SUMMARY
- 9. Design Review and [= sign Def ines the measures used f or the preparation, conduct, Release and documentation of design reviews with follow-up action i
requirements.
- 10. Unusual Occurrence Establishes a systou for reporting, evaluating, and de-Reporting fining corrective actions relative to unusual occurrences.
I
- 12. Approval of IN and Establishes the methods for approval of the Quality Supp!Ier Quality Assurance Progrm Indices proposed by RMs and the Assurance Progr m LRM suppliers to meet the quality requirments
, g Indices imposed by conteact during design, manufasturing, j u and testing of NS$$ structure, systms, and C components. 4 N 13. Request for Watver Deseribes the method used by the LRM f or disposition of waivers received from FNs and LRM suppliers. i i 4
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ATTACIS1ENT 17D-1
SUMMARY
OF LRM QUAL ITY ASSURANCE PROCLDURES INDEX NO. PROCEDURE
SUMMARY
- 14. Hold Points Provides Instructions and methods to be used in imple-menting a verification hold point program and when per-forming " Hold Point" inspections at RMs and LRM supplier locations.
- 15. Quality Release of Supplier Defines the measure for the LRM Quality /.ssurance to or RM Material Preparatory to issue a quality release to effect shipment by LRM Shipment suppliers which may include the RMs.
- 16. Quality Assurance Provides instructions to LRM Quality Assurance Represen-Surveillance tatives when performing survelliance at LRM suppliers and at RMs.
- 17. Control and Disposition Estabilshes the Instructions and methods used for report-I of Nonconformances Ing, evaluating, and dispositioning nonconformances
$ generated by either LRM suppliers or RMs, including evaluation of corrective actions.
- 18. Certification of Nondes- Establishes the criteria for the quellfication and cert-tructive Testing ification of Nondestructive Testing (NDT) personnel and Personnel provides for instructions for records refer.tlon and recall.
- 19. Quality Assurance Audits Details the Instructions and measures used for scheduling, of Reactor Manutacturers conducting, reporting, follow-up, and closeout of quality and LRM Activities assurance audits of LRM Intarnal activities, LRM suppliers, and RM activities.
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pg .- ATTACHMEf4T 170-I
SUMMARY
OF LRM QUALITY ASSURANCE PROCEDURES INDEX NO. PROCEDURE SU WARY
- 20. Communications Establishes requirements and methods uset for communica-ting with organizations external to the LRM.
- 21. Correspondence Transmittal Estabilshes the system for distribution and control of and Distribution Incoming and outgoing LRM correspondence.
- 22. Configuration Control Prescribes the requirements and the operation of the Configuration Control Board to review and approve design changes to released RM, LRM, and LRM supplier engineering documentation.
[ 23. Documentation Status System Defines the system requirements and methods used to c3 s maintain and control the design documentation, 4 e 24. Controlled Information Establishes the methods used for controlled dissemina-Data Transmittal tion of principal design data prior to the release of (CinDT) the systan design descriptions,
- 25. Preparation and Establishes the preparation, updating, and control of Control of LX-OR LX-OR-Procedures.
Procedures
- 26. Document Hold Defines the requirements and methods used to identify Status System principal design data which is not yet released for Project use.
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ATTACHMNT 1701
SUMMARY
OF LRM QUAllii ASSURANCE Pf<0CEDURES INDEX NO. PROCEDURE
SUMMARY
- 27. Design Document Review Establishes the measures used f or controlling and and Approval processing of technical and design documents for review, approval, and release.
- 20. Overall Plant Design Establishes the methods used for the generation and Description (OPDD-10) maintenance of OPDD-10, the Overall Plant Design Description.
- 29. Divlslonal Policies / Defines the policy, implementation, and responsibill+y I Procedures Program fer divisional, administrative, operating and depart-mental policies and procedures.
e-* 30. Request for Purchase Establishes the requirements and controls exercised y throughout the procurement cycle f or structures, systesns e parts, components, materials, and services. U1 o
- 31. Purchase Requisition Establishes the requirements and controls, exercised Change Notice for modifications to purchase requistflons.
- 32. LRM Procurement Review Defines the methods used by the LRM to review RM, LRM and Approval Actions and and LIN supplier procurement actior.s.
LRM Procurement Actions
- 33. Purchase Order /Contred EstLblishes the system and methods used for organizing, File Organization filing, and retrieval of purchase crder documentation.
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C) v) ATTACHMENT 170-1 SUNY OF LRM QUALITY ASSURANCE PROCEDURES INDEX NO. PROCEDURE
SUMMARY
34 Preprocurement Defines tre pollcy, system, and methods used for Planning preprocurement planning, review, and approval thereof.
- 35. Preparation of PUR Defines the methods and controls used to obtain approval letters and Justification of higher level authority for procurement actions.
- 36. Acceptable Source List Defines systen and measures used for identifying and l maintaining a list of suppliers who have demonstrated their capability to provide acceptable products or services.
- 37. Use of Procurement Establishes the method of controlling procurernent
- Administrative Documentation administrative documents (advisory releases, approval y and Requirements requests).
e
$ 38. Response to NRC Questions Establishes the responsibilities and methods used to (PSAR related) prepare formal responses for the Owner to communicate i
with NRC. I j
- 40. Quality Levels Establishes the quality level assigned to items or item-i related services to assure satisfactory performance and safety.
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All ACliMLNT 170-1
SUMMARY
OF LRM QUAL ITY ASSURANLE PHOCf DURES lNDEX NO. PHOCfDURE
SUMMARY
- 41. Quality Assurance Review Establishes the requiroments for Product Assurance review and Approval of Procurement and approval of pr ocurement documents to assur e that l Documents quality requirements are effectively applied.
- 42. Training and Qualification of Establishes requiroments for training and quellfication Personnel (special processesi of personnel who accept materials or who perform certain special process operat ions.
- 43. Verification Hold Point Establishes requiroments to ensure that achievement Program of Contractural Quality requirements is verlfled, including ASME Code Requirements f or ASME code items.
- 44. ARO Purchasing Procedure Establishes the need and authority for a purchasing y Manual procedure manual to define procurement policles, practices, o and procedures.
e $ 45. Interface Control Document Establishes the procedure for generation and review of LRM Interface Control Documents (ICDS) and Review and Approval of ICDS prepared by other Project Participants.
- 46. Qualifications of Audit Establishes the LRM requirements and methods for qualifi-Per sonnel cation of personnel to perform quality assurance audits.
- 47. Determining Responsible Establishes the requirements for determining responsible Prospective Suppliers prospective suppliers of materials and services and provides guidelines f or c.onducting surveys of potential suppliers.
- 48. Preparation and Control Establishes requirements for preparation and Control of of WARD Documents WARD documents which provide technical information, og including de' lgn, construction test, and Pre-operation test requirements.
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sg (/ ATTACHMENT 17D-2 INDEX OF LRM QUALITY ASSURANCE PROCEDURES TO 10CFR50, APPENDlX B CR11ERI A 10CtR50 Appendix 8 Criteria . Criteria Title LRM Imolcmen11aglrocedure_ladex No. (from Attachment _11D-ll i Organization 1 2 5 12 11 Quality Assurance Program 1 2 3 4 5 6 12 16 19 29 41 42 43 46 Ill Design Control 9 12 13 17 22 23 24 26 27 28 43 45 48 IV Procurement Document Control 12 27 30 31 32 33 34 35 36 37 41 44 V Instructions, Procedures, and Drawings 1 2 12 29 41 VI Document Control 12 13 17 20 21 22 23 24 25 26 27 29 30 31 32 38 41 45
$ Vil Control of Purchased Material, Equipment and Services 12 13 14 15 16 17 18 19 22 27 30 31 32 34 35 36 37 41 44 47 Vill Identification and Control of Materials, Parts and Ccanponents 12 14 15 30 31 32 41 43 44 IX Control of Special Process 12 18 41 42 X Inspection 12 14 15 16 19 43 XI Test Control 9 12 14 15 16 22 27 30 31 32 41 43 XII Control of Measuring and Test Equipment 12 27 30 31 32 41 Xtli Handling, Storage and shipping 12 30 31 32 41 43 XIV Inspection, Test and Operating
@g Status 12 14 15 16 43 m (D [ XV Nonconforming Materials, Parts or Components 12 14 15 16 17 18 41 b XVI Corrective, Action 6 7 10 12 14 15 16 17 19 41 XVil Quality Assurance Records 4 12 14 15 16 27 41 XVill Audits 6 7 19 27 46
CONTENTS (Cont'd) PAGE N0. 4.5 CHANGE CONTROL 17E-15 4.6 P.EPLACEMENT PARTS 17E-15 5.0 INSTRUCTIONS, PROCEDURES AND DRAWINGS 17E-16 8 6.0 DOCUMENT CONTROL 17E-17 6.1 DOCUMENT CONTROL SYSTEM 17E-17 6.2 DOCUMENT REVIEW AND APPROVAL 17E-17 6.3 DOCUMENT CHANGE PROCEDURE 17E-18 6.4 DOCUMENT DISTRIBUTION 17E-18 6.5 OBSOLETE DOCUMENTS 17E-18 6.6 PROCUREMENT DOCUMENTS 17E-18 7.0 CONTROL OF PURCHASED MATERIAL, EQUIPMENT AND SERVICES 17E-19 8 7.1 PROCUREMENT CONTROL 17E-19 7.2 EVALUATION OF SUPPLIERS 17E-19 7.3 SURVEILLANCE OF SUPPLIERS 17E-19 7.4 SUPPLIER OVALITY ASSURANCE RECORDS 17E-20 8.0 IDENTIFICATION AND CONTROL 0F MATERIALS, PARTS AND COMPONENTS 17E-21 9.0 CONTROL OF SPECIAL PROCESSES 17E-22 10.0 INSPECTION 17E-23 8 11.1 TEST PROGRAM REQUIREMENTS 17E-25 11.2 SUPPLIER TEST PROGRAMS 17E-25 11.3 PREOPERATIONAt AND OPERATIONAL TESTING 17E-26 11.4 TEST RESULTS 17E-26 12.0 CONTROL-OF MEASURING AND TEST EQUIPMENT 17E-27 13.0 HANDLING, STORAGE AND SHIPPING 17E-28 14.0 INSPECTION, TEST AND OPERATING STATUS 17E-29 Amend. 40 17E-iii July 1977
CONTENTS (cont'd) PAGE NO. 15.0 DEVIATING MATERIALS. PARTS AND COMPONENTS 17E-30 15.1 CONTROL OF DEVIATIONS 17E-30 15.2 REVIEW AND APPROVAL OF DEVIATION REPORTS 17E-30 15.3 SUPPLIER DEVI ATION C0fRROL SYSTEM 17E-30 15.4 REVIEW OF SUPPLIER DEVIATION CONTROL 17E-31 16.0 CORRECTIVE ACTION 17E-32 16.1 CORRECTIVE ACTION PROGRAM 17E-32 16.2 ISSUANCE OF CORRECTIVE ACTION REOUESTS 17E-32 16.3 DISTRIBUTION OF CORRECTIVE ACTION REOUESTS 17E-33 17.0 OUALITY ASSURANCE RECORDS 17E-34 17.1 OUALITY ASSURANCE RECORDS PROGRAM 17E-34 17.2 SUPPLIER OUAllTY ASSURANCE RECORDS 17E-35 17.3 MAINTENANCE OF OUALITY ASSURANCE RECORDS 17E-35 17.4 VERIFICATION OF OUALITY ASSURANCE RECORDS 17E-35 18.0 AUDITS 17E-36 18.1 AUDIT PROGRAM 17E-36 18.2 INTERNAL AUDITS 17E-37 18.3 EXTERNAL AUDITS 17E-37 18.4 INTERFACE AUDITING 17E-37 18.5 AUDIT FINDINGS REVIEW 17E-38 FIGURES 17E-1 AE Quality Assurance Organization Chart 17E-39 17E-2 Major Elements of the AE Program 17E-40 i 17E-3 Matrix of 10CFR50 Appendix B and The Quality Assurance Program PIen 17 E-41 ATTACHMENTS 1 Quality Assurance Manual Procedure Descriptions 17El-1 17E-IV Amend. 63 Dec. 1981
Vendor Surveillance Group - This group schedules, plans and implements vendor pre-award and in-process fabrication surveys h; and may participate in audits. The services of qualified engineers U' from AE engineering are utilized whenever the scheduled vendor audits or survey requires such capability. By virtue of-the charter of the Quality Assurance Manager, the group has authority to issue an order through contractual channels to stop unsatis-factory or unapproved practices for so long as such stoppage may be necessary to assure compliance with specification requirements. 1.3 RESPONSIBILITY AND AUTHORITY The responsibility for execution of the AE Quality Assurance Program 81has been assigned to the Architect-Engineer by Contract. The Vice-President, Breeder Reactor Division, has been assigned responsibility for the AE Quality 40 Assurance Prngram within the Architect- Engineer Organization. The Quality Assurance Manager reports directly to the Vice-President, 8 Breeder Reactor Division, for overall quality assurance matters and administra-40 tive control and interfaces with the Project Manager for integration of qual-ity program requirements and coordination of quality assurance activities with overall project efforts. The Quality Assurance Manager is responsible for assuring that the Quality Assurance Program is established and implemented. He is 8 45 responsible for the review and concurrence or approval of engineering and pro-40, curement documents to assure that quality requirements are properly applied. The Quality Assurance Manager has organizational freedom and authority to evaluate quality prcblems and initiate or recommend and verify implementation p) ( 8 of solutions. Through him, this authority is extended to individuals under his supervision that perfonn quality assurance functions. He has the responsibility 40 of reporting to the Vice-President, Breeder Reactor Division, on the adequacy and effectiveness of implementation of the AE Quality Assurance Program. He has the responsibility for planning, definition and coordination of Quality Assurance Program activity, and by surveillance, audit and review for assuring that adequate procedures to control quality related work are de-veloped and implemented. He has the authority to require the Project Manager to stop work in any area of the project when he detects nonconforming con-ditions which jeopardize quality objectives. He communicates'directly with the Client's Quality Assurance Manager for the interchange of project quality assurance criteria and information. 8 The Quality Assurance Manager is responsible for verifying quality achievement of suppliers and subcontractors in their work performance. The AE retains responsibility for assuring that the program execution delegated to suppliers and subcontractors is adequate to support project quality objectives. The AE has established procedures for implementing the plans and actions de-scribed herein to assure that the technical design bases, codes, standards, regulations anddocumentation requirements are appropriately invoked for each procurement action. The Quality Assurance Manager is responsible for assuring that suppliers:are performing work in accordance with approved supplier quality assurance programs during component design, procurement and manu-40 facture. Verification is performed through surveillance and audits of supplier b G Amend. 45 July 1978 17E-3
operations which relate " Jesign, procurment, fabrication, testing and shipping. The activities also include assuring that corrective actions, when necessary, have been ef fectively Impimented. He is also authorized to direct the Procurment Manager to stop unsayisf actcry work by subcontractors and suppliers and to control further processing, delivery cr Installation of deviating material. He also has the responsibility to assure that an adequate Indoctrination and trainirg progrm for AE personnel performing activities af fecting quality is provided. The Indoctrination and training progrm will assure that:
- 1. Personnel perf ormirg activities af fecting quality are appropriately trained in the principles and techniques of the activity being performed;
- 2. Personnel perf orming activ!tles af fecting quality are instructed as to purpose, scope and impimentation of governing manuals, policles and procedures ;
- 3. Appropriate training procedures are established.
The Quality Assurance Manager has complete administrative and technical control of personnel in the QA Section in ceder to assure suf fIclent independence and f reedom in the perf ormance of quality verif ication activities. His "hlre/ fire / promote" actions are reviewed and approved by the Vice President, Breeder Reactor Division. Manpower schedules and budgets, with Project limitations, are prepared by the QA Manager, then reviewed and approved by the Vice President, Breecer Reactcr Division. 1.4 OUALIFICATION REOUIREMENTS FOR OUALITY ASSURANCE MANAGEMENT POSITIONS 1.4.1 OUALITY ASSURANCE MANAGER The Individual assigned responsibility for managment of the quality assurance progrm will have the following qualifications: Education - He shalI be a graduate of a four year accredited engineering cr science college or university. General - He shalI have a minimum of 10 years experience in quality assurance or engineering, construction, or operation activities associated with nuclear facilities or equivalent heavy industry. Soecialtv - He shall possess a broad knowledge and understanding of l Industry and government codes, standards and regulations defining quality assurance requirments and practices. He shal I have a broad knowledge and understanding of quality assurance methods and their appl! cation. He shal l have experience in planning, def ining and perf orming quality assurance practices and the application of procedures. 17 E-4 O Anend. 63 Dec. 1981
Managerial - He shall be experienced in the supervision of personnel and [V j the planning and management of other resources normally needed to conduct an extensive quality assurance program. 1.4.2 ENGINFFRING OUALITY ASSURANCE GROUP - SUPERVISOR The Individual responsible for supervising the quality assurance engineering f unction will have the following qualifications: Education - He shall be a graduate of a four year accredited engineering college or university. General - He shalI have a minimum of 7 years experience in qua!Ity assurance or engineering, construction, or operation activities associated with nuclear facilities, power generation, or heavy industry. Soecialty - He shall possess knowledge and understanding of industry and government codes, standards and regulations which define quality assurance requirements and practices. He shall be familiar with methods of application of programmatic and special quality assurance requirements in design and procurement documents. He shall be experienced in evaluating program plans, procedures and practices, and subsequently verifying conformance. Suoervisory - He shall be experienced in the supervision of technical and administrative personnel engaged in quality assurance or engineering activities. %.) 1.4.3 AUDIT GROUP SUPERVISOR l The individual responsible for supervising the quality assurance auditing function wiII have the folIowing qualifications: Education - He shall be a graduate of a four year accredited college or university, or be a high school graduate and have 10 years experience in quality assurance / control in Ileu of a degree. General - He shall have a minimum of 7 years experience in quality assurance or engineering, construction, or operation activities associated with nuclear facilities, power generation, or heavy industry. Soecialty - He shall possess knowledge and understanding of industry and government codes, standards and regulations which define quality assurance' requirements and practices. He shall be experienced commensurate with the scope, complexity or special nature of the activities to be audited. Suoervisory - He shall be experienced in the supervision of technical and administrative personnel engaged in quality assurance auditing activities. 1.4.4 VENDOR SURVEILLANCE GROUP - SUPERVISOR The individual responsible for supervising the vendor surveillance function will have the following qualifications: [v} 17E-5 Amend. 63 Dec. 1981
Education - He shall be a graduate of a four year accredited coIIege or university, or be a high school graduate and have 10 years experience in quality assurance / control in lieu of a degree. General - He shall have a minimum of 7 years experience in quality assurance or inspection and testing, construction, or operation activities associated with nuclear facilities, power generation, or heavy industry. Soecialty - He shall possess knowledge and understanding of industry and government codes, standards and regulations which define quality assurance requirements. He shall be experienced in establishing and implementing programs, plans and practices for product inspection, process surveillance, and auditing of supplier QA Programs. He shall have a broad knowledge and understanding of NDE, special processes and equipment test methods, including evaluation of vendor qualifications and capabilities. Sucervisorv - He shall be experienced in the supervision of technical personnel engaged in inspection and test, vendor surveillance or auditing activities.
- 2. OUALITY ASSURANCE PROGRAM 2.1 POLICY Burns and Roe is committed 1o achieving standards of quality in all its services to clients which will assure public safety and optimize plant reliability consistent with costs and schedules. The company will take appropriate measures to perform its designated work in accordance with all applicable codes, standards and regulations concurrent with its corporate wide commitment to excellence in engineering. The AE QA program is consistent with these corporate QA pelicies, goals and objectives.
2.2 PROGRAM REOUIREMENTS The AE has established and implemented a quality assurance program in accordance with contractual requirements. The contract also provides that appropriate nationally recognized codes and standards such as those pubilshed by ASMC, ANS, ASTM, IEEE, ANSI, etc. will be applied and followed. The AE QA program complies with the NRC-Licensing requirements contained in Title 10, Code of Federal Regulations, Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants (ICCFR50, Appendix B)." This program description demonstrates the AE's methods of complying with each of the applicable criteria in 10CFR50, Appendix B. 2.3 PROGRAM ELEMENTS To fulfill the requirements for quality assurance on the planning and design of the Balance of Plant, assigned portion of the NSSS, the integration of the NSSS with the Balance of Plant and the procurement of items for which the AE has procurement responsibility, the AE Quality Assurance Program has been O 17E-6 Amend. 63 Dec. 1981
estabiIshed. The progra described herein was initiated in the Fail of 1973
) and applied to all work performed since then. The program and changes thereto V are prepared and approved by the Quality Assurance Manager, concurred in by the Project Manager, and approved for release and implementation by the Vice President, Breeder Reactor Division. This program has been structured and defined in accordance with contractually established requirements, with major program elements as il lustrated in Figure 17E-2. This figure shows that the program is made up of a progrm management practice compimented by those programmatic practices unique to the design, procurment and manufacturing phases or activities of the project.
In other sections of this description, the methods and techniques 1 hat wil I be impimented to conduct progra practices are described and include those requirements that are imposed on suppliers / subcontractors to assure that Individuals or groups within their organizations who are performing quality assurance f unctions have suf ficient authority and organizational freedom to ef fectively impiment their respective progrms; and that quality related activities are perf ormed with appropriate equipment and under suitable environmental conditions. For ease of NRC-Licensing review, these practices have been aligned to correspond with the appropriate criteria of 10CFR50, Appendix B. Figure 17E-3 of this description is a matrix cross-referencing 10CFR50, Appendix B, the contractually established QA progra requirements and the BRD documents or procedures that implement each criterion and requirement. Attachment 1 is a brief summary of each procedure. 2.4 PROGRAM IMPLEMENTATION The Architect-Engineer functional organization of QA Program responsibility is shown in Figure 17.1-4. The second level includes management type f unctions while the first level is primarily work practice-oriented programs concerned with direct control and verification through inspection, examination and testing. 2.4.1 PROGRAM PLANNIFE The AE QA progrm applies to planning and ot gineering and procurment administration Irrespective of whether it is saf ety related. The program is impimented through a series of procedures which prescribe the methods of accomplishing activities affecting qualltf . The preparation, release and control of project procedures is described in Subsections 5 and 6. 2.4.2 TRAINING AND INDOCTRINATION The AE has established a training and Indoctrination program under the control of its Project Operations Section. This training is accomplished in group sessions and individual discussions covering the purpose, scope, and implementation of the quality assurance manuals, procedures and Instructions. Indoctrination and training sessions are conducted for alI new project members. These sessions cover the QA Program Plan, Procedure Indices and
- - Procedures D
17 E-7 Amend. 63 Dec. 1981
applicable to the mployee. In addition, Individual procedures are addressed in group sessions of personnel respcnsible for perf orming activities af fecting qual'ty, including ali engineering personnel through the group supervisor leves. These sessions emphasize and reiterate that the QA Progrm Plan, proceder es and instructions tre mandatory requirments which are enforced through the authority of the Vice President, Breeder Reactor Division. Work assignments, principles and techniques involved, and responsibilities are addressed in individual sessions with the Group Supervisors. Further training is given by attendance at courses given in house or at recognized learning institutions. Records are kept f or each Individual . The tralning and Indoctrination progrm encompasses quality assurance engineers who verify that f unctions delegated to suppliers and subcontractors are properly aca>mplished. Quality assurance perscnnel who perf orm source surveil lance of non-destructive examinations wil l be qualif ied and certif ied in accordance with SNT-TC-1 A. 2.4.3 RESOLUTION OF OUALITY ASSURANCE REOUlREMENTS The provisions f or application of " Quality Assurance Holds" to documents when there are disagreenents regarding QA requirments are covered in Subsection 3 of this progrm deccription. The resolution of other horizontal disputes arising from dif ferences of opinion between quality assurance and other sections which cannot be resolved at the intra-project managerial level is accomplished by decision of the Vice President, Breeder Reactcr Division. 2.4.4 MANAGEMENT REVIEW A managment relew to assess the scope, implanentation, ef fectiveness and currentness of toe QA Progrm is scheduled to be perf ormed at f our month intervals by a Management Review Committee comprised of the Vice President, Greeder Reactor Division, QA Manager, Project Manager, Project Operations Manager, Licensing Manager, and the two Project Engineering Managers. Minutes of the meeting are pubilshed and kept for the record. In addition, the QA Manager must prepare a mor,thly memorandum type report for the Vice Fresident, Breeder Reactor Division and the Client detailing the current status of the QA Program. 2.4.5 fJNUAL ASSESSMENT l An assessment of tne scope, impimentation and ef fectiveness of the AE CRBRP QA Progran is performed annually. The assessment is conducted by designated corporate personnel or consultants from outside the Breeder Reactor Division to assure that the progrm is meaningf ul and ef fectively complies with the criteria of 10CFR50, Appendix B. The tem documents the results of the assessment in a report to the Vice President, Breeder Reactor Division. 2.4.6 OUALITY ASSURANCE PROGRAM REVIEW l The results of management reviews, annual assessments, external audits including Authorized inspection Agency Audits, and internal audits, contract scope changes, project interf ace and Intrastructure changes as well as other input are considered in maintaining the QA Progrm current. This QA Program description is reviewed at least annually and shall be modified as necessary to keep it current and up-tcr-date. 17 E- 8 Anend. 63 Dec. 1981
- 3. DESIGN CONTROL 3.1 DESIGN CONTROL PLANNING AND ASSIGWENT The AE executes his design activities through a Cognizant Engineer system.
The plant is broken down into manageable unit systems, each of which is assigned to a Cognizant Engineer who is responsible for alI design activity for his system. He is supported by all the engineering disciplines and specialties required to execute the design of his systas. He is the focal point for the receipt and the release of Information concerning his syste. The Cognizant Engineer reports to a Group Supervisor who in turn reports to a Discipline Section Manager. The AE Project Organization is shown in Figure 1.4-7. 3.2 FUNCTION RESPONSIBILITY Engineering is performed by four engineering discipline sections; Mechanical / l Nuclear, Electrical / Instrumentation, Stress Analysis Engineering and Civil / Structural, each under a Section Manager. An engineering discipline section is comprised of a series of groups, each of which is headed by a Group Supervisor responsible to his Section Manager. Work is performed within an Individual engineering group, and checked by another engineer of the same discipline before it is presented to the Group Supervisor for review. If the work in question is a calculation, it is rpproved by the Group Supervisor. If the work is a procurement specification, it is reviewed and concurred with by all af fected Section Managers, the Quality Assurance Manager, the Engineering and Construction Services Section Manager, and the Procurment Manager. After resolution of alI comments, concurrence is obtained from the Procurment O V Manager on alI procurement specifications. Final approval of procurement specifications is given by the Cognizant Section Manager and a Project Engineering Manager. Procedures are established to assure that alI engineering activities affecting design are carried out in a planned, controlled and orderly manner. 3.2.1 ENGINEERING AND CONSTRUCTION SERV lCES The Engineering and Construction Services provides expertise in the areas of materials, special processes, codes and standards, constructibility, maintainability, operability, rellabilIty, availability and accessibility for in-service inspection. The design engineering groups accurately translate the applicable regulatory requirements and design bases for safety-related structures, systems and components into specifications, drawings, procedures and instructions. 3.2.2 LICENSING AND ENVIROWENTAL SECTION The Licensing and Environmental Section determines federal, state, and local legal requirements and assures that the requirements of these regulatcry bodies are included in the design and construction specifications. 3.2.3 PROCUREMENT SECTION The Procurement Section detennines the overalI adequacy and suitability of the equipment and construction specifications to support the method of O procurement. - 17 E-9 Anend. 63 Dec. 1981
3.2.4 QUAlllY ASSURANCE SECTION 40 lhe Quality Assurance Section provide", enqincering support by determininq the quality assurance in uirements applicable to ecch system, asstn inq that apprnpriate quality s tandards are specified, assuring that g) deviations and changes from such s tandards are controlled, det ermin quality assurance elem nts applicable to each procurement action, revicuing and approving quality assurance requirements and accompanying acceptance criteria in procurement, inspection, or test documents and assuring that all specialists, including those of the Engineering and Construction Services Section and Procurerent Section, have reviewed and concurred with the tech-40 nical documents as evidenced on the document. review and concurrence form. This includes assurance that adequate review and selection for application 8 suitability and the use of valid industry standards is conducted for ma-terials, parts, equipment and processes that, are essential to safety-related functions of the structures, systems and components. 13 .bESIGN DATA CONIFOL Unbaselined system design information is controlled by the use of
" Controlled Information Data Transmittals" (CINDT) up to the issue of a 40j s n ption (SDD) for project use. After that, each system is controlled by its SDD or other baselined Principal Design Documents (PDDs).
CINDTs are used for transmittal of specific ncw design information among design organizations prior to such information being incorporated into a 40 baselined document. Design information is transferreri from engineer to engineer or from engineer to drafting room via a Controlled Information Data Transmittal form which is filed for the purposes of traceability. 45 4d Approved PDDs are subjected to control measures which assure timely and 8 positive processing in order to prevent inadvertent use of superseded design information. Document control measures are described in Sub-section 6. Design engineering groups prepare their technical documents with the assistante of the Engineering and Construction Services Section,
] the Licensing Section, Procurement Section and the Quality Assurance Section.
3.4 DESIGN DOCUMENT CONTP,0L Drawings, generated by the AE or received from other project parti-40 cipants, are collected and~ controlled by the filing section of the AE design and drafting group. All othtr design documents are collected and controlled 53 l /,0j by the Document Control Group of the Project Operations Section. Procedures are implemented for the revicw, approval, release, distribution, collection and storage of documents involving design interfaces and changes thereto. Whenever a standard "off-the-shelf" component is to be used, the responsible engineer defines a design and performance envelope for the component that. is used as the basis of the procurement action after adequate application review and selection. 3.5 DESIGN REQUIREMENTS INDEX AND INTERFACE CONTROL 40 Each Cognizant Engineer maintains a system design notebook which contains a design requirements index. Major interface requirements imposed g by other systems, which are derived from overall plant design criteria or 17E-10 Amend. 53 Jan. 1980
from design configuration Integration, are listed in the Index. As each [,) design requirement, including criteria and Interface requirements, is b Identified, the cognizant engineer enters it into his design requirments index noting its origin and status. He also enters in his index the documents in which it is used as a basis of design. Ther., when later requirements arrive superseding prior Information, he revises alI information derived from It, using his notebook and associated Indices as a record of where requirements are used as a basis of design. The Section Manager may direct termination of a design requirements index when the information is verified as having been incorporated into a baselined document and the maintenance of the index no longer serves a usef ul purpose. Major Interf ace requirements imposed on and by each system are listed in the SDD along with the baselined PDD controlling each Interf ace. This may be an Interface Control Document (ICD). ICDS control ling RM interf aces are concurred in by the LRM prior to final approval and release. In checking his design requiremerts, he also assurt.,s that specifications for suitably controlled conditions are included which assure: (1) the use of appropriate equipment, (2) a suitable environment for accomplishing the activity, e.g., adequate cleanliness, and (3) compilar.ce with necessary prercquisites for the given activity. 3.6 DESIGN VERIFICATION All design documents generated by the AE are subjected to the regimen of checking, review and approval described in this Appendix. In addition, the AE
% has established a system for independent design review (IDR) performed by its Chief Engineers together with a representat!ve from Quality Assurance and appropriate specialists from Licensing and Engineering and Construction Services when applicable. Each Cognizant Section Manager develops a list of items which shalI require an IDR based on guidance provided in CRBRP procedures. Typical itens subjected to IDR are conceptual and preliminary major general arrangements, major process and instrumentation diagrms, major equipment specifications and other major system or design documents, such as seismic criteria documents and overalI plant criteria. Project schedules identify the work areas subjected to these reviews, and the point in work development at which they take place. These reviews are established as hold points beyond which work cannot proceed until completion of the review. These design reviews are conducted af ter completion of alI technical review and sign-of fs of the concerned designs in accordance with documented procedures.
All individuals responsible for design verification are other than the original designer and his immediate supervisor. Topics to be used as a basis for IDR are listed in CRBRP procedures and include review for delineation of acceptance criteria for inspections and tests. 3.7 DESIGN DOCUMENT REVIEW AND APPROVAL REOUlREMENTS Upon completion, technical documents, other than calculations and drawings, are submitted to a regimen of review, comment, and correction by 17 E-11 Amend. 63 Dec. 1981
O engineers of all participating disciplines other than the persons who pre-pared the document. This includes assurance that design characteristics can be controlled, inspected, and tested. Calculations and drawings are checked and corrected upon their completion. After completion of the checking / correction cycle, technical documents, including drawings, are put through a review and approval regimen starting with the Group Super-17 visors and proceeding up through the Section Managers and Project Engineer-O Am nd. 53 Jan.1980 17E-lla
1 i Managers. The Quality Assurance Manager is part of the review and approval process and he assures that proper inspection and test criteria have been included. Sign-of f sheets ar e generated and retained, testifying to the completion of the proper review and approval cycle f or each type of document l generated. Specifications f or procurement of standard canmercial items are
- subject to the established review and apr.roval process f or technical documents. Changes to baselined documents including field changes are 4 authorized by approved Engineering Changes Proposals (ECPs) that describe the i changes to be made. The change is then processed through a system of Internal review and approval, which subjects it to the same design controls that were applied to the original design, 3.8 DRAWING REVIEW
- Drawings are checked using a multicolored system in which every item on the
! drawing has a line drawn through it Indicating either acceptance or rejection. When an item is marked as incorrect, the desired correction is indicated. The correcting draf tsman checks of f each item on the check print as the correction Is made. When the drewing has been corrected to the satisf action of the checker, the check print is filed and retained in accordance with the records requirements. 3.9 2ESIGN SCALE MODEL 1 Design activities such as the development of piping and ductwork, conduit, and j cable tray arrangements are perf ormed in conjunction with engineering design g scale models of the Reactor Containment, Reactor Control Building, Reactor l Service Building, Steam Generator Building, and Turbine Generator Building which are being constructed by the AE. The models will show all systems - within each building necessary to insure an Interference free design. The AE performs the modeling work regardless of which project participant is developing the design of the system. The flow of design information to the model shop is controlled by the use of CINDTs issued by the cognizant system engineer, the cognizant building engineer, and the draf ting / design squad leader. 3.10 CALCULATION VERIFICATlGN Hand calculations are checked by a second party with qualifications at least equal to those of the person who performed the calculation. The checking
! process produces a separate copy of t'ne calculation being checked with comnents f or resolution. Af ter resolution of all check comments, the checker signs and dates the original calculation cover sheet and initials each original calculation sheet. The checking copy is filed in the calculation notebook.
O 17 E-12 Amend. 63 Dec. 1981
i
- 11. TEST CONTROL 11.1 TEST PROGRAM REOUlREMENTS The AE delegates execution responsibility for testing and test control practices to suppliers by contracts. The AE includes requirements for written test programs in his procurement and/or construction specif Ications. These reouirements include the identification of all testing required to demonstrate that structures, systems and components wilI perform satisf actorily in service; the training and appropriate qualification of pe:sonnel conducting tests; written test procedures which incorporate or reference the requirements and acceptance Iimits. Test procedures generated during procurement of l ccrnponents are reviewed by the AE's engineering and quality assuracco organization to assure that they comply with requirements of the particular procurenent specif Ications. These test procedures are reviewed to assure that alI prerequisites for the given test have been specifled; that adequate test instrumentation and equipment are delineated; that each test is required to be performed under suitable environmental conditions with adequate test methods; and that test results are required to be documented and evaluated to assure that test requirements have been satisfied. Test items that are modified, repaired, or replaced are tested in accord 3nce with the original test program l requirements or alternate procedures which are reviewed in the same manner and to the same extent as required for the original .
11.2 SUPPLIER TEST PROGRAMS
/ Each supplier performing manuf acturing activities is required by contract to k establish a testing control practice for which testing is required. The test control practice will include the following elements:
- 1. Identification of required testing to demonstrate that the iten will perf orm satisf actorily in service and that testing activities are identif ied, documented and accomplished in accordance with written control led procedures.
- 2. Written test procedures that incorporate or reference the requirements i
and acceptance limits contained in applicable design and procurement documents.
- 3. Written test procedures that include:
- a. Instructions for testing method and test equipment acd Instrumentation.
- b. Provisions f or the foi lowing as appropriate:
o Calibrated instrumentation o Adequate and appropriate equipment o Trained, qualifled, and Iicensed or certifled personnel o Preparation, condition, and completeness of Itaa to be tested p) o Sultable and controlled environmental conditions t i V 17 E-25 Anend. 63 Dec. 1981 _ . . , . - ,_ _ _ _ _ _ _ _ _ . ~ . . _ _ , _ ._
. Mandatory inspection hold points for witness by purchaser, contractor, or authorized inspector
. Provisions for data collection and storage
. Acceptance and rejection criteria
. Methods of documenting or recording test data and results.
- 4. Test results are documented, evaluated, and acceptance status identified by a qualified, responsible individual or group, 11.3 PRE 0PERATIONAL AND OPERATIONAL TESTING 40 The Engineering and Construction Services Section of the AE prepares preoperational and startup test specifications for those systems and components f r which it has been assigned responsibility in its contract.
53. 11.4 TEST RESULTS 40 When a specification contains performance test requirements, the appropriate engineering group in the AE organization reviews and dispositions the test results. Quality Assurance will verify that this is done. The AE periodically audits the suppliers' test control practice to assure imp 12 mentation and adequacy. 40 53 Amend. 55 17E-26 June 1980
- . .. _. _ _= . =- . ,
t
- 14. INSPECTION, TEST AND OPEpATING~ STATUS i
The execution responsibilities for inspection, test and.oper3 ting status measures are delegated to suppliers through contracts. Suppliers, who are assigned responsibility for mac..i acturing, are required to establish and impicment practices to indicate the status of inspections and tests performed upon individual items throughout fabrication, assembly and test by using such markings as stamps, tags, labels, routing t cards or other suitable means. These practices will include provisions for: ,
.a. Inspection, test, and operating status of structures, systems and components being known throughout fabrication and asser$1y.
- b. Controlled application and removal of inspection and welding stamps and status indicators such as tags, markings, labels, and stamps.
- c. Controlled bypassing of required inspection, testt ind other critical operations through documented measures under the cognizance of the QA organization.
45l d. Ider tification of the st tus of deviating, inoperative, or malfunctioning structures, systems, or components to prevent inadvertent use. The AE monitors the suppliers' practices for indicating inspection, s test and operating status and periodically audits suppliersipracticos to
) 40 assure implementation and adequacy.
f l ps 17E-29 Amend. 45 July 1978
- 15. DEVIATING MATERIALS. PARTS AND COMPONENTS 15.1 CONTR^L OF DEVlATIONS The execution responsibilities f or the identification, documentation, notification, segregation, disposition and reinspection of deviating items or services are delegated to suppliers / subcontractors. These practices are designed to assure that measures are established to control materials, parts, or ccmponents which do not conform to requirements in order to prevent their inadvertent use of instal lation. The deviation control practice includes the foflowing elements:
- a. Establishment of disposition responsibility
- b. Documentation and reporting
- c. Review, evaluation and disposition The responsibility to control deviating materials, parts and components related to equipment manufacturing and resulting subcontracting, is delegated to equipment Suppliers by Contract.
15.2 BEVIEW AND APPROVAL OF DEVIATION REPORTS All reports of deviations that are proposed to be dispositioned " accept-as-Is", " repair", or "as modif ied" are forwarded to the AE f or approval, or to obtain the approval of the same organization that approved the requirements not met; dispositions pertaining to safety related Itans and those which might require major design changes as defined in Project procedure are forwarded to the owner for approval. Submitted deviation reports are reviewed in accordance with documented procedures which also provide for the roview of deviations for consideration as reportable defects and noncompliance under 10 CFR Part 21 and as reportable def Iciencies under Par. 50.55 (e) of 10 CFR 50. The AE has established a Nonconformance Review Board (NRB) whose members have final authority in establishing dispositions and approving dispositions for items and services reported on deviation forms. The membership of the NRB is the QA Manager as chairman and the appropriate engineering discipline Section Managers or their designated alternates. The NRB functions in accordance with documented procedures which also estabi tsh the requirements for record retention, filing, and subsequent forwarding to the owner. Records are retained and deviation reports are analyzed to assess the existence of any adverse quality trends. Adverse quality trends are reported to responsible organization management. 15.3 SUPPLlER DEVlATION CONTROL SYSTEM Each supplier / contractor, who is assigned responsibility for manuf acturing or construction of Itms by the AE, is required by contract to establish and implement a practice for the control of deviating materials parts or components. These deviation contrci practices wilI include the foilowing clements:
- a. Identi f ication, documentation, segregation, review, disposition, and notification to af fected organizations of deviating materials,
, parts, components, or services. 17E-30 Amend. 63 Dec. 1981
1 3 conducted by trained perr.connel that do not have direct responsibilities In the areas being audited. This program is executed by the organization outlined in Figure 17E-1. 18.2 INTERNAL AUDITS Internal audits are conducted by members of the Quality Assurance Section in accordance with written directives and written procedures. Upon conclusion of the audit evaluation, a rough report is prepared and a debriefing held with all of the affected parties. Immediately after the debriefing, the final audit report is sent to the Vice President, Breeder Reactor Division, Project Manager, Project Quality Assurance Manager; and Cognizant Project Engineering Manager. The cognizant representative from the activity audited, his supervisor, Quality Assurance Group Supervisor and the responsible organization manager supervisor, are required to respond to the audit report, in writing, within ten working days to the Quality Assurance Manager, delineating the corrective actions recessary to correct the findings of deviations revealed by the audit and the schedule for their completion. Verification of corrective action is promptly performed at the end of the scheduled implementation to assure corrections have been accompiished. Failure to obtain an approved extension of the rep!y due date or to respond to the audit report or to complete proper corrective action will cause the initiation of a corrective action request. The Quality Assurance Manager may grant one extension of the correctivo action schedule, in writing, not to exceed 20 working days. Additional extensions, not to exceed 60 working days, are granted in writing by the Project Manager or Assistant Project Manager, d with the concurrence of the Quality Assuranco Manager. When extensions are noi granted, a CAR wili be issued. Audits evaluate both the degree of compliance with established procedural methods and the effectiveness of the methods for the purpose for which they are intended. Audits of each project area will be conducted at least once in each twelve month perio:1. The Indoctrination and training program are included as a regular part of the scheduled project auditing program. 18.3 EXTERNAL AUDITS External audits are conducted of preselected procedural and work areas of-suppliers and vendors in addition to the normal surveillance activities. The audit of each supplier's program is designed to include .m objective evaluetion of quality-related practices, procedures and instructions; the effectiveness of implementation; and the conformance with policy directives. These audits include the evaluation of work areah activities, processes and items, and the review of documents and reports. Scheduled audits are supplemented by unscheduled audits where the need becomes evident. Manufacturer-identified special processes would be typical work areas that would be subjected to audits in addition to the normal surveillance. The audits are conducted from checklists prepared for the audit in question. The audit team is comprised of Quality Assurance personnel supplemented by selected discipline engineers from the engineering groups. The results of the i audits are documented in audit reports, audit report responses, and finding q reports or corrective action requests as may be applicable. 17E-37 Amend 63 Dec. 1981
18.4 INTERFACE AUDITING The Burns ar:d Roe design control concept requires that an "SDD Notebook" be naintained for each system by its Cognizant Engineer. Three lists in this notebook which are part of the interface control practice are the Design Requirements Index, the Interfaces imposed Index and the Parameter List. The status, traceability and currentness of these lists are part of each audit of system design control conducted on each system. They are therefore regularly audited as part of the scheduled audit program which covers ali systems in the project. The Design Requirements are der ved from controlled information received by the subject system from other systems (either from within Burns and Roe or from other project participants) which define conditions or para:neters imposed on the subject system. In a similar manner, the subject system defines its requirements on other systems and lists them in its " Interfaces imposed index". In addition, when the situation warrants, a nonscheduled interface audit is conducted. 18.5 AUDIT F!NDINGS REVIEW Summaries of audit findings and corrective actions are included in the monthly Quality Status Report submitted to the Vice President, Breeder Reactor Division and the Client. These reports are reviewed by the Management Review Committee to evaluate quality trends and ef fectiveness of the QA Program. O O 17 E-38 Amend. 63 Dec. 1981
~ . . . . . . . . _ . . . . . . .
O O O APPENDIX 0 PROGRAM PLAN BRD IMPLEMENTING DOCUMENT OR PROCEDURE CRITER10N SUBSECTIONS NO. TITLE I. Organfration Section 1; 2.3, Appendix V il QA Program 1.3, 2.2, 2.3.2, E-l.$ System and Equipment Classification 2.3.3, 2.4.1, PC-7.1 Indoctrination and Training 2.4.3, 2.5.2 QA-1.18 Training and Certification of QA Personnel QA-4.3 Project Audit Iil 2.7, Section 3 D-1.4 Drawing Checking snd Review Design Control 4.6 D-3.3 later-Organizational Drawings E-1.1 System Design Description E-1.1-1 System / Subsystem Designativ s E-1.2 Calculations E-1.2-1 Auxiliary Steel Calculations N 7 4 E-1.3 Engineering Studi . E-1.24 Using Fast Flux Test Facill'ty (FFTF) Experience FIGURE 17E-3. MATRIX OF 10CthSO APPENDIX B AND 'HE QUALITY ASSURANCE PROGRAM f1AN. kn. l3 k. we e Co ci 6-* W
BRD IMPLEMENTING DOCUMENT OR PROCEDURE APPENDIX B PROGRAM PLAN CRITERION SUBSECTIONS NO. TITLE E-1.4 Basic Model and Engineering Design Model III Design Control E-1.5 System and Equipment Classification
."-1. 6 Equipment Numbers and Nomenclature (Continued) E-l.7 Drawing Contrcl E-1.7-1 Classifying and Issuing Drawings E-1.7-2 Review of AE Construction Drawings & Specification s by Constructor E-1.7-3 Sequence of Operations E-1.12 Incorporation of Safety & Environmental Require-ments in Design E-1.13 Incorporation of Specialty Requirements in Design E-1.13-1 Instructions for the Incorporation of RAM Re-m quirements in Design
- j E-1.13-2 Codes and Standards N
L E-1.13-3 Materials, Welding and Hondestructive Examination E-1.13-4 Maintenance and In-Service Inspection E-1.13-5 Constructibility E-1.13-7 Cleaning and Cleanliness E-1.13-8 Packaging, Shipping, Receiving, Storage and Handling E-1.13-9 Piping Stress Analysis E-1.13-13 Radiation Protection E-1.15 Engineering Changes E-1.16 Holds E-1.18 Technical Document Review and Release E-1.18-2. Baselining Design Infomation E-1.19 Interface Control E-1.19-1 Internal Interface Data Report E-1.20 Independent Design Review E-1.21 Overall Plant Design Description E-2.1 Preparation of Specifications pp E-2.1-1 Initiation and Close-out of Developa.ent Require-a c) ments Specification [R to E-4.1 Preoperational ana Startup Test Soecifications FIGURE 17E-3. (CONT'D. ) MATRIX OF 10CFR50 APPENDIX D AND THE QUALITY ASSURANCE PROGRAM PLAN. O O O
O n 0 L) APPENDtX B PROGRAM PLAN D MMNHNG EUENT OR PROUNRE CRITERION SUBSECTIONS NO. TITLE-Ill Design Control E-2.3 Technical Evaluation of Bids (Continued) E-2.4 Vendor / Contractor Docurr.ents E-2.5 Vendor / Contractor Waiver Requests PC-3.2 Project Information Center PC-3.3 Technical Information - Receipt and Control t'C-3.6 Ulstribution-QA-1.16 QA Review of Submittals QA-1.66-1 QA Review of Design / Document Submittals QA-1.17 Review of Specification for Quality m . Requirements
;;f QA-1.17-1 Specification Review Checklist w
L QA-1.21 Bid Review for Quality Requirements , IV Procureraent Document 1.3, 4.3, 4.4, E-1.1 System Design Description Control 4.6.1 E-1.1-1 System / Subsystem Designations E-1.15 Engineering Changes E-1.16 Holds . E-1.18 Technical Document Review and Release E-2.4 Vendor / Contractor Documents E-2.7 Preparation of Purchase Requisitions g 2j ae P
$1"n FIGURE 17E-3. (CONT *D.) MATRI'( 0F 10CFR50 APPENDIX B AND Tile QUALITY ASSURANCE PROGRAM PLAN.
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1 i fy Q l' L/ V U) APPEllDIX B PROGRAM PLAN BRD IMPLEMENTING DOCUMENT OR PROCEDURE CRITERION SUBSECTIONS NO. TITLE j V Instructions, Proce- E-1.13-9 Piping Stress Analysis dures and Drawings E-1.13-13 Radiation Protection (Continued) l E-1.16 Holds l E-2.1 Preparation of Specifications l E-2.1-1 Initiation and Close-out of Development Require-ments Specification E-2.4 Vendor / Contractor Documents l E-2.5 Vendor / Contractor Waiver Requests l IL-1.2 Preparation of Safety and Environmental Reports l 0 L-1,3 Preparation of Responses to NRC Questions rp L-2.3 Reporting of Defects and Noncompliances e- L-2.4 Unusual Occurrences l PC-1.5 Procedure Preparation i PC-1.5-1 Lists and Guides Manual PC-3.2 Project Information Center PC-3.3 Technical Information - Receipt and Control PC-3.6 Distribution QA-l.2 Preparation, Control and Distribution of QA Instructions QA-1.3 Preparation of QA Procedures QA-1.19 Procedure Writing Format QA-3.1000 Project Surveillance
- QA-3.1000-1 Preparation of Project Surveillance / Acceptance l Checklists, Summary & Report Forms E-1.18-1 Assignment of Data Types E-1.18-2 Baselining Design Information EN 8e"
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- FIGURE 17E-3. (CONT'D.) MATRIX OF 10CFR50 APPENDIX B AND THE QUALITY j ASSURANCE PROGRAM PLAN.
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APPENDIX B PRCSRAM PL AN BRD IMPLEMENilMG DCCUMENT OR PRCCEDURE CRITERf0N SUDSECTIONS NO. TITLE Vi 3.4, 4.9.2 E-1.1 System Design Description Document Control E-1.1-1 System / Subsystem Designation E-1.7 Drawing Control E-1.7-1 Classifying and Issuing Drawings E-1.7-2 Review of AE Construction Drawings and Specifications by Constructor E-1.7-3 Sequence of Operations E-1.15 Engineering Changes E-1.18 Technical Document Review and Release E-1.18-1 Assignment of Date Types E-1.21 Overall Plant Design Description (OPUD-10) E-2.1 Preparation of a Specification E-2.1-1 initiation and Close-out of Development f<equirements Spectfications
- E-2.4 Vendor / Contractor Documents M L-1.2 Preparation of Safety and Envircnmental Reports e
PC-1.5 Procedure Preparation M PC-1.5-1 Lists and Guides Manual PC-3.2 Project Information Center PC-3.3 Technical information - Recelpt and Control PC-3.6 Distribution E-1.23 Control of Security-Sensitive information PR-1.10 Documenting Communications for Burns & Roe Designed Equipment FIGURE 17E-3. (CONT'D.) MATRIX OF 10CFR50 APPENDIX B AND THE QUALITY ASSURANCE PROGRAM PL AN. ne
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APPENDIX B PROGRAM PL AN ORD IM LEMENTING 00QJMENT OR PROCEDURE CR11ERlON SUBSECTIONS NO. TITLE vil Control of Pur- 4.2, 4.3, 4.', E-2.2 Pruqualification of Pldders chased Material, 4.6.2, 4.8, 4.9.1 E-2.3 Technical Evaluation of Bids Equipment and 4.9.2, 4.9.3, 4.10 E-2.4 Vendor / Contractor Documents Services E-2.5 Vendor / Contractor Walver Requests QA-1.11 Vendor Quality Assurance Prequellfication Program QA-1.11-1 Evaluation of Prequalification Questionnaire QA-1.12 Vendor QA Qualification Survey QA-1.12-1 Performance Evaluation and Reporting of Freeward Surveys QA-l.16 QA Review of Submittals QA-l.16-1 Review of Design / Document Submittats QA-1.21 Bid Review of Quality Requirements y I QA-1.25 *bnconf ormance Peview Board (NIO) m QA-3.101 Source Serveillaxe Q A-3.101 -1 Preparation and Control of Source Verification a Plans and Sci.edules N QA-3.101-2 Administration of the Source Surveillance Program QA-3.101-3 Preparation f or and Performance of Surveillance QA-3.101-4 Preparation and Issuance of Source Surveillance Reports PR-1.I Preprocurement Plenning PR-1.2 Bid Evaluation, Purchase Contract Negotiations and Award PR-1.4 Perchase Contract Amendments FIGURE 17E-3. (CONT'D.) MATRIX OF 10CFRSO APPIN0lX B AND THE QUALITY ASSURANCE PROGRM4 PL AN. ON n.
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APPENDIX B PROGRAM PL AN BRD IW'LEMENllNG DOCUMENT OR PROCEDURE CRITER10N SUBSECTIONS NO. Ti1LE Vill identification & 3.3.7, 4.11 E-l.6 Equipment Numbers and Nomenclature Control of Materlats Parts ano Components IX Control of Special 2.3.3, 3.3.2, 8.6 Processes E-1.13 incorporation of Specialty Requirements in Design E-1.13-3 Materials, Welding and Nondestructive Examination QA-1.18 Training and Certification of QA Personnel FIGURE 17E-3. (CONT'D.) MATRIX OF 10CFR$0 APPENDIX B AND THE QUALITY ASSURANCE PROGRAM PL AN. s-. Zm C0 n m
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- X Inspection 4.2, 4.3, 4.8, E-1.13-3 Materials, Welding and Nondestructive Examination 4.9.1 QA-3.101 Source Surveillance QA-3.101-1 Preparation and Control of Source Verification Plans and Schedules QA-3.101-2 Administration of the Source Surveillance Program QA-3.101-3 Preparation for and Performance of Surveillance i QA-3.101-4 Preparation and issuance of Source Surveillance Reports i
XI Test Control 3.6 E-2.4 Vendor / Contractor Documents I Q A-1.16 QA Review of Submittals i e-. ! N X11 { T
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' E-1.13-8 Packaging, Shipping, Receiving, Storage and Handling l E-2.4-1 Documentation Required by Const'.scror 'l 1 FIGURE 17E-3. (CONT'D.) MATRIX OF 10CFR50 APPENDIX B AND THE QUALITY ASSURANCE PROGRAM PLAN. F n F. :3 J & i G-a cn j - w i i I l l
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APP [NDly 0 PHOGRAM PL AN Of<D IMPLEMENilNG DOCUMlNT OR PROCl(HJRL CRiitRION SUBSECll0NS NO. TITLE Xill XIV inspection, Test 4.9.2, 4.9.3, 4.11 QA-3.101 Source Surveillance and Operat'nn QA-3.101-2 Administration of the Sourca Surveillance Program Status XV Nonconforming 2.6, 2.8, 2.9, E-2.5 Vendor / Contractor Walvar Requests M.s t er i a l s Par t s 3.7, 4.10 QA-1.13 Corrective Action Requests (CAR) or Components QA-1.25 Nonconformance Review Doard (Nf6) QA-1.1000 Deviation Repor ting and Control L-2.3 Reporting of Defects and Noncompliances
~ L-2.4 Unusual Occurrences N
7 XVI g Corrective Action 2.6, 3.7, 8.8 QA-1.13 Corrective Action Request (CAR) QA-1.25 tionconf ormance Review Boar d (NTO) QA-1.1000 Deviation Reporting and Control L-2.4 Unusual Occurrences FIGURE 17E-3. (CONT'D.) MATRIX OF 10CFRSO APPENDlX B AND THE qualify ASSURANCE PROGRAM PL AN 5$ on
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APPENDlX B PROGRAM PLAN 8RD 1MPLiMENT1NG DOCUMENT OR PROCEDURE CR1TER10N SUB5ECTIONS NO. TlitE XVi1 Quality Assurance 2.4.2, 3.8, 4.6.2 E-2.4-1 Documentation Required by Constructor Records 4.9.2 QA-1.18 Training and Certification of QA Personnel QA-3.101 Source Surveillance QA-3.101-1 Preparation and Control of Source veri f icatf or: Plans and Schedules QA-3.101-2 Administration of Source Verification Progro QA-3.101-3 Preparation f or and Perf ormance of Surveillance QA-3.101-4 Preparation and issuance of Source Surveillance Reports FC-3.1 Filing PC-7.1 Indoctrination and Training E-1.18 Technical Document Review and Release E-2.4 Venoor/ Contractor Documents Ft-3.7 Declaring, F! ling, and Retrieving Quality Records t N rn XVill 1 M Audits 2.5, 3.9, 4.12, QA-1.13 Corrective Action Request (CAR) j - Section 8 QA-4.3 Project Audit QA-4.5-1 Project Audit Checklist QA-4.3-2 Preparation of Project Audit Matrix Record j QA-4.4 Quality Assurance Audits at Contractors / Suppliers FIGURE 17E-3. (CONT'D.) MATRlX OF 10CFR50 APPENDlX B AND THE QUALITY ASSURANCE PROGRAM PL AN. i i nm
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Attachment 1 (/ OUALITY ASSURANCE MANUAL PROCEDURE DESCRIPTIONS PROJECT CONTROL BRD-PC-1.5 Procedure Preparation This procedure establishes the method for preparation, review, revision approval, and distribution of all BRD procedures and supplementary instructions except those numbered "BRD-QA-xx." BRD-PC-3.1 Filing This procedure establishes the methods for maintenance, coding, and filing of project documents and correspondence, including declared quality records in the Quality Records Center that will be transferred to the Owner. BRD-PC-3.2 Project Information Center This proceagre establishes the Project inforcation Center as the repository for reference information required for use by Project f- s Personnel. ERD-PC-3-3 Technical Information - Receipt and Control This procedure establishes the method for control and transmission of technical information for subsequent use in design documents including processing of Controlled Information Data Transmittal (CinDT) form. BRD-PC-3.6 Distribution This procedure establishes the method for traintaining distribution requirements of project documents. BRD-PC-3.7 Declaring, Filing, and Retrieving Quality Records Th's procedure establishes the method for declaration, filing, storage and retrieval of Quality Records in the Quality Records Center (QRC). BRD-PC-7.1 Indoctrination and Training This procedure establishes the requirements for Indoctrination and training of personnel in CRBRP objectiles and procedures, and functional training in the job-oriented specific technical, administrative, clerical, and ouality assurance activities. h G 17El-1 Amend. 63 Dec. 1981
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS PROJECT CONTROL INSTRUCTIONS BRD-PC-1.5-1 Lists and Guides Manual This instruction provides the method for authorizing, preparing, issuing and revising the Burns and Roe List and Guides Manual. 55 O l i l l l l l l Amend. 55 June 1980 17El-la
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS ENGINEERING BRD-E-1.1 System Design Descriptions This procedure establishes the method for development and control of system design descriptions and assigns responsibility for a system design description to a Cognizant Engineer. it also provides for the traceability of the design requirements throughout the design process. ' BRD-E-1.2 Calculations This procedure provides the method for selection and authorization, and checking, approving, superseding and volding preliminary and calculations. BRD-E-1.3 Engineering Studies This procedure defines the format and identification of engineering i studies and establishes the requirements f or review and approval of canpleted studies. BRD-E-1.4 Basic Model and Engineering Design Model i This procedure establishes the responsibilities and control governing the flow of inf ormation to and from the model shop applicable to plant design. BRD-E-1.5 System and Equipment Classification This procedure provides direction for determining appropriate codes and standards and for assigning classifications or categories. BRD-E-1.6 Equipment Numbers and Nomenclature j This procedure establishes a standard identification system for all plant j components. BRD-E-1.7 Drawing Control i'. This procedure defines the methods f or controlling the development, initiation, processing, checking, reviewing, approving, release, reproduction, and distribution of drawings. 4
\s -
17El-2 Amend. 63 Dec. 1981
- , - _ . . . . - . - _ . - . _ _ . - . _ - . ~ . . _ - _ , - . , . - . _ - _ - . - _ . _ - _ - . . . _
p QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS V ENGINEERING (Continued) BRD-E-1.12 incorporation of Safety and Environmental Requirements in Design This procedure establishes the method and assigns the responsibility for monitoring alI regulatory requirements, disseminating these requirements to implementing personnel and assuring that the design conforms to the regulatory requirements. BRD-E-1.13 incorporation of Specialty Requirements in Design This procedure establishes the methods by which design requirements concerning specialty subjects, such as materials, welding, NDE, cleaning, packaging, codes and standards, constructibility, rellability, avaliability and maintainability, are defined and Incorporated in the design. BRD-E-1.15 Engineering Changes This procedure establishes the method to control the Initiation, review, approval, and inp'.ementation of changes to base ilned principle design documents. O BRD-E-1.16 Holds This procedure defines the method for initiating, reporting and assigning reschtlon responsibility for engineering holds and Quality Assurance Holos rhat are imposed to identify and limit design and f abrication activities. BRD-E-1.18 Technical Document Review and Release This procedure establishes the sequence and minimum requirements for review and approval of ali technical documents except drawings before issue. It identifies required reviews and provides for the maintenance of the Document Status Report. O
\v/ '
17El-3 l Amend. 63 Dec. 1981
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS ENGINEERING (Continued) BRD-E-1.19 Interface Control This procedure establishes the method for identifying, documenting, reporting, and controlling interface information. BRD-E-1.20 Independent Design Review This procedure defir.es the methods and responsibilities for planning, conducting, and documenting independent design reviews. This procedure encompasses only Internal Design Review. BRD-E-1.21 Overall Plant Design Description This procedure establishes the methods for processing Initial criteria subject input to Overall P8 ant Design Description (OPDD-10), prior to baseline e.id changes thereto af ter baselining. BRD-E-1.23 Control of Security-Sensitive information This procedure defines the methods for controlling and safeguarding Security-Sensitive information. BRD-E-1.24 Using Fast Flux Text Facility (FFTF) Experience This procedure defines the follow up system to assure that valuable and applicable experiences from FFTF are laicorporated into the CRBRP design. BRD-E-2.1 Preparation of Specifications This procedure establishes the method for preparation and control of procurement and/or ccnstruction specifications utilizing a standardized format. BRD-E-2.2 Prequalification of Bidders This procedure establishes the method for selection and prequalification of prospective bidders. BRD-E-2.3 Technical Evaluation of Bids This procedure defines the methods to be used fc. erainetring review and evaluation of bids. O 17 El-4 Amend. 63 Dec. 1981
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS () ENGINEERING (Continued) BRD-E-2.4 Vendor / Contractor Documents This procedure provides the methods for receipt, handling, routing, recording, reviewing, approving, distributing, and return of Vendor / Contractor (V/C) document submittals. l BRD-E-2.5 Vendor / Contractor Walver Request (CWR) This procedure provides the method for processing Contractor Walver Requests (CWRs) from Contractors supplying / performing in accordance with B&R Specifications. BRD-E-2.7 Preparation of Purchase Requisitions This procedure defines the requirements and methods for preparation of a purchase requisition to be submitted to the Purchasing Department. BRD-E-4.1 Preoperational and Startup Test Specifications This procedure controls the preparation of all preoperational and start-up test specifications by B&R, and the review of externally-generated test specifications. s 4 e-~g
~-I 17El-5 Amend. 63 Dec. 1981
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS ENGINEERING INSTRUCTIONS BRD-E-1.1-1 System /Subsyst m Designations This Instruction def ines the project breakdown into systms and subsystes with identifying names and numbers. BRD-E-1.2-1 AuxIIIary Steel Calculattons This in.ctruction identifies the degree of ef fort by Structural Engineering for checking auxiliary steel calculations. BRD-E-1.7-1 Classifying and issuing Drawings This instruction provides for preparing, classifying, Issuing and revising drawings for information, project use, pre-construction use, and construction. BRD-E-1.7-2 Review of AE Construction Drawings and Specificottons By Constructor This instruction provides the method for the selection and review of Burns and Roe Construction Drawings and Specification by the Constructcr Resident Representative (CRR). BRD-E-1.7-3 Sequence of Operation This instruction defines the responsibilities of the contributors to the development and change cycle of Sequence of Operations. BRD-E-1.13-1 Reilability Assurance Analysis l This Instruction defines the methods to be utilized and tasks to be l accomplished for the CRBRP Reliability Program. BRD-E-1.13-2 Codes and Standards This instruction provides the requirements for inclusion of codes and standards in project design documents. l 17El-6 Amend. 63 Dec. 1981
(- QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS ENGINEERING INSTRUCTICNS (Continued) BRD-E-1.13-3 Materials, Welding and Nondestructive Examination (NDE) This instruction provides the requirements for inclusion of materials, welding and NDE in system design descriptions and procurement documents. l BRD-E-1.13-4 Maintenance and inservice Inspection and Survell lance This Instruction provides for the inclusion of maintenance, inservice inspection, and survelllance requirements in System Design Description. BRD-E-1.13-5 Constructibility This instruction provides for the incorporation of constructibilIty requirements in project design documents. BRD-E-1.13-7 Cleaning and Cleanliness This instruction provides for incorporation of cleaning and cleanliness requirements in project design documents. BRD-E-1.13-8 Packaging, Shipping, Receiving, Handling and Storage This Instruction provides for the incorporation of packaging, shipping, receiving, storage and handling requirements in project design documents. BRD-E-1.13-9 Piping Stress Analysis This instruction applies to all piping stress analysis performed for ASME Section lil, Class 2 and 3 and ANSI B31.1 piping. BRD-E-1.13-13 Radiation Protection This Instruction providos guidance for the analysis and incorporaticn of radiation protection requirements in project design documents. BRD-E-1.18 -1 Assignment of Data Types This instruction provides guidance for determining the organizational approval level required for design documents. BRD-E-1.18-2 Baselining Design Information This instruction provides for baselining design information in Principal Design Documents (PDDs). 17El-7 Amend. 63 Dec. 1961
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS O ENGINEERING INSTRUCTIONS (Continued) BRD-E-1.19-1 Internal Interface Data Report This Instruction provides the method of Identifying internal interface data requirements and their scheduled transmittal dates. BRD-E-2.1-1 Initiation and Close-out of Development Requirements Specification This Instruction provides direction from initiation through close-out of development programs required to support the CRBRP Nuclear Island activities, using Development Requirements Specifications (DPS). BRD-E-2.4-1 Documentation Required by Constructor This instruction provides instructions for collecting, preparing, and transmitting documents required by the Constructor prior to, wiih, and after the shipment of a finished item. DESIGN AND DRAFTING Drawing Checking and Review O BRD-D-1.4 This procedure establishes the minimum requirements for drawing checking and provides objective evidence of the checking activity. BRD-D-3.3 Inter-Organizational Drawings This procedure establishes the responsibilities for review and control of drawings submitted by other project participants. l l O 17El-8 Amend. 63 Dec. 1981
! . QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS i
LICENSING , BRD-L-1.2 Preparation of Safety and Environmental Reports 45l This procedure establishes the methods for preparation, revision,
' review and approval of B&R input to the SAR and the-ER. Revisions will be subjected to tne same regimen of reviews and approvals as the original report. ~
45 j BRD-L-1.3 Preparation of Responses to NRC Questions This procedure establishes the methods used to prepare concise and timely responses to questions rai:;ed by the Nuclear
. Pagulatory Comission (NRC) in conjunction with their review f the Safety Analysis and Enviromental Reports.
40
. BRD-t-2.3 Reporting of Defects and Non-Compliances
, This procedure establishes the method for review and reporting
; of defects or non-compliances as defined by 10 CFR 21 and
- significant' deficiencies as defined by Paragraph 50.55(e) of 10 CFR 50.
- BRD-L-2.4 Unusual Occurrences This procedure establishes the method for determining and reporting an unusual or unplanned event as required by RDT Standard F1-3T.
- 45 4
i i ' Amend. 45 17El-9 July 1978
1 QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS OUALITY ASSURANrf, BRD-QA-1.2 Preparation, Control and Distribution of Quality Assurance instructions This procedure establishes the guidelines for preparation, Issue, control and use of quality assurance Instructions by QA personnel. BRD-QA-1.3 Preparation of QA Procedures This procedure establishes the method for preparation and control c' "QA" designated procedures. BRD-QA-1.11 Vendor Quality Assurance Prequalification Progrm This procedure establishes the method of prequalifying a prospective bidder's quality assurance progr m for a bidder's list. BRD-QA-1.12 Vendor Quality Assurance Qualification Survey This procedure establishes the method and criteria for conducting a preeward survey and evaluation of a prospective vendor's or subcontractor's quality assurance / quality control syst s. BRD-QA-1.13 Corrective Action Request (CAR) This procedure establishes the method for requesting and obtaining l corrective / preventive action from the management of an organization responsible for repetitive quality assurance deficiencies or for significant probles that have reculted in or could result in adverse Project Quality Conditions. BRD-Qh-1.16 Quality Assurance Review of Submittals This procedure provides methods and responsibilities guidelines for Quality Assurance review of submitted documents. BRD-QA-1.17 Review of Specification for Quality Requirments This procedure provides guidelines for a standard approach for quality assurance review of specifications. BRD-QA-1.18 Training and Certification of Quality Assurance Personnel This procedure establishes the training and certification methods for quality assurance personnel who perf orm nondestructive examinations and inspection of materials, parts, structures or systms. O 17El-10 Aniend. 63 Dec. 1981
( QUALITY ASSURANCE I4ANUAL - PROCEDURE DESCRIPTIONS x -) OUALITY ASSURANCE (Continued) BRD-QA-1.19 Procedure Writing Format This procedure provides a guide to the standardized format to be used in writing procedures f or the BRD. BRD-QA-1.21 Bid Review for Quality Requirments This procedure provides guidelines for a standard approach for quality assurance review of bids. BRD-QA-1.25 Nonconf ormance Review Board (NRB) This procedure provides the structure and responsibility for a Nonconformance Review Board whose members have final authority within B&R in establishing dispositions. BRD-QA-1.1000 Deviation Reporting and Control This procedure establishes the methods and for Identifica1!on, g3 documentation, control and dispositioning of deviating It ms or services. j Also includes detemination of corrective action to prevent recurrence. BRD-QA-3.101 Source SurvellIance This procedure describes the Source Surveillance Progrm which implements Source Survelllance and inspection Requirements. BRD-QA-3.1000 Project Surve!IIance This procedure provides a means and guidelines for examining the of fectiveness of the project quality assurance progrm on a less formal basis than auditing. ,q
,,Y 17El-11 Amend. 63 Dec. 1981
QUALITY ASSURANCE MANUfL - PROCEDURE DESCRIPTIONS QUALITY ASSURANCE (Continued) BRD-QA-4.3 Project Audit This procedure establishes the guidelines for auditing project activities for conformance to established procedures and assessing the effectiveness of the procedures. BRD-QA-4.4 Quality Assurance Audits at Contractor / Suppliers This procedure establishes the guidelines for auditing activities of vendors and contractors for conformance to approved quality assurance program plans and the implementation and effectiveness of established procedures that execute those plans. O l l l 17El-12 Amend. 8 O i Dec. 1975 i
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS OUALITY ASSURANCE INSTRUCTIONS BRD-QA-1.11-1 Evaluation of Prequalification Questionnaire This Instruction provides direction for evaluating a QA Prequalification Questionnaire when considering the suitabliity of a vendor as an acceptable source. BRD-QA-1.12-1 Performance, Evaluation and Reporting of Preaward Surveys This Instruction defines the actions required in planning, performing and reporting the results of a preaward survey. BRD-QA-1.16-1 Review of Design / Document Submittals This Instruction provides the checklist that defines the minimum QA review of design documents and vendor submitted documents. BRD-QA-1.17-1 Specification Review Checklist This instruction provides the checklist that defines the minimum QA review , g of technical specifications. b/ BRD-QA-3.1000-1 Preparation of Project Surveillance / Acceptance Checklists, Summary and Report Forms This instruction defines the requirements for a surveillance checklist, methods of summarizing the results and reporting them. BRD-QA-3.101 -1 Preparation and Control of Source Verification Plans and-Schedules This instruction describes the considerations which must be addressed when preparing Source Verification Plans and Schedules or revisions thereto. BRD-QA-3.101-2 Administration of Source Surveillance Program This instruction describes methods to assure surveillance required by the Source Verification Plans are scheduled and performed. O ' 17El-13 Amend. 63 Dec. 1981
QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS OUALITY ASSURANCE INSTRUCT 10NS (Continued) BRD-QA-3.101-3 Preparation f or and Perf ormance of Survell lance This Instruction c'escribes the methods and considerations addressed when preparing and perf orming surveillance activities. BRD-QA-3.101-4 Preperation and Issuance of Source Survelllance Reports This instruction defines the requirements and provides the guidance for preparation and issuance of Source Survelllance Reports. BRD-QA-4.3-1 Project Audli Checklist This Instruction provides for the preparation of checklists to be used in project and home of fice QA activities audits. BRD-QA-4.3-2 Preparation of Project Audit Matrix Record This instruction provides for the preparation and maintenance of an audit matrix record to be used as a guide in determining required audit areas. O O 17El-14 Anend. 63 Dec. 1981
1 QUALITY ASSURANCE MANUAL - PROCEDURE DESCRIPTIONS PROCUREMENT PROCEDURES BRD-PR-1.1 Preprocurement Planning This procedure establishes requirements for Procurenent Planning and covers the preparation of a Request for Proposal (RFP). BRD-PR-1.2 Bid Evaluation, Purchase Contract Negotiations and Award This procedure covers actions following issue of RFPs, for receipt and evaluation of preposals and negotiations of purchase contracts and contract award. BRD-PR-1.3 Purchase Approval Requests This procedure provides for the preparation and processing of purchase approval requests, preparation of supporting documentation and issue of - purchase contracts with covering purchase orders. BRD-PR-1.4 Purchase Contract Amendments This procedure defines the requirements for planning, evaluating, negotiating, approving and issuing contract amendments. BRD-PR-1.5 Escalation This procedure provides the guidelines for evaluating proposals which include escalation as a condition of contract acceptance. BRD-PR-1.10 Documenting Communications for B&R Designed Equipment This procedure provides the method of controlling communication between Stone & Webster, Vendor / Contractor, and Burns & Roe during the bidding cycle and afier contract award. i C) (- 17El-15 Amend. 63 i Dec. 1981
O i THIS PAGE WAS INTENTIONALLY DELETED. O O 17E2-1 Amend. 63 Dec. 1981
O AMENDMENT 63 LIST OF RESPONSES TO NRC QUESTIONS There are no new NRC Questions in Amendment 63. O O Qi
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