ML20086T563
| ML20086T563 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/20/1991 |
| From: | Madson M NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20086T561 | List: |
| References | |
| NUDOCS 9201060329 | |
| Download: ML20086T563 (165) | |
Text
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t k ! (. PRAIRIE ISt.AND NUCLEAR GENERATING PLANT t SB0/ESU PROJECT I L i ? DESIGN REPORT ,.~ ii 'i 4 esgue L' Project Engineer l-Revision 1 w201060329 9112zs PDR ADOCK 05000282 P PDR
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s } Rev. 1 '/, NORTHERN STATED POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT CONTENTfl 3.3 SYSTEM DESIGli AND INSTALLATION 3.3.1 Diest1 Encine Coolina Svatnm "J.3.2 Q12agl Fuel Oil System 3.3.3 Diesel Air Startitl1..EYDICE
"!.3.4 Diesel Lube 011 Systelu J.3.3 Qignol Combustion Air and Exha ut Systen 3.3.6 Diesel Generator _RQpm Verltilglion Systqmg ,
3.3.7 Diesel Encine Auxili,DLrv SVstems Pinina and ; Eggipment Recruirements and Maior.isda 3.3.8 Mechanical Desian and Fabrication Codes 3.3.9 Electrigal Power Distribution and Switchaear 3.3.10 Diesel Generator Cotitrols , Indication, and Alarms 3.3.11 Diesel Generator Operatina Descrintion 3.4 FUEL OIL STORAGE AND TRANSFER SYSTEM l 3.4.1 Ewictional RecuireaqDia and Descr1D112R 3.4.2 Qasian Peauitrenanta 3.5 DESIGN STANDARDS 3.5.1 NUREG 0800 S_1;.and0.rd.. Review Plan ( S RP). 3.5.2 JEEE Standards 3.5.3 NRC Reculator / Guides and 41111eting 3.5.4 NFPA Standardg 3.5.5 ANSI Standards 3.5.6 Northern States Power Standards 3.5.7 Elpor Daniel Procqdureq 4.0 L1EH Q5]D6 BUILDING 4.1 SEISMIC DESIGli CLAS3IFICATION
- 4.1.1 Structur.gg 4 ~.1. 2 J:lectrigl / Mechanical /HVAQ. Buildina Suonort Systeng ,
4.2 SAFETY DESIGN CLASSIFICATION 4.2.1 Structurfqn 4.2.2 D,Milding_.Aur200rt Svet;.2EE 5 ii
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NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT 3 9.QNTIETA i 4.3 BUILDING STRUCTURE DESIGN 4.3.1 Desian Iqada 4.3.. R.tructqtal_.Reaian Basis 4.3.3 Construction Materi.gla 4.3.4 Load CombinatioDH 4.3.5 DeniqD.anc) Analysis Procedurea 4.3.6 Structural AcceDtance Cr.itoria ' 4.3.7 S3Inctural/ArchiteStural Fire Protection ; Renuirernents 4.3.8 Buildina Extgrior OpeniDSR 4.4 BUILDING ELECTRICAL DESIGN 4.4.1 Lichtina 4.4.2 Power Distrjbytlon and_ Loads 4.4.3 firaIndino , 4.4.4_ C_qFSRDi.qntinna 4.4.5 fire Deteeti,qn ; 4.4.6 S.ggMr.ity 4.4.7 Radiation liRD11.2T1REI 4.5 DUILDING/ MECHANICAL /HVAC DESIGN 4.5.1 Fire Protection DesiaD 4.5.2 P.19plina/Draina 4.5.3 ILqEtina . Ventilation, and Air Conditioning DLVACl 4.5.4 S.tation Air:Reatirements 4.6 DESIGN STANDARDS 4.6.1 InJREG 0800 StaDdard Review Plan (SRP) 4.6.2 IEEE SlaDdQIda 4.6.3 Reculations and Reaulatory Guidga 4.6.4 NFPA Standards ' 4.6.5 M,SI ( Standarda
, 4.6.6 Rullding_,Q.25102 4.6.7 ILqrlhernltiat?s PSwgr, Standaydb ,
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f- i PRAIRIE ISLAND NUCLEAR GENERATING PLANT f SB0/ESU PROJECT t e a f DESIGN REPORT i t { Approved: dNG 4#A 12/20/91 Project Engineer n i I i'. ., f' ' Revision 1 ! b 9201060329 91122:3 FDR ADOCK G500D282 . P GDR 1
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NORTHERN STATES POWER COMPANY I PRAIRIE ISLAND NUCLEAR GENERATING PLANT p_0_HTJJiTS 1.0 JNTRQQQCTION AND BACKGROUND
1.1 INTRODUCTION
1.2 CONTENTS OF DESIGN REPORT
1.3 BACKGROUND
REVIEW OF STATION BLACKOUT PROGRAM 1.3.1 }Lg.qu1atorv _}iiatsry 1.3.2 Industry Pqpition 1.3.3 ErAirie Io1and P1 ant S.ngsfLi.p,_S.tp.qi. Lea 1.4 SBO/ESU PROGRAM OBJECTIVE AND GOALS 1.5 RESPONSE TO THE NRC RULE ON STATION BLACKOUT 1.6 ELECTRICAL SAFEGUARDS UPGRADE 1.7 QA PROGRAM APPLICATION 1.8 DEFINITIONS
1.9 REFERENCES
2.0 OVERVIEW
EXISTIl{Q_DI. SIGN AND UP_QRADED DESlqll 2.1 EXISTING SAFEGUARDS AUXILIARY POWER SYSTEM 2.2 UPGRADED SAFEGUARDS AUXILIARY POWER SYSTEM / 2.2.1 DS . 411sL _ D6 Diesel Generators a.nst Suenort SYstSEi 2.2.2 SafecuardfLllectriqal Systga 3.0 RTlplL GENEBATQR.AND AUXILIARY SYSTEMS._- DESIGN A!!Q_ IRS.TALLATI.QH 3.1 SEISMIC DESIGN CLASSIFICATION 3.1.1 RLesel Enaine Auxiliary Systems 3.1.2 p_19JdL Generator Room Venti.lation System 3.1.3 Electric Power QJ1tILb_ulti_on. Instrumentation. and Cont;rols 3.1.4 Fuel Oil Storag.e and Transfer System 3.2 SAFETY DESIGN CLASSIFICATION 3.2.1 Diesel Encirlp_&qXLLlary Systems 3.2.2 Diesel Generator Room Ventilation Systems 3.2.3 Elg_q.1 r ic Power Distrik_qtion . Instn1Aenta_t;.LQn DJ1d Controln 3.2.4 Fuel _ Oil Storace and TransfeE J_ystem
. Rev. 1 C NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT CONTlHIS 3 . ') SYSTEM DESIGN AND INSTALLATION 3.3.1 Dipsel Encine Coolina System 3.3.2 Diesel Fuel Oil System 3.3.3 Diesel Air Startina System 3.3.4 Diesel Lube Oil System 3.3.5 Diesel Combustion Air and Exhaust Systgg 3.3.6 Diesel Generator Room Ventilation Systems 3.3.7 Diesel Enaine Auxiliary Systems Pinina qqd Eauioment Reauirements and Materialg 3.3.0 dechanig33 Desian and Fabrication Codes 3.3.9 Electrical Power Distribution and Switchacar -
3.3.10 Diesel Generator Cpntrols. Indication, and Alarmn 3.3.11 Diesel Generator Operatina Description 3.4 FUEL OIL STORAGE AND TRANSFER SYSTEM l 3.4.1 Punctionsi Recuirementg_and Descrintion 3.4.2 Desian Reautrements 3.5 DESIGN STANDARDS 3.5.1 NUREG 0800 Standard Review Plan (SRP) 3.5.2 IEEE Standarda 3.5.3 ERC Reculatory Guides and Bulleting 3.5.4 REPA Standards , 3.5.5 ANSI S$3rdards 3.5.6 Northern States Power Standards 3.5.7 Guor DanieLProcedures 4.0 N_EW DS/D6 BUILDING 4.1 SEISMIC DESIGN CLASSIFICATION , 4.1.1 Structures 4.1.2 Electrical /Maghanical/HVAC Buildina Suonort Systemg 4.2 SAFETY DESIGN CLASSIFICATION 4.2.1 Structures 4.2.2- Buildina Suonort Systems 11 j
__. m . . - . _ _ ___ _ _ _ _ _ . . _ ._. i Rev. 1 , i, NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT CONTENTS 4.3 BUILDING STRUCTURE DESIGN 4.3.1 Desian Loads 4.3.2 Structural Desian Dasig 4.3.3 Construction Materials 4.3.4 Load Combinations 4.3.5 Desian and Analysis Procedures j 4.3.6 Structural Accentance criteria 4.3.7 Strugtyral/ Architectural Fire Protect 1QD l Re. c.n11r_ement.a : 4.3.8 Buildina Exterior Oneninas ' 4.4 BUILDING ELECTRICAL DESIGN 4.4.1 Lichtina
-4.4.2 Power Distribution.and Loadr.
4.4.3 Groundina 4.4.4 gammynicationo 4.4.5 Fire Detection 4.4.6 Security 4.4.7 Badiation Monit.aring 4.5 BUILDING / MECHANICAL /HVAC DESIGN 4.5.1 Fire Protection Desi SD j 4.5.2 Plumbina/Dr31DE 4.5.3 ligatina . Ventilation, and Air Conditionina 1163C1 4.5.4 Statiqn Air Reauirements 4.6 DESIGH STANDARDS e 4.6.1 NUREG 0800 Standard Review Plan (SRP) 4.6.2 IEEE Standards 4.6.3 Beaulations and Reculatory Guides 4.6.4 NFPA Stan g d_g 4.6.5 ANSI S.landards 4.6.6 Buildina Codes 4.6.7 Northerr._ States Power Standards 4.6.8 Othe_t Reference Documents i i l I l 111
nu.. 2 NORTHERN STATED POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT
- QONTENTS 5.0 DIESEL GENERATOR INTERFACE AND ELECTRICAL SAFEGUARDS UPGP,ADE 5.1 SEISMIC DESIGN CLASSIFICATION 5.2 SAFETY DESIGN CLASSIFICATIO?!
5.3 UPGRADED SAFEGUARDS AUXILI.1Y AC POWER SYSTEM DESIGN 5.3.1 General Descriptio.D 5.3.2 Preferred. Alternate. and_ Standby Power Source Conficuration 5.3.4 4160V Confiauration - Safecuards Busen 5.3.9 33,0V Confiauration - Safeauardo Buses Voltaae Restoration / Load Reiection/ Load 5.3.5 Restoration 5.3.6 Em2rcency Response Computer System _ Existing 5.3.7 D5/D6 Control Scheme Tie-In With 2.1D11% 5.3.8 Mpin Control Room "G" Panel Modification 5.3.9 Detailed _Denian 5.4 DESIGN STANDARDS (SRP) 5.4.1 EUREG 0810 Standard _ Review Plan 5.4.2 IEEE Standards 5.4.3 Reculatory Guides 5.4.4 ANSI Standa,Ida 5.4.5 Northern States Power Standards 5.4.6 Electrical Eauippent Plan 5.4.7 Structural Recuirements ATTACHMENTS
.5-A Electrical Cable and Cable Tray Coding 6.0 ..Q SLING WATER SYSTEM MODIFICATION 6.1 SYSTEM FUNCTION 6,2 121 COOLING WATER PUMP UPGRADE FOR ADDITION OF DIESEL GENERATORS AND 7.0 IMPLEMENTATION PLAN AND 2 ELECTRICAL SYSTFJi UPGRADE FOR PRAIRIE ISLAND UNIT 1 7.1 SBO/ESU PROJECT CONSTRUCTION ACTIVITIES 7.2 SDO/ESU PROJECT STARTUP ACTIVITIES 7.3 SBO/ESU PROJECT SUPPORT ACTIVITIES 8.0 SAFEGUARDS AUXILIARY POWER SYSTEM QEEBATION 8.1 EXISTING SAFEGUARDS AUXILIARY POWER SYSTEM DESCRIPTIO 8.2 EXISTING SAFEGUARDS AUXILIARY POWER SYSTEM POWER AUXILIARY OPERATION 8.3 UPGRADED SAFEGUARDS SYSTEM DESCRIPTION 8.4 UPGRADED SAFEGUARDS AUXILIARY POWER SYSTEM OPERATION iv
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I I Rev. 1 , NORTNERN STATES POWER COMPANY , PRAIRIE ICLAND NUCLEAR GENERATING PLANT l CONTENTA , 1 FIGURES l Figure 2-1 Existing one-Line Electrical Diagram of
.the Emergency AC Power System Figure 2-2 Upgraded One-Line Electrical Diagram of the Emergency AC Power System Figure 3-1 DS HT Cooling Water System Figure 3-2 DS LT Cooling Fater System Figure 3-3 D6 HT Cooling Water System Figure 3-4 D6 LT Cooling Water System Figure 3-5 D5/D6 Fuel Oil System Figure 3-6 D5 Fuel Oil System Figure 3-7 D6 Fuel Oil Systems Figure 3-8 D5 starting Air System Figure 3-9 D6 Starting Air System Figure 3-10 DS Lube 011 System Figure 3-11 DG Lube Oil System Figure 3-12 D5 Combustion Air & Exhaust System Figure 3-13 DG Combustion Air & Exhaust System Figure.4-1 Arrangement of New D5/D6 Building and CSTS 21 and 22 Figure 4-2 D5/D6 Building Ground Floor Figure 4-3 DS/D6 Building Mezzanino Floor Figure 4-4 DS/D6 Building Operating Floor Figure 4-5 DS/D6 Building Upper Dock figure 4-6 D5/D6 Building Roof Figure 4-7 D5/D6 Building Elevation Figure 4-8 D5/D6 Building Elevation Figure 4-9 D5/D6 Building Fuel Oil Storage Vault
& Basement "
Figure 6-1 Cooling Water System Simplified Flow Diagram Figure 6-2 Cooling Water Screenhouse Figure 7-1 SBO/ESU Project Integrated Schedule V
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NORTHERN STATED POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT CONT.ERT_Q TABLES Tabic 2-A Diesel Generator Loading DBA in First Unit and Hot Shutdown for Second Unit (Load) as a Function of Timo Table 4-A Damping Factors Table 4-B Tornado Generated Missiles Table 4-C Fire Barriers Table 8-A Existing and Proposed Voltage Restoration Sequpnce Table B-B Proposed Loading Sequence l l h 1 . V1
t Rcv. 1 NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT STATION BLACKOUT / ELECTRICAL SAFEGUARDS UPGRADE PROGRAM DESIGN REPORT
1.0 INTRODUCTION
AND BACKGROUNQ
2.1 INTRODUCTION
Thin Station Blackout / Electrical Safeguards Upgrade (SBO/ESU) DeLign Report provides the following: a) Background information and descriptions of the existing Prairie Island emergency power system. b) Information and discussion on the SBO/FSU Program hardware additions which includes two additional new emergency diesel generator sets, a new building and now electrical distribution equipment. c) Information regarding the proposed operation of the modified emergency power system. The introductory section provides a background review of the Station Blackout issue, the SBO/ESU Program objective and goals, and the NSP response to the NRC rule on Station Blackout, whid includes a summary of the hardware modifications. This report is being provided to the NRC to support NRC staff approval. A separate submittal containing the Safety Evaluation, proposed Technical Specification changes, and the Significant Hazards Analysis will be docketed early in 1992. 1.2 CONTENTS OF DESIGN REPORT This report contains the following sections: Section 1.0 provides an introduction and background for the Station Blackout and Electrical Safeguards Upgrade (SBO/ESU) Program. Section 2.0 provides an overview of the existing emergency power distribution system and an overview of the revised emergency power distribution system which includes two additional diesel generato*s, DS and D6, and upgraded electrical safeguards 4kV and 480V systems. Section 3.0 discusses the design and installation of the DS and D6 safety-related diesel generators. Section 4.0 discusses the design and installat. ion of the new DS/D6 Building and support systems, and the relocation of two existing Condensate Storage Tanks that stand near the nes building site. 1
Rev. 1 Section 5.0 discusses the interface of the now emergency diesel generators to the electrical safeguards distribution system and the upgrade of the electrical safeguard 4kV and 480V distribution systems. Section 6.0 discusses the repowering of the 121 Cooling Water Pump to increase the reliability of the Cooling Water System. Section .0 discusses the implementation plan for the addition of the diesel s,enerators and the electrical system upgrade. Section 8.0 discusses the operation of the existing emergency power system and of the proposed systems for Unit 1 and Unit 2.
1.3 BACKGROUND
REVIEW OF STATION BLACKOUT PROGRAM in!.s section provides a summary of the Station Blackout Issue (SBO) from its-inception in 1975 to its resolution through the ef forts of the Nuclear Utility Management and Resources Counci] (NUMARC) and the Nuclear Regulatory Conmission (NRC).
'1.3.1 Fagulatory. liisitory The Reactor Safety Study (WASH-1400) issue in 1975 showed that station blackout was a significant contributor to the potential total risk from nuclear power plant accide'its. The NRC designated station blackout as an Unresolved Safety Issue USI A-44 and issued a Task Action Plan, TAP A-44, in July 1980.
The NRC staff researched various aspects of the issue through supporting contractors, documenting the research results in various NTIREG reports. This effort culminated with presentation of the NRC staff's technical . findings in NUREG-1032 issued on June 15,.1985. The NRC identified proposed rulemaking in the Federal Register, Vol. 51, No. 55 March 21, 1986. The NRC proposed to amend regulation 10 CFR Part 50 by adding section 50.63 and by adding a paragraph to General Design Criteria 17, Appendix A of 10 CFR Part
- 50. These additions would requira that all nuclear power plants be capable of coping with a station blackout for some specified period of time. Additionally, the NRC proposed issuance of a Regulatory Guide on Station Blackout to recommend a means for meeting the requirements c* Section 50.63 of 10 CFR Part 50. i The draft Regulatory Guide was first issued for comment in March 1986. The final Regulatory Guide 1.155, Station Blackout, was issued in June 1988.
On June 21, 198", the NRC issued the final rule on Staticn Blackout which endorses the approach contained in the nuclear industry report NUMARC 87-00 as an acceptable method for meeting the requirements of the rule. This rule became effective July 21, 1988. The intent of the rule was to reduce the contribution of statica blackout to the overall risk of a core meltdown. 2 l
Rev. 1 1.3.2 IndmLtry Pou.ition . The nuclear utility industry formed a working group under NUMARC that developed a guideline for responding to the Station B'dNout Issue. This group, the Nuclear Utility Group fs;. Station D ' 7ut (NUGSBO), produced a guide (NUMARC 87-00) for evaluat. m ,he probability for a plant tc encounter a station blackout cont.:.%on. It also presented five initiatives for plants to use to address the more important contributors to station blackout events. This guidn also establishod a method to determine the minimum required coping time for each plant to be able to maintain reactor core and NSSS systems integrity until AC power is returned. 1.3.3 Frairio Island Plant _Soecific Jtudien Two studies were completed by teams consisting of representatives from Plant Engineering, Plant Opera *. ions, Nuclear Technical Services, Nuclear Engineering and Construction, Production Plant Maint.enance and a consultant engineer, Fluor Daniel, Inc. The Station Blackout Coping Study was completed in September 1987. , This study showed that the Prairic Island Plant can safely respond to a Station Blackout condition of four hour coping duration as determined by the analysis required in NUMARC 87-00. This si.udy was done based on the configuration which will exist when Prairie Island has met the NUMARC SBO Initiatives. The NUMARC Initiatives express relative risk by the number of hours the assumed loss of all normal sources of safeguards AC power continues. This is called the " coping duration". Plants with a less secure power supply _ system have to be able to cope with a blackout for a longer period of time. NUMARC's position is that if a plant's coping duration is greater than the four hour category, then improvements must be made by the Licensee until the plant is within the four hour coping duration category. The addition of two safeguards diesel generators is the action Prairie Island will take to move-from an-eight-hour to a four hour coping category. When installation of the new diese~t generators is' complete, Unit 1 can provide an alternete power source for Unit 2 (and vice versa)_under blackout conditions. . A Study of the Station Blackout Issue and Addition of Safeguards
'Diebel Generators, issued in SepLember 1987 reviewed the safeguards Electrical, Auxiliary Foodwater and Reactor Coolant Pump seal' injection systems plus the proposed SBO rule. It described modifications. to comply with the rule and addressed issues with those systems. It also identliied issues for additional study.
l~. i SBO/ESU PROGRAM OBJECTIVE AND GOALS The primary objective of the Station Blackout / Electrical Safeguards Upgrade (SSO/ESU) Program for Prairie Island is to implement those plant nodifications and software elements (procedures, reporting mechanisms and analyses) that will be necessary to comply with the 3
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final NRC rule on Station Blackout and rer ove the regulatory uncertainty and negative availability factor associated with the ' unit's sharing of safeguards diesel generators. Implementation will' be consistent with the industry positica as represented in-the NUMARC Initiatives and the Guidelines published in NUPARC 87-00.
- 1) The short term goals for SB0 included:
o Respond to the SB0 Rule using the .NUMARC 87-00 fornat, within 270 days of July 21. 1988 - Complete.
.o Upgrade the transmission grid and offsite power restoration procedures - Complete, o Provide interim procedures to provide alternate AC using the ,
D3 and D4 generators - Complete. o Reviso ' the Er.ergency Operating Procedures to adC.ress coping with 580 with the present plant equipment -Cumplete.
- 2) The long term goals for SB0 are:
- o. Achieve .a four, hour coping duration per MUMARC 8'l-00 by adding two new diesel generators.
-o. ' Achieve alt' rnate AC availability within 10 minutea or if not possible, one hour, by utilizing the- safeguard diesel' .
generators as alternato AC power for the other unit. o Update the coping analysis to reflect the actual design for , the new' diesel generators. Additional benefits of the SBO. Program' include:
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1); Inrtall additional safeguards diesel generators, to: , o Reduce the regulatory uncertainty associuted with sharing emergency diesel generators between units. . o Reduce the loss of onsite AC power contribution to core melt risk, o -Eliminate the two unit shutdown exposure caused by the present diesel ;w nerator Limiting condition for Operatica (LCO) . o Provide increased emergency on-site power margin as well as margin for future loads.
- 2) Provide for powering of 121 Cooling Water Pump to reduce two unit shutdown exposure caused by the Cooling Water System LCo.
3). ' Provide integrated planning, design and installation for diesel generator plant interface. 4
Rev. 1 i L1.5 RESPONSE To T11d-NRC FULE ON STATION BLACKOUT , The formal report required by the NRC SB0 Rule was culmitted to the $ Commission on April 13, 1985. This response was formatted in accordance with guidance frota NUMARC and addressed completed and future activities required to meet the NUMARC Initiatives. For Prairie Island, the response included: o Description of the coping cLtogory and coping duration. . o Descr.iptien of completed ar.d planned procedate revisiot.s. 1 o The schedule for the addition of D5 anel D6. H , ; o Description of the a] ternate AC concept. In resporise to the NRC Rule on Station Blackout, an alternate source of AC power for the essential (safeguard) electrical equipment buses will be provided. The addition of tne alternate AC source of power will be accomplished by the following SB0 Program pjant modif! cations: ,
- 1. D1/pj_, Diesel Geneistor Mditicp.
Two new diesel generators, DS and D6, will be added to the Dnirie Island Plant. These generators will serve as a dedicated source of emergency pownr for Unit 2 and as an alternate AC source of pawer for Unit 1. The existing D1 and D2 diesel generators will serve, as <ledicated ettargency AC poner for Unit 1 ard as an alternate AC source of power for Unit 2. The new diesel generators will be sized to provide adequate onsite emergency power to Unit 2. Additienal capacity 'will be provided for 121 Cooling Water Pump and
-possible future loads.
- 2. New -Diesel Gerleiator P,gil.dirig A new Class I building will be constructed to house US and D6 diesel generators, support equipment, and new switchgear for Unit 2.
- 3. E l at1 L I,tt te r f a c e ,
Electrical, instrument and control equipment will be installed i to permit the use of D5 and D6 as onsite emergency sources for Unit'2 and as alternate AC for Unit - 1. The existing electrical power and contrcl systems for D1 and D2 will be
, modified to facilitate their use as onsite emergency sources fcr Unit 1 and'as alternate AC for Unit 2.
The control design will minimizo the impact of the additional equipment on plant operations staffing requirements for an 5 , I
/w Rev. 1 Appendix R safe shutdown condition by centraliz.ng local controls for diesel generatcr and switchgear operation. The electrical and controls design will permit the implementation i 4 of alternate AC within 10 minutes. Main control room !
instrumentation and controls vill be human engineered to allow i efficient control room operation of the diccel generators and j safeguards electrical syctems. Additic,nal switchgear will be provided to allow pawning of 121 Cooling' Water Pump from einhe- Unit 2 safeguard 4kV bus. i Additional suitchgear cubicles will be provided for future loads.- l Plant computer monitering of the new diesel ver erators and - i related electrical systems will be provided. To the fullest extent possible, construction sequencing will be planred to allow installation during unit operation, with minimal disruption of plant activities. Critical installation 1 interfaces will be planned to occur during planned unit l refueling outages. t 4, 121 Coolirr2 Watyr Pugo Uncrade As part of the SB0 project, a new 4kV switchgear power feed will be provideri for 121 Cooling Water _ Pump. This pump is comraon to both units. The pump motor will be upgradad to safety related. 'The new switchgear will be designed to be fed ! from either DS or D6 diesel generators. This upgrade will increase the availability of tne Cooling Water System and provide the basis to request a Technical Specification change to a ' Limiting Condition for Operation which presently requires shutdown of both units in the-event of extended inoperability of one of the safeguards die.1al-driven cooling water pumps.
' 5. $_in Control Board Modifi_gation Space will be provided on the Main Control Room panels for DS and D6 instrupentation and controls and for additional switchgant controls. An evaluation was performed to determine the intormation and control capability required co operate the o diesels and safeguards buses, and to determine the prudence of modifying G Panel versus providing space on each unit's F Panel. The evaluation considered cost, single and tw:, unit outage time, safe operations, construction complexity and operating philosophy for the two basic options.
The. option chosen was to replace G Panel. The work will b3
-performed as part of the Plant Interface diu:uesed above.
This will involve placing all required instrunentation and controls on a new "G" Panel. 6
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- 6. S,inglatpr MqdQLeation .
The plant control room simulator will be modified to reflect the addition of the D5 and U6 diesel generators. Thie modification will include changing the simulator software and the simulator control board to include the new diesel generator and electrical switchgear control functions. The Emargency Response Computer System Simlator (ERCSS) sof tware will also be modified to emulate tue ERCS in the plant. 1.6 . ELECTRICTLL SAFEGUARDS UPGRADE
-In conjunctien with tha SBO Program modifications '.isted in Section 1.5, an upgrade- of the electrical safeguards 4kV and 480V distributions systems will also be provided. The Electrical Safeguards Upgrade (ESU) Program will perform the following modifications:
_ Replace %nt.of 4kk cafeguarc's buses in Unit 2 and expansion of l c
- Unit .1 safeguard buses.
L o Replacement of 480V safeguard buses in Units 1 and 2. o Frovide additional 480V safeguard buses and 4kV switchaear capacity for. future loads, Units 1-and 2. o- Provide 480V safeguard bus alternate feeds in Unit 1 and 2. o Improve voltage regulation, principally at the 480V lavel, in
' Units 1~and 2,.
o Improve circuit coordinatiori by eliminating subfed 480V . Motor Control Centers-{MCCs) on safeguards buses.
' 1. 7 - CA PROGRAM APPLICATION-L . Northern States Power Company has established and is implementing an : Operational- QA Plan to govern operation and htodification activities of the Prairie Island Nuclear Plant. The Operational QA Plan des::ribes' in ~ general terms -compliance with 10CFR S0, Appendix B, and has been reviewed and found to be acceptable by the-NRC QA Branch. Corporate level Administrative Control Directives (N1ACDs) and Administrative Work Instructions' (N1AWIs) establish the ~q, respotesibilities and requirements for implementing the requirements of the Operational'.QA Plan for dasign, procurement & constructi a activities. The QA program - for SBO/ESU will consist of these j Corporate. and Department procedure requirements, supplemented ' ;y Project Procedures.(PPs) and Section Work Instructions (SWI's).
Design and selected safety related and Non-safety related-procurement activities for SBO/ESU will be performed by Fluor l Daniel, Inc. (FDI) using their QA program, which has been reviewed and evaluated against 10CFR 50, Appendix B by NSP. The balance of 7
procurenent activities wi.11 be performed by NSP under their QA procedures.
~With regard- to construction act.ivities , contractors furnish fabrication and construction services, while NSP will provide the QA/QC procedures and personnel, and overall construction management including prucurement, site engineering and training.
Suppliers of safety related items and materials provide their own QA/QC programs, which have been evaluated by NSP or NSP's approved ' representatives, FDI and Nuclear Utility Procurement Issues Committee (NUPIC), for compliance to 10CFR50, Appendix B. The diesel- generator supplier, SACM of France, is required by contract through FDI to- apply a QA program taeeting the requirements of 10CFR50 Appendix B. NSP and FDI have performed three QA audits of SACM along with several surveillance trips. In addition, the NRC Vendor Inspection Branch has made inspection trips- to SACM f acilities . The NRC Electrical Branch has witnessed SACM's factory acceptance run tests for the project's diesel generators. 1.8 DEFINITIONS blternate AC-(AAC) lg.u_rce: An alternating current (AC) power source that is available to and
' located at or nearby a nuclear power plant and meets the following ,
requirements; 1) is connectable to but not normally connected to the offsite or onsite _ emergency AC power system; 2) _has minimum potential for common mode failure'with offsite power or the oncite ' e:te gency . AC power sources; 3) is available in a timely manner af ter - the onset of station' blackout; and; 4) has sufficient-
. capacity and reliability- for operation _of all systems required for coping with Station Blackout (SBO) and for the tine required to bring and maintain the plant in safe shutdown (non-design basis accident).
E92R931pn t : A~ piece of equipment required to perform a specific function within
.a system.
P p_13ss 1E: o Label applied to all electrical equipment that has been seismically. and environmentally qualified to support all required safety
=related equipment and safety system functions. (New equipment in 05/D6 Building) ,
lion-Qlass 1E1. Label applied tu all electrical equipment qualified to support all non-cafety related equipment and non-safety system functions.
-Desian Basesi 8
i i Rcv. -1 Information which identifies the specific functions to be performed by a _ structure, system, and component of a f acility., and the specific- values or ranges of values chosen for controlling L parameters as reference bounds for design. Enging_ered Safeauards Featurf1p_f Safet2uards) t Provisions in the plant which implement methods to retain fission products by the containment for operational and accidental releases
- beyond the ' reactor coolant boundary and limit finsion prodt'et releases to minimize population exposure, prevent occurrence, or to minimize the effects of serious accidents.
E, ira,Jrotection Relaj;Adi Plant fire protection features including those which preve7t fires from starting, detect, control or extinguish fires or otherwise provide fire protection for structures, systems and components in accordance with 10 CFR 50 Appendix R commitments, Safoty EVE ?.uation Reports, Technical Specifications, and other documented commitments to the NRC concerning fire protection. T.nngj;igtlal Cqmp_pnent; A component in which movement must occur automatically, with or without operator action at the device location, to accomplish the nuc1 car safety furction of the component. py3G3,ina Basin Eag thauakp (OBE) :, That earthquake which, considering the regional and local geology , and seismology _and specific characteristics of local-subsurface material, could reasonably be expected to affect the. plant _ site during: the operating life of the plant, and produce the vibratory ground motion for which those features of the nuclear power plant necessary for continuen operation without undue risk to the health and safety of the-public are designed tc remain functional. - Safety Relatada Items 1 Any structure, system or component that provents or mitigates the consequences of postulated nuclear accidents that could cause undue b risk to the health and safety of the public.
.Rgfety RalAtgl Structurgf1 Safety _ reclated structures are those structures whose f ailure might cause or ' increase the severity of a loss-of-coolant accident or l:
result in an uncontrolled release of radioactivity which would produce radiation levels at the site boundary in excess of 1% of 10 g CFR 100 limits, and-those structures vital to safe shutdown and !- isolation of the reactor. Safety related structures include those structures that are foundations or supports for or that protect those systems and components clacsified as safety related. L L 9 o l
l l
. Ray. 1 Non-Safety Related jd;rygiures: u Non-safety related structures are those struc+.ures which may or may not be important to normal reactor operation but are not essential to safe shutdown and isolation of the rea : tor and whose failure could not result in the release of radioac+.ivity in excess of 1% of 10 CFR 100 limits.
Fp,fety Systems: Any systems or portions of systems which are necessary to remove heat directly from the reactor containment, circulate reactor coolant for any safety system purpose, control radioactivity released within the reacter containment, or control hydrogen in the reactor containment. Safe Shutdown Eprthauake_iSSF); An earthquake which is based upon an evaluation of the maximum earthquake potential considering the regional and local geology and seisrmology and specific characteristics of local subsurface material, it is that earthquake which produces the maximum vibratory ground motion for which certain structures, systems, and components are designed to remain funct'onal necessary to assure the integrity of the reactor coolant boundary, the capability to shutdown the reactor and maintain it in safe shutdown condition, and the capability to prevent or mitigate the consequences and accidents which could result in potential offsite exposures. The SSE defines that earthquake which has commonly been referred to as the Design Basis Earthquake. Hafe J_t}utdown (Non-Defilon BasLg_Accide;qt (Ngn-DBA)): In referenca to Staticn Blackout (SBO), the non-DBA means bringing the plant ta either Hot Standby or Hot Shutdown, since plants have the optlon of maintaining the RCS at normal operating or reduced temperatures. f,eisnic Categorv l A structure, system, or component designed to withstand the ef fects of a Safe Shutdown Earthquake (SSE) and remain functional because they are needed to assure the integrity of the reactor coolant pressure boundary, the capability to shutdown and maintain the reactor in a safe shutdown condition, the capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposure comparable to 1% of the 10 CFR 100 guidelines. This category has two subsets as follows: Seismic-Active Components which must remain operable during and or af ter an SSE in order to perform their seiety function. 10 l
R ev ., 1 J E!dEE19.7.Ea.fiE1X!1 Components which must maintain structural integrity during or af ter an SSE in order to perform their safety function. No> Seismic; Components that have no seismic requirements. Seismig IT Over L;. All non-sr M.ty-related systams and componento and their supporting systems e designed to ensure that the SSE does not cause their structural failure in a manner that will renult in damage to safety-related systems or ccmponents. Sinnie Fa Qurer,. An occurrence which results in the loss of capability of a component to perform its intended safety functions. Multiple f ailures resulting from a single occurrence are considered to be a single failure.
$11 tion I!La_qkout,_L1LCFR50. 2 SBO) :
" Station Blackout":means the, complete loss of alternating current
.(ac) electric power to the essential and nonessential switchgear buses in a nuclear power plant (ie, loss of offsite electric power system concurrent with turbine trip and- .une.vailability of the ensite energency ac power system). Steion blackout does not iaclude the loss of available ac power to buses fed by station batteries through inverters or by alternate ac nources as defined in this section -(10CFR50.2), nor does ic assume a concurrent single failure or . design basis accident. At single unit sites, any emergency . ac power source (s) in-excess of the number required to y meet minimum- redundancy requirements (ie, single f ailure) for safe
! shutdown (non-DBA) is assumed to be available and may be designated as an alternato power source (s) provided the applicable requirements are met. At multi-unit sites, where the combination of . energency ac power sources exceeds the minimum redundancy requirements for safe shutdown (non-DBA) .of all units, the remaining emergency ac power soucces may be used as alternate ac power-sources provided they meet the applicable requirements. If i' these criteria are not met, station blackout must be assumed on all the units. I~
-SA.uctare:
r l l' The . physical shield, foundation, or building which encloses, protects, and/or supports any plant system or component, or L protects plant operators. l- 11 l (
. . . . . -- - - . . - ~ . .
- 1 Rev. 1 a'
Dvstmu l A group of interdependent components required to perform a specific -
. function.
- 1.9 REFERENC.2S
" Study of Station Blackout Issue and Addition of-Safeguard Diesel l Generators", Northern States Power / Fluor, R/E 86Y730, September 1987. j i
I.3irie Island' Updated F ,~ty Ahalysis Report (USAR), Sections 1, ) 8, 10.and.14.2. j 10 CFR Part 50, S e c t.. ..a t i v. B6ackout Rule. NUMARC-8700 "Guidelino ' 4'N Bases for NUMARC Initiatives ) Addreasing- Station Blac? u - Nater Reactors", November, i 1987, l 1
" Loss of all. Alternating Ct. - nfor.aation Required by 10 l CFR 50, Section 50.63 (c) (1)", e .t e e of Apnl 13, 1989 to NRC. i
Proj ect for Addition' of Two Faergency Diesel Generators", NSP J
I letter of September 29, 1989 to NRC. Nuclear Specification for Emergency Diesel Generators D5 and D6, M-- -l
-870, . Northern States Power Company's Prairie Island Nuclear Generating. Plant.
NSP ~ letter to the NRC: " Reply to Questions on Design Re port for the Station Blackout / Electrical Safeguards Upgrade Project (TAC numbers 68588/68589)," dated July 10, 1991. K3P letter to the NRC: "Fupplemental information on Programmable Logic. Controllers for the Station Blackout / Electrical Safeguards. Upgrade Pr;oject (TAC numbers 68588/60589)," dated October 21, 1991. NRC Latter to. WSP -dated January 31, 1s90, entitled " Safety Evaluntion Related to the Emergency Diesel Generator Qualifichtion Plan (TAC Nos. 68588_and 68589)" 1 l I ! ) 1 \ li 12- i l l' I o i
~ Rev. 1 7 jo' f)VERVIEW: EY(SIU[G DESIGN At!!,0 UPGMQED DESIGN . 2.1 EXISTING SAFEGUARDS AUXILIARY POWER SYSTEM The existing Prairie Island Units 1 and 2 diesel generators, D1 and D2, and safeguards electrical distribution system provide for emergency power in the event af loss of offsite puwer in order to i bring both ur.its to a safe (hot) shutdown condition. This is achieved using automatic contrcl logic and operator. actions. Each diesel generator, as a backup to the preferred offsite A-C power supply, is capable of sequentially storting and supplying the ,wer requir:ements of one complete set of engineered safety featuret, for one unit while providing power to allow the second unit to be placed in a safe shutdown condition. See Figure 2-1 for the existing one-line electrical diagram of the Emergency AC Power System. Diesel generators D1 and D2 consist of two Fairbanks Horse units each-rated at 27S0kW continuous (8750 hr. basis) , 0.8 power factor, 900 rpm., 4160-volt, 3-phase, 60 Hertz. The 2000 hour rating of each diesel generator is 3000 kilowatts and the 30 minute rating is 3250 kilowatts maximum. This figure is based on cooling water at a maximum temperature of 95'F and ambient air at a temperature of 90*F. The limitations imposed by the- generator and the heat removal equipment limits the overall 30 minute rating of the system to 3250 kilowatts. The worse case plant loads placed on an emergency diesel generator- during a design basis accident (requiring safety injection on one unit and hot shutdcwn on the other in conjunction with loss of power . to both Units plus a fallare of one- EDG) result in approximately 2825kW for the automatically and manually connected loads within the first hour and . then decreasing to less than 2000kW fcr the duration of the accident, See - Table 2-A' for the presently evaluated D1 and D2 loads for the above scenario. Each diesel engine is - automatically started by compressed . . ai r atored at a pressure of approximately 2 50. ' psi. iwo parallel solenoid admission velves deliver air simultaneously to a timed pilot air-distributor valvo and an individual air-start valve located in each of the twelve cylinders. Starting air is thus admitted directly into the cylinders for fast, reliable cranking and starting. Adequate cranking effort is obtained with only six air valves. The additional six valves give increased starting reliability. Each diesel generator has its own independent air starting system including motor-driven hir compressors, (powered from a 480-volt safeguards bus) and receiving tanks, each of sufficient capcity to e crank the engine for 20 seconds. To enhance rapid start-up, each diesel unit is equipped with two tenperature-controlled immersion heaters which furnish heat to the engine cooling water and the engine Ir.bricating oil when the engine 13 _ 1
)
1 Rev. 1 ) l is shutdown. Two motor-driven circulating pumps, for cooling water and lube oil, operate continuously when the engine is shutdown. Autcmatic starting of each diesel generator (D1 and D2) is initiated by an under-voltage or sustained degraded voltage relay scheme (either of 2 sets of 1 plus 1-out-of-2) on the 4160-volt bus to which the diesel generater is connected. Automatic starting is also initiated by a safety Injection (SI) signal. Suf ficient fuel is stored in the day tank for each diesel generator for a minimum of one hour operdtion at full load. Fuel from interconnected storage tanks is transferred to the day tanks by electric pumps for operation'of each diesel. j i 2.2 UPGRADED SAFEGUARDS AUXILIARY POWER SYSTEM The upgraded safeguards auxiliary power system includes the construction and Anstallation of two new diosel generators, D5 and D6, with all support systems. ~The suppnrt systems include fuel oil, rtarting air, ventilation, cooling water, diesel oil storage tanks located in a vault, and transfer pumps located it. the DS/D6 building, 4160V and 480V switcngear buses, 480V Motor control Centers (Mcc), 125V DC distribution panels,- load sequencers, ' lighting distribution panels, transf orr:ers , cabling and numerous components necessary for modifying the existing equipment. See Figure 2-2 for 'an upgraded one-line electrical diagram of the emergency AC power system. 2.2.1 DS and-D6 Diesel Gent 3ratoIS and Suncort Systems ! The new diesel generators will consist of two tandem-drive units manufactured by Societe Alsacienne de Constructions Hecanique7'de Mulhouse' (SACM), located in Mulhouse, France. Each diese1 ' generator consists of one generator d. riven by two diesel engines, with one mounted on each cad of the generator in a back-to-back arrang e nunt. - Each diesel-generator. ls rated at 5400 kW continuous (C750 hr. basis), 0.8 power factor, 1200 rpm, 4160-volt, 3-phase, 60' Hertz. + The new diesel generators - are radiator cooled and will- be-independent of the existing plant cooling water system. The new D5/D6 Building houses two SACM diesel generators (D5/D6), with associated control panels,. auxiliary equipment, electrical distribution equipment, fuel oil day tanks and lube oil tanks, and
- l. the dieael engine radiators.
The Fuel Oil Storage and Transfer System for each diesel generator l consists of two storage tanks mounted in a concrete vault located L /ad-)acent to the D5/D6 Building plus two transfer pumps' located in l' ~the diesel room pit area of the DS/D6 Building. A shared, above grade,: receiving tank is also provided. Diesel engine fuel oil L l- transported to the site will be off-loaded initially to the receiving tank. The fuel oil in the receiving tank will be tested 14
Rev. 1 to ensure compliance with the diesel engine fuel oil After compliance is verified, the fuel oil in the I specifications. receiving tank can be transterred to any diesel engine fuel oil storage tanks. 2.2.2 Safectuards El,getrical Svgl.p2 As part of the SBO/ESU Progran, existing ' diesel generator D1, presently supplying power to the Train A Safeguards system of both Units, vill be reassigned to the Unit 1 Train A Safeguards emergency power system. Similarly, existing diesel generator D2 will be reassigned to supply power to the Unit 1 Train B Safeguard einergency power system. Thus, the two existing diesel generators will be aligned as the emergency AC power supplies for Unit 1 and certain common or shared systems. The two new diesel generators will be aligned as the emergency AC power supplies f or Unit 2 and certain common or shared cystems. DS will supply power to Unit 2 Train A Safeguards power system and D6 will supply the Unit 2 Train B Safeguards power system. The four existing Unit 1 and Unit 2 load sequencers will be i replaced with four new commercial grade solid-state prcgrammable logic controller-based sequencers, which have been dedicated for Safety Related service and sof tware qualified as discussed in NSP's
" Reply to Questions on Design Report ior the Station Blackout Electrical Safeguards Upgrade Project (TAC numburs 685B8/68589)",
dated July 10, 1991. Ir' addition to installing DS and DG diesel generators, tha safeguards electrical distribution system will be upgraded.
-New Unit 2 4160V safeguards switchgear will be located in the new Seismic Category I DS/D6 Building. This will be accomplished using l two new - 4160" switchgear lineups. The present Unit 2 4160V safeguard loads will be reconnected to the new Unit 2 safeguards switchgear.
A new 4160V safeguards switchgear lineup (Bus 27) will be installed in the DS/D6 Building - and the switchgear will be selectively energized from Unit 2 416f'i switchgear train A or D. This lineup will be the safeguards power source for 121 Cooling Water Pump. Portions of the present Unit 2 4160V safeguards switchgear will be added to Unit 1 safeguards switchgear. The cooling tower source transformers and the R source transformers will be connected to each of'the four safeguards 4160V switchgear line-ups,. This configuration will provide 2 independent (see Section 3.2) offsite sources to each 4160V safeguards bus and will minimize the use of 4160V bus ties between units. 15 l
- Rev. 1
.- Four new' Unit 2L 480V safeguara buses (two per train) will be installed in the new DS/D6 Building to replace the two existing buses. The present Unit 2 safeguards loads (MCCs) plus additional DS, D6-and building safeguards loads will be divided between the buses of a given train to improve th? voltage regulation on the 480V safeguards buses.
The two exit, ting Unit 1400V safeguards buses will be replaced with four new safeguard buses. One of the buses will occupy vacated Unit 2 480V switchgear room. The second bus will occupy an existing Unit 1 480V switchgear room. The two additional buses will be located in the present Unit 2 4160V switchgear rooms. The resulting Unit 1 configuration, two buses per train, will be similar to Unit 2. .The present Unit 1 safeguard MCC loads will also be divided between the buses. . Automatic solid-state programmable logic controller-based voltage regulators will be added to each of the Unit 1 and Unit 2 480V safeguards buses (8 total) to improve voltage regulation. The ~ voltage regulators and noftware have been qualified for this safety related application as discussed in NSP's " Supplemental Information on Programmable Logic Controllers for the Station Blackout / Electrical Safeguards Upgrade Project (TAC numbers 68588 and 68589," dated October 21, 1991. Alternate power sources from the same train of the. opposite unit, to be used primarily during maintenance outages on 4160V source i buses will-be added to the 480V safeguards buses. Each alternate source' line-up will consist of an incoming line compartment, a 4160'-480V transformer section and a trancition section for connection to the 480V switchgear by bus duct or cable. One alternate source line-up.per train will be provided to be used by either or both 480V safeguards buses. Loading on the alternate source transforme.r will be administratively controlled within ratings. l l [. l' i l-L I l 16
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Rdy. 1 Table 2-A PRAIRIE ISLAND USAR TAOLE 8,4-1 (Page 1 of 2)- 2 Olesel Generator Londina DBA in Flest Unit andaHot Shutdown Function for Second Unil of Timel (Load a r, Motor Equivalent 0-5 5-30 1/2-1 After
~
Automatically Loaded Unit Minutes Ho .J r I Hour or KW Minutes KW KW KW KW Screty F e.a tur e s Load' Rating e 663 663 663 663 1 800 HP B 8 S. 1. Pump 10 HP B B B 4 . Roof Exhaust Fan 1 i 5 rip 4 L h L LO Scresn House Vent --e LO bO 40 40
~ Sct,tery Charger arid 1
' Inst, Power 38 38 3G I h6 HP 30 38 Diesel Gen, Support -
f7 17
' Auni l i ar l e s 20 lip 17 17 7
Raccior Dome 162 119' 119 ' Note 2 Note 2 Not.e 2
' ' tioto - Opera t ed Va lve s 162 144 HP 181 181
--- 181 tal 181
- ' Miscellaneous Loads 162- 166 16o 166 200 HP 166 166 R.H R. Pump i 207 207 ---
250 HP _207 207 Containment Spia a r 1
' Pump 207 207 20' 4
250 HP 207 207 C.C. Pump 1 207 207 207 250 HP 20/ 207
;.C.C, Pump '2
'249 249 249
-300 HP 2L9 249 Aun Foodwat er Pump Note 1 L1 41 41 41 1 50 HP 41 fan Coli Unlts 83 03 (2 Vens)~ 162 100 HP 83 83 D3 124 Air Cocpressor 121 124 124 126 2 150 HP 12h
- Fcn Lol1 Lin i tx 192 192 192 J ( 2i F ans ) 2 192 KW 192 192-Croup "A" Pressuel2er
-H3ater 155 159 ISS 187 HP 155 155 Cce t,r o l Room Fans and '162
. Water Chilier 192 192 192
.192KW #92 192 Group "A" Pressurizer Ileater e
R 19
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Rcv. 1
, Table 2-A PRAIRIE ;SLAND tJSAR TABLE B,f.-1 (Page 2 of 2) plesel Genernter Londing DBA In FirsI Unit and Het Shutdoe for Second Unit (load as a Function of time) + ORDER Automatically Leaded UNIT Motor Eculvalent 0-5 .5-33 i /?.- 1 After or KW Minutes Ninutes Hour i Hour Safetr Features Lood KW KW kW KW Rating MANUAL & MISC,.AFTER S MIN, r,
_ Charging Purnp . 2 100 HP 83 --- 83 83 83 i Turbine-Of1: Pump (Note 3) 2 50 HP- L2 --- 14 2 42 f. 2
. Boric Acid Trnnsfer 2 15 HP 12 ---
12 12 12
~ Pump Boric Acid Henters and- 2 23 KW 23 ---
23 23 23 Hant- Trac ing - Misc, Loads 162 . 100 HP 83 --- 83 83 83 .; TOTAL LOAUS 2701 2025 2075 1955 NOTES: : 1., -Unit 1 Aux, F,W, Pump on Diesel Generator No. 2, 1 Unlt 2 Aux, F,W . Pump on DIesei Generator No, 1, 2 , -- M , __ O , Values are approxImately.30 See, Load,
.3 Point where turbine of1 pump starts depends on coast down time of
. turbine, probably,after 3-5 minuten, i
[ .. E % i. l-l 20 l l' .
Rev 1 3.0 DIESEL GENERATOR AllD_Al%1LI ARY SYSTEMS- DESIGN AND TNSTALLATlQ1{ . Two identical diesel generator sets, D5 and D6, will be installed on a concrete foundation, complete with all accessory components, > connecting piping, wiring, and instrument tubing. DS and D6 will be located in separate rooms - of a reinforced concrete Seismic Category I structure. Each - diesel generator system will be monitored to alert personnel of abnormal conditions. Annunciator alarm systems will be located in the main control room and on local control panels in the DS/D6 Building. The - D5 and D6 units will be composed of tandem-engine diesel generators manufactured by Societe Alsacienne de Constructions Mecaniques de Mulhouse (SACM). The diesel engines are Model No. UD45-V16-S-D-$,16 cylinder, and have a closed cooling system using radiators. The generator manufacturer, subcontractor to SACM, will be Jeumont-Schneider, also of France. . The equipment will be specified, designed and manufactured to operate over a design life of 40 years with specified servicing. The diesel engine will be of vertical V-frame, stationary type, turbocharged, multi-cy31nder, and complies with the manuf acturer's qualified design for emergency standby operation required for nuclear power plant service. The operating rated speed will be 1,200 rpm. The'two-engines in each set will be directly coupled to a dual bearing generator, one on each end in a back-to-back arrangement. The generator and exciter will have a continuous rating of 5,400 kw gross, and a voltage rating of 4.16 kV at a. frequency of 60 Hz. Each diesel generator will be capable of attaining rated frequency and voltage within 10 seconds after receipt of the starting signal. During the loading sequence steps, frequency and voltage will be maintained above minimum values of 95 percent and 75 percent, respectively. During recovery from transients caused by step load increases, or resulting from the disconnection of its largest single load, the speed of the diesel- generator set will not exceed nominal speed plus 75 percent of difference between nominal-speed and tho'overspeed trip setpoint. Each generator will be designed for isolated and parallel operation. The units will be free from harmful critical speeds within the normal operating range,'up to
. and including automatic trip shutdown speed-at 115 percent of rated-operating speed.
The two engines are identical except for the camshaft drive trains which provide- clockwise rotation for one encrine and counter clockwise ~ for the other as required by the back-to-back arrange. ment. Each diesel delivers equal power to the generator as a result of the governor control. Acceleration, speed, and load will be controlled by means of the governors which meter the flow of. fuel into the combustion chambers. 1 i l L 21
Rev. 1
'i ."1 SEISMIC UESIGN CLASSIFICATION The seismic design classifications for the diesel generator and
-auxiliary systems are as follows:
The D5/D6 Building Seismic Response Spectra will be used for systems and components and qualification of Seismic design classified'as Seismic Cacegory I. 3.1.1 piesel Encine Auxiliary Systemrq hll components of the diesel engine auxiliary systems that are required to operate during a design basis accident or to mitigate consequences due to an accidet.t will be designated as Seismic Category I and are designedAll and constructed other componentsto withstand which are safe not shutdown earthquake (SSE). required for safe shutdown will be seismic II over I supported to preclude damage to safety related systems or components.
.3.1.2 lliesel__Qenerator Room Ventilation Systems All components of the diesel generator room ventilation systems will be seismic Category I, except the normal mode ventilation fan Components and ductwork which will be mounted Seismic II over I.
required for alarming, indication and monitoring will be designed for seismic mounting only (seismic passive). 3.l.3 Electrical Power Distribution. Instrumentation and Contrplg The electrical _ power distribution system will1.29, be designed and and Seismic as Seismic Category I per RG installed qualification -will be per IEEE 344 and Regulatory Guide 1.100. This safety-related system is required to be operable both during and after the occurrence of a design basis event. Instruments, controls and associated sensing linesand required engineforroom the , operation of the dieselbe engine auxiliaries ventilation system will seismic Category I. Those that-are required for alarming indication and monitoring will be designed for seismic mounting _only (Seismic II over I) when necessary to preclude damage to safety related systems or components.
-3.1.4 Luel Oil Storace and Transfer System The fuel 013~ storage tanks, concrete structures, transfer pumps, The piping and_ electrical equipment will be seismic Category I. associated piping, receiving tank, recirculating pump, components will be non-safety related, but will be designedThe to l
L withstand SSE Joads without failure (Seismic II over I). storage tank level instrumentation for indication and alarm will not be safety related and will be seismically mounted (Seismic II onlyI).to over preclude damage to safety related equipment The control switches to initiate operation of the transfer pumps l ! (also day tank level switches) will be Seismic Category I. 22 l' l
Rov. 1 All electrical equipment and raceways will be designed and ~ installed as Seismic Category I. All sensing lines for tank level and transfer pump instrumentation will be seismically supported and must maintain integrity of the pressurc boundary (Seismic Category I). 3.2 SAFETY DESIGN CLASSIFICATION The safety design classifications for the diesel generator and auxiliary systems are as follows: 3.2.1 Diese1 Enaine Auxillary Svstems All interconnecting piping between equipment that is necessary for the opcration of the diesel generator will be safety related. All other piping and its components that are not necessary for diesel generator operability, such as drain, vent, and fill lines vill be non-safety related. The design classification for piping and equipment in each diesel engine auxiliary system is as follows:
- 1. Cooling Water System Enfety Classification (both HT: High Temperature Cooling Circuit and LTi Low Temperature Cooling Circuits)
- a.
- Radiator Safety Related
- b.
- Expansion Tank Safety Related
- c. Reservoir / Storage Non-Safety Related Tank and Piping
- d. AC Motor Operated Non-Safety Related Transfer Ptap
- e. Interconnecting Safety Related Piping (Including Equipment Vent Lincs)
- f. Exp. Tank Fill, Non-Safety Related overflow, Vent, beyond first isolation and Drain Lines valve.
- 2. Fuel Oil System
- a. Day _ Tank Safety Related
- b. Dirty 011 Tank Non-Safety Related
- c. Interconnecting Safety Related Piping 23 j
Rov. 1
- 3. Starting Air System
- a.
- Compressor Unit Non-Safety Related
- b.
- Air Dryer Non-Safety Related
- c.
- Air Receiver Safety Related d.. Interconnecting Piping
- 1) Receiver to Safety Related Engine
*2) Compressor to Non-Safety Related Dryer
- 3) Dryer to Non-Safety Related Receiver
- e. Vent & Drain Lines Non-Safety Related beyond first isolation valve for air receiver.
- 4. Lube Oil System
- a. Lube Oil Storage Tank Non-Safety Related
- b.
- Lube Oil Cooler Safety Related
- c. AC Motor Driven Non-Safety Related Transfer Pump
- d. Tank Vent & Non-Safety Related Drain Lines
- a. Engine / Aux. Desk Safety Related Interconnecting Piping
- f. Lube Oil Tank Non-Safety Related Fill Line
- 5. Combustion Air and Exhaust System
- a.
- Intake Air Filter Safety Related
- b.
- Exhaust Silencer Safety Related
- c. Incerconnecting Safety Related PipiTg
- Supplied under Diesel _ Generator Specification M-870.
3.2.2 plesel Generator Room Ventilation System The diesel generator room normal mode ventilation fans and associated ductwork and controls, will be non-safety related. This equipment is provided for human comfort only. Components of the diesel generator room ventilation system that support operation of the diesel generator set will be safety related and support operation of the diesel generator set. Those components required for alarming indication and monitoring will be non-safety related. 24
Rev. 1 '3'.2.3 X}ectrical Power Distribution, instrumentation and Controls The electrical power distribution and controls system neconsary for operation of safety related equipment is classified as safety related (Class 1E). Diesel generator power is required in the event of a loss of offsite power, and is required to be available when a safety injection (SI) actuation signal is initiated. Instruments, controls, and associated sensing lines having the function to ensure operation of the diesel generator units, the engine room ventilation, or to maintain integrity of Class 1E circuits, will be designed safety related. Those that are required for_ alarming, indication and monitoring will be non-safety related. 3.2.4- fuel Oil Storace and Transfer System The electrical power supply equipment, including pump controls, instrumentation and cable / raceway will be safety related Class 1E for the equipment associated with the four storage tanks and four transfer pumps. Controls and instrumentation associated with level and leak detection of fuel oil for the purpose of indication, monitoring and alarm will be designated as non-safety related. Power supply equipment, controls, instrumentation and circuits / raceway associated with the receiving tank. and recirculating pump will be designated as non-safety related. 25
4 Rcv. 1 The fuel oil storage tanks and associated transfer pumps, piping, including interconnecting lines, concrete structures and supports, will be safety related. The fuel oil receiving tank, recirculating pump and associated piping are not part of the safety related storage tank pressure boundary, therefore, will be designated as non-safety related. The design classification for piping and equipment for the fuel oil storage system are summarized as follows: Safety Cj.gssificatdgn
- 1. Tanks
- a. Emergency Storage Tanks Safety Related
- b. Receiving Tank Non-Safety Related
- 2. Pumps
- a. Transfer Pumps Safety Related
- b. Recirculating Pump Non-Safety Related
- 3. Piping and Components
- a. Fuel Oil Transfer Piping Safety Related System including storage tank interconnecting lines (except vent and drain lines)
Receiving Tank Non-Safety Related b. Recirculating Piping System
- c. Storage Tank Vent Lines Safety Related
- d. Scorage ' lank Drain Lines Non-Safety Related After First Isolation Valve
- e. Fuel Oil System Emergency Safety Related Fill Connections
- 4. Instrumentation r
- a. Fuel Oil Day Tank Level Safety Related Switches and Standpipe All Other Instrumentation Non-Safety Related b.
- c. Instrumentation Lines from Safety Related Safety Related Process Linep to Root Valve 1
26
Rov. 1 . 3.3 SYSTEH DESIGN AND INSTALLATION . 3.3.1 Diesel Encine Coolina System 3.3.1.1 Diesel Engine Cooling System Design Each engine will be provided with two independent closed loop cooling systems consisting of high temperature (HT) circuit and low temperature (LT) circuit. The HT circuit cools the engine jacket, cylinder block, and the turbocharger. The LT circuit cools the aftercooler and the lube oil heat exchanger. Both HT and LT circuits vill be provided with an engine driven circulating pump, expansion tank, water-to-air heat exchanger (radiator), and a three-way thermostatic valve. In addition, the HT circuit will be provided with a preheating circuit to reduce thermal stress and wear during f ast starts of the diesel engine. The preheating circuit will consist of an AC motor-driven standby circulating pump, an electric water heater, and a lube oil standby heat exchanger. The heater and pump are electrically interlocked so that the heater will be energized only when the pump is running. The preheating circuit equipment are located in the engine auxiliaries desk (skid) located adjacent to each engine. In the standby mode when the engine is not running, the standby motor-driven circulating pump will be running to circulats warm water through the engine jacket. Jacket water temperature is maintained at a " keep warm" temperature by controlling power to tne electric heater with a temperature switch. The warm temperature is transferred to the lube oil system through the preheating lube oil beat exchanger of the HT circuit. During normal engine operation, the coolant temperature for either HT or LT circuit will be maintained at design temperature by the 3-way thermostatic valve - action to either direct flow to or bypass the radiator. The purpose of the HT or LT cooling system expansion tanks located on the third floor of the D5/D6 Building, will be to maintain the required pump NPSH on the system circulating pump. The cooling system flow to the pump will be pressurized thus protecting the pumps from cavitation. The cooling expansion tanks will be adequately sized to provide for thermal expansion of the cooling water, and for minor system leaks at the pump shaft seals, valve stemc, and other associated components. Each 50-gallon expansion tank per diesel engine will provide an air vent for the venting of the cooling water system to remove air pockets which otherwise will be entrained in the system creating poor heat transfer conditions in the radiator. The closed cycle cooling system will utilize high quality makeup water f om the existing plant demineralized water system. This is necessary to prevent formation of scale and to maintain a uniform 27
. . . - . - . _ - - - . - .- -.- ~- . - . . - . - - - . -
V
.'* - RGv. 1 heat transfer rate in the engine jackets. The. cooling water will be _ treated with ethylene glycol mixed to a ratio of 50-50% by weight and a rust inhibiter.
3.3.1.2- Diesel Engine Cooling System Installation
-The' installation requirer nt for the-engine high temperature (HT) and low temperature (LT)' cooling circuits will include providing interconnecting piping between the engine outlet nozzle and the radiator, and from the radiator discharge to the engine driven pump inlet-connection. A 3-way thermostatic valve will be installed in the' piping between the engine and the radiator and its bypass connection will be connected to the piping between the radiator and the pump-inlet connection. The function of this velve will be to bypass the radiator to enhance quick engine heatup; therefore, the
-valve will be located as close to the engine as possible.
Interconnecting-. piping will be provided to install' the HT preheating-_ circuit in parallel with the engine driven pump. The standby circulating pump of the preheater circuit will be in operation when the engine pump is not running. AllLvent connections from the engine cooling water piping, the-electric water heater, and the radiator will be routed to the expansion tank. A reservoir / storage tank will_be provided for each diesel generator
-set to collect overflow-from the expansion . tank and to provide. ,'
refilling _ water to:the cooling-water system. A fill line will be pro.vided so that treated water can be added to the . storage tank for replacing any system _ losses. A manual AC. electric pump will be provided to assist in transferring water from the reservoir / storage The minimum. capacity of- the
~
tank. to the ' expansion tank. reservoir / storage tank will be sufficient to allow the batch mixing '
- of one 55-gallon drum of glycol and an equivalent volume of water.
Figures.3-1.through 3-4 depict the HT & LT cooling Water Systems for D5 and D6 diesel generators.-
- 3.3.2 Diesel Fuel Oil System
-3.3.2'. 1 Diesel Fuel 011' System Design Each engine fuel oil system will consist of a 100% capacity engine-driven booster pump, a 100% capacity backup booster AC motor-driven pump,.a duplex-type:rilter and'a common. day tank. Any excess fuel oil from both. pumps is returned to the day tank by the excess flow valve located upstream of the . duplex filter. Each; ofithe 16
~
l. cylinders ' will be fed from a dedicated injection pump- and nozzle - via the double wall injection piping. Any-fuel oil leakage from the inner wall piping will be contained within the outer wall where it _ drains into the accidental leakage manifold _ and finally drain to 28
- i R6v. 1
/ .
the leakage tank. The leakage tank is monitored by a high level alarm that- indicates excessive leakages. Discharge from the leakage tank flows by gravity to a common dirty vil tank. , The usable volume of each day tank, accounting for the actual 2vations of overflow connections and suction piping is 600 gallons. Based upon full load fuel oil consumption rates for both engines, plus a margin of 10%, each day tank would be of a capacity to allow the. running of both engines for 90 minutes without makeup. Each day tank will be located inside the DS/D6 building at an elevation that will encure adequate net positive suction head to the booster pumps. 3.3.2.2 Diesel Fuel Oil System Installation The' installation requirements for the fuel oil system will include providing interconnecting piping for the following:
- a. From the day tank to the engine oil pump inlet connection,
- b. From the engine oil pump outlet to the auxiliaries desk.
- c. From the auxiliaries desk discharge connection to the engine oil feed inlet connection.
- d. From the day tank to the backup booster pump inlet located in the auxiliaries desk.
Miscellaneous engine connections such as the engine oil overflow line and the auxiliaries desk safety valve connections will be routed back to'the-day tank. Each day tank will oc equipped with a_ drain and overflow connections'that are. tied together and routed back to the storage tanks._ A missile-protected vent line will be provided and vented to atmosphere. A flame arrestor will-be installed in the vent line, one dirty _ oil tank will be provided for each diesel generator set for storing-leakage from the fuel oil system. A drain line with manual operated valve will be provided to empty the tank periodically i'c o a portable containar. The tank will be equippe'd with overflow ine that is roeed to the DS/D6 building sump. A ~ gauge site glase for level indication will be provided. Level switches will be provided for each day tank to automatically refill the tank by actuating the oil transfer puItp on lo*. tank
-level.
,~3.3.3 Diesel Air Starti..a System i 3.3.3.1 Diesel Air Startir,g System Design L The air starting system for the tandem SACM diesel generator set l- - consists of four independent subsystems, each ine'.uding its own air l dryer, compressor, and air receiver. The air rn.eivers were sized l 29
l .
. +
Rov. 1 based upon test data for SACM enginen, corrected for cystem inertia specific to the Prairie Island diesels. Each of the four air receivers is sized to provide ten starts of the diesel engine without recharging, and any two of the tour reculvers wil,i ottet the genset within ten accends. Therefore, nizing of the starting air system per the manuf acturer's recommendations complies with the guidance of SRP 9.5.6 (capacity for five crankir.g cycles). . Each starting air receiver will ba provided with a pressure switch which will alarm a low air pressure condition at Lhe DG control room annunciator panel. This s.gnal will also annuenciate the ccmmon troubic alarm in tne mair control room. Thn air receivers will also be monitcred ny pressure indicators located on the DG benchboard in the DG control room. This arrangement :omplies with SRP 9.5.6, Section II, Item 4h. The air dryer will be of the heatless type containing two towers that are connected 'n parallel. . Both towers are filled with molecular sieve desiccent product whofe one tower is alternately in the drying phase while the other tower is regenerating. The dryer will provide dried starting air at a dew point of -4*F when the system is pressurized, Each starting air skid . 11 uo provided with equipment to prevent fouling of M i air start valve or filter as follows:
- 1. Moisture , desiccant type air dryer will be provided upstream of the a i'. eceiver to reduce moisture to acceptable levels. In addition, u wat er separator is provided upstrean of the air dryer to ensure E.fficient dryer operation.
- 2. Oil - luoricating n.t1 carry over f rom the air compressor will be prevented by an oil separator located at the compressor discharge.
- 3. Rust - an air filter will be providea upstream of eacn air dryer to clean up contaminants in the air atream such as rust. In addition, . duct filter located at the air skid discharge will be capable of eliminating fine rust particles. The dryer for rust discussed above will also reduce the potential f ore.ation.
Provisions will be made to blow down any accumulated moisture in the water Foparator provided with the compressor unit, and the oil and water separators with the air dryer. The air receiver will be provided with drain connections to allow periodic manual draining of moisture content during startup and normal opere ion. A relief valve will be provided to protect the air receiver from overpressure. 3.3.3.2 Diesel Air Starting System Installation The installation requirements for tne air starting system will include providing interconnecting piping for the following: 30 I 1 j
l Rov. 1 -
- a. From each air receiver outlet connection to the air filter and starting air solenoid located inside the auxiliarios desk. *
- b. From the auxiliaries denk outlet connoction to the engine air distributor inlet connection.
I
- c. From air supply line in the aux 311ary dost to engine overspeed i protection system. l 1
d.-From the dryer to the air receiver. Figures 3-8 and 3-9 depict the starting air systems for the D5 and ~ D6 diesel generators, respectively. ( 3.3.4 Dig.p3.L.Lu be . Qil_, System
?
L 3. S . 4.1 ' Diesel Lube oil System Des 3gn The engine lube oil syst.em will consist of two cross-tied loops, pressurized by two 50% capacity engine driven pumps. The pumps , discharge supply oil from the crankcase sump :hrough the lube oil cooler, a duplex-type filter for cleaning, and distribute lube oil to the engine block to lubricate noving parts and to provido piston cooling. : A 3-way thermostatic valve regulates flow through the oil cooler based on outlet temperature. Any excess oil from the discharge , valve and cylinder block internal bearings are returned to the oil . sump. , '~ The lube oil system will be provided with a pro-lube system to , maintain constant flow of lubricating oil to critical areas during standby mode to mininige wear during engine starts.. To enhanco quick engine starts, the pre-lube system maintains lube oil in the "Psep warm" temperature through the lube oil standby heat exchanger, heated by tho'keepwarm portion of the HT cooling water - system. The pre-lube - system design will include provision for .' draining lube oil from the engine' crankcase. An AC motor-driven pump will be used normally frer pro-lube system' operation with a 9c , motor-driven pump for backup operation. Both pumps'and the standby heat exchanger will be located in the auxiliaries desk. The- diesel engine lubricatinc oil system (except. for interconnecting piping between_ the engine and auxiliaries desk) was designed by the. diesel engine manuf acturer, SACM. Design values ; for operating pressure, temperature differentials, flow rate and heat removal rates determi:ad by SACM were utilized in the design for the system. Interconnecting piping between the engine and auxiliarios desk was designed to. ensure that the pressure losses within' the . piping met SACM's allowable pressure loss requirements. ,
?
31 t
. S Rev. 1 A sufficient quantity of lube oil to permit 7 days of continuous operation at rated load will be maintained on site for each diesel generator. Tho lube oil wil.1 be stored in a lubs oil storago tank.
Tho lube oil storage tank provided for each diesel generator will be located at an elevation to permit filling of each engine crankcase by racans of gravity flow, which will be controlled by a manually-operated fill valvo. 3.3.4.2 Diesel Lubu Oil System Installation Installation requirements for the lube oil system will include providing interconnecting piping for the following equipment:
- a. From the lube oil storage tank to the manually operated fill valve.
- b. From the engine prelubrication outlet to the auxiliaries desk.
- c. From the auxiliaries desk outlet to engine prelubrication inlet connection.
Miscellaneous piping will be required by the diesel engine. This includes providing crankcase relief valvo discharge piping to be routed to the building sump. An AC motor driven transfer pmtp will be provided at the ground floor elevation to refill the lube oil tanks from portable lube oil containers. The control of this motor will be provided by local utart and stop push buttons and local motor starter. The lube oil stotage tanks will be located inside the 05/D6 Buildirig. Each will be equipped with a vent line and a flame i arrestor. A drain line with e manual drain valve wjll be provided. I Each tank will be furnished with an overflow line so that any overflow will be accumuli.ced in the dike enclosure provided for each lube oil tank. Instrument interconnecting lines for the lube oil system will be routed from the engines to the auxiliaries desk. These include instruments, such as for oil pressura and oil tamperature indicators and switches. Figures 3-10 and 3-11 depict the lube oil systems for DS and D6, respectively. 3.3.5 Rir.qg.LQombup1 ion Air 31D5LIEllags,1; Svste,n 3.3.5.1 Diesal Combustion Air and Exhaust System Design Each diesel engine will have independent combustion air intake and exhaust systems. The combustion e.ir syt. tem will include an air 1 intake filter that will function in accordance with the engine 32 i
- - __-__~ - _ . _
e , Rov. 1 manuf acture:c 's recommendations. The air intake s"atem will be designed and located no less than 20 foot above grade such that fresh outside air will be provided and dilution wJth exhaust products will not occur. The air intake system will be designed to pruvent entrained wat(r-from entering the engine air intake. The combustion air inlet piping system har, been reviewed by the engine manufacturer to ansure the engine ability to start and run during site design basis tornado depressurization conditions.
'Ihe engine exhaust system will include a mant'f acturer's reconunended industrial-type exhaurt silencer with multi-compartment construction-to limit noise level.
13.3.5.2 Diesel Combustion Air and Exhaust System Installation Installation requirements for the combustion air and exhaust system of each engine will include the following interconnecting piping:
- a. From single air intdke filter discharge connection to two turbocharger inlet connections. ;
- b. From both turbocharger outlet connections to a single connection provided by the exhaust silencer. :
- c. From exhaust silence:- discharge end to atmospheric discharge.
i The combustion air and exhaust piping will be sized so that the combined total maximum. ptocsure drop. will be within the manufacturer's recommendation. Each of the engine's dual air intake' and exhaust legs will be closely balanced to minimize differential back pressures from occurring. Similarly, the total pressure loss consisting of combustion air and exhaust piping for both engines will be closely matched so that both engines will , share equal loads. The exhaust piping will be protected from posuible clogging due to rain, snow, or ice, during standby or operation of thu systems. An angled shield structure equipped with a bird screen protects the exhaust from plugging and from damage by external missiles.
.An expansion joint will be provided in the intake air and exhaust .
i piping to accommodate . piping thermal expansion and to minimize transfer of vibration to the piping. system. Thermal insulation will be provided for the exhaust piping including silencer and expansion joints. , Figures 3-12 & 3-13 depicts the combustion air and exhaust for D5 ; and.D6, respectively. 33
, .- -, ~ . . . . - .-,--,.-:_.--.-..- -. - . - . - . - . . . . - - - . . . - -
i
<a Rev. 1 l 3 .3. 6 Eiggs),,,Sangrator Room Ventilation Systems 3.3.6.1 Diesel G7norator Room Ventilation Supply System Design
- a. Diesul Generator Room Ventilation Supply Each of the two diesel generator rooms will have an independent ventilation system which will fonction to limit the maximum ambient temperature to 120'F in conformance with ocptipment ;
ratings, when the Diesel Generators Are operating. The ventilation system will also supply the minimum required volumetric flow of air necessary to directly cool the generator bearings and otner features specizied by the Manufacturer. , The diesel generator roc,m cooling fan will force outside air o- into the' room. Provisions will be made to mcdulate the outside air'vith return air. This modulation limits indoor ambient air temperatura to 50*F minimum, while the engine ir running. . l l Each diesel generator room cooling f an will auto stat t when the corresponding diesel generator starts,
- b. Diesel Generator Rcom Normal Mode Ventilation Each of the two diesel generator rooms will have an independent ventilation exhaust system which will function to provide a minimum continuous ventilation requirement of 1 cfm per square foot of the diesel generator room floor area when diesel generator set is not operhting.
- c. Diesel Generator Room. Ventilation Instrumentation and Controls ;
The engine room ventilation system will be provided with instruments and controls to enable operation of the systems to maintain room temperature within design limits. The controls are required to function during and af ter . diesel generator ; operation. 3.3.6.2 Detailed. Design I All components of the diesel generator room ventilation aystems be capable of performing their function in a 120'F will environment. Relative humidity is in the range of 20's to 90%. cnd air conditioning (HVAC) systems The hesting, ventilation, capacinea are based on an outdoor ambient temperature range of . I 96*F and.-20*V. This is the 99% occurrence range recommended by Refrigerating, and Air-the American Society of Heating, ' Conditioning Engineers, Inc. (ASHRAE). 34
~
Rev. 1 Five different sources of historical weacher data were reviewed in . t.he selection of the outdoor design temperature. The two principle sourced wera ASHRAE and the National Oceanic and Atmospheric Agency (HOAA). The justification in selecting thes Summer tempere';ure given~ above was based on the following: The outdoor temperature recommendation with 99% occurrence was given as 92 F. This informatic,n was also referenced from the ASHRAE " Weather Data and Design conditions," Table 1, Page 24.10. 1985 Edition for the city of Minneapolis. Ample meteorological evidence indicates that the temperature at the it level may vary on the order of 2*F to 4*F in any 15 year pcriod from the previous 15 year periad, and may vary even more.in any single year from the previous year, since there were stringent design conditions, the 4 F was added to the referenced temperature. Althcugh extremes may result from 100*F and above for a short time, the system will tolerate this increase without adverse impact. Although the record mrximum on-site temperaturo was 101.6'F for one hour in the hottest summer recorded of 1988, recordings exceeding 96 F (transients of 97"F or 101.6*F) are not appropriate to be used as summer design temperatures due to their short duration. The HVAC steady state heat load calculations do not take credit for passive heat sinks (concrete walls and floors) and thermal lag. Therefore, the HVAC design conditions are (,onservative, and'brief temperature excursions up to 100*F or below -20*F will not adversely affect olectrical equipment operability. Ventilation air flow rates for the diesel generator rooms will be l based on heat losses including Jights, diesel engine, generator, exhaust- piping within the room, air conpressors and cooling fan motors. The diesel generator room cooling fan will be automatically started by a run signal from its corresponding diesel generator. When the diesel generator stops, the supply fan will continue to rt il the room temperature falls below 100'F as sensed by a tempe . cure twitch in the room. The control switch for the supply un is located on the benchboard control panel. Temperature co.". trol in the Engine Room will be achieved by modulating outside-air and return air dampers with a set point of 70'F to- maintain a minimum temperature of 50*F in the supply fan discharge duct. The temperature sensor located in the fan discharge and associated tempera:.ure controller provide a modulating signal-to control the outside and return air damperm High engine room temperature as a result of loss of air flow, fan failure or control component failure will be alarmed in the diesel j_ ges.erator control room. l. l 35
.= - . . . . . . - . -- - - - . - -
Rev. 1 I 1
. The intake and exhaust louver frames and blades will be steel, and i vill be tornado missile proof. The intake and exhaust openings l will be located-at an elevation higher than the maximum probable i flood level. I All components of cach ventilation system will be protected from tornado generated missiles.
- The diesel generator room cooling f ans will be vano axial type with direct-drive totally-enclosed-air-over (TEAO) motors. .
Fan-developed pressures will be based on the prensure drop through ductwork. concrete pienums and distribution accessories. ; 3.3.7 D12a2LEDgine Auxilia? v Systems Pininc and Eauloment Melgi3"9Mut.2 ;
.QDd Materialg ;
l All interconnecting piping unless otherwise noted herein, will be l ANSI 150 lb pressure class. All miscellaneous piping such as for l drains and vents, will be rated for 150 lbs. or greater. ; All piping joints and connections will be welded. Where required, such as at pump suction, discharge connections, and flexible e connections, flanges will be acceptable. ; All~ piping material will be carbon steel except the following systems: Material
- a. Starting Air Systen Stainless Steel '04
. or 304L *
. b. Combustion Air Carbon Steel l-l c.- - Exhaust System Carbon Moly ' Alloy Steel ,. All tanks will be ' designed to atmospheric conditions. Tank *
, material will be carbon steel.
The day tank discharge nozzle connections will be bottom mounted. It will be extended inside the tank such that the accumulated ' residual sediment from the tank bottom will not be disturbed and carried-into-the engine-cylinders. L The day tank and , storage tants associated with each diesel generator include provisior.s for a low-point drain with a trap for , removal of accumulated water and sediment. l l l 36 , y ,-.m y .m yye pw,9y,,,y y 9
,gyy9,_7 y
- w y ya7% r- w+W4r 'P-~'--w-y- v- y H--- --
g +- .---.n#.9.g- ,943p,-9
i Rev. 1 The lube oil motor-operated transfer pumps will be of the rotary . gear type and of commercial grade. The casing material will be cast iron or carbon steel and will be compatible with the transferred fluid. Engine-gunerator set and supporting systems will be designed to provide sufficient space to allow for inspection, maintenance and testing por ash 2 Section XI. Maintem nce envelope space requirements will to in accordance with vendor's recommendations. 3.3.8 Mgchanical Design _and Fabrication Coden SACM diesel generators have been used extensively throughout the world in nuclear power plants with successful results. There have been no significant failures of engine or skid mounted mechanical systems in approximately 300 units placed in service in nuclear power plants. This hirtory attests to the general integrity of the codes and standards applied by SACM. With regards to the pipe systems supplied with SACM equipment, baseline comparisons of the French codes utilized (CODAP) and ASME - Section III have been performed. In a technical audit performed by FDI in 1988, it was fotmd that stress allowables prescribed by CODAP were more conservative tian ASME Section III in the ranges applicable to engine related piping. In addition, SACM performed comparisons between French material (NFA) codes and ?SME Section II for carbon steci piping and weld materials, and stainless steel piping, with acceptable results. SACM welders are qualified to ASME Section IX. SACM utilizes codes and standards that compare f avorably with MME or otherwise will provide items that will perform acceptably. In addition, t.he qualification of the EDGs and the auxi]iary systems supplied by SACM is the result of an extensive effort by SACM, NSP and FDI. This effort is described in "SACM Diesel Generator Qualification Report, Revision 0" submitted to the NRC as an attachment to the September 29, 1989, letter entitled " Project for the Addition of Two Emergency Diesel Generators". This qualification plan was found acceptable by the NRC by letter dated January 33, 1990. The codes utilized for piping and equipment in diesel engine auxiliary systems, not supplied by SACM, are as follows: 3.3.8.1 Pipe / Pipe Support Installation Code ASME Section III (1986) Class 3 with the following exceptions: (1) No N-stamp is required. (2) Maintenance of a current ASME Certificate (NA-8100) or valid stamp is not required. (3) Filing of a quality assurance manual with ASME (NCA-3463, NCA-3862) is not required. 37 1,
' ^' - - ~ _ - - - - . _ _ _ _ _
~ ~ - ' l i Rev. 1 Piping subassembly f abrication and installatj on is performed underThis w
!!SP's QA program.
fabrication and installation of piping and supports will meet the In design, material and fabrication requirements of Section III. additio data reports will be supplied. Pipe support welds to plant structural members and ir. transitional structura? cactions, will be in accordance with AWS D1.1-1988. Integral pipe attachment velding will be per ASME Section III (1986), Class 3 with exceptions as noted above. Footnotes on next page) 3.3.8.2 Design and Fabrication Codes (*/**
- 1. Roolina Water Syltps pyjap_& Fabrigation Code ib.93h HT &_LT Q.i.rEqjja)_ ASME Section VIII,
- a.
- Radiator (1986), U Stamp ASME Section VIII,
- b.
- Expansion Tank (1986)
- Reservoir / Storage AWWA D100 ~/3 c.
Ya n>;
- d. Motor Operated Manufacturer Std.
Make-up Pump Interconnecting ASME Section
- e. III (1986;, Class 3**
Piping (Including Equipment vent Lines) ANSI B31.1-1967
- f. Exp. Tank Till, Overflow, Vent and Drain Lines (beyond the First Isolation Valve) Manufacturer Std.
- g. *Three-way valves
- 2. Eugl._Qi L Sypten ASME Section III,
- a. Day Tank (1986) Class 3**
Dirty Oil Tank API 650-1984
- b. ASME Section III
- c. Interconnecting (1986), class 3**
Piping
- 3. $1aart.ina Air System Manufacturer Std. ,
- Compressor Unit a.
- b.
- Air Dryer Manufacturer Std.
ASME Section VIII,
- c.
- Air Receiver (1986) U Stamp
- d. Interconnecting ASME Section III (1986), Class 3**
Piping (except Manu-facturer's Standard Piping Sections) ANSI B31.1-1967
- e. Vent & Drain Lines (for air receiver, beyond First Isolation Valve) 38 l
9 Rev. 1 4._ Lube Oil System ,
- n. Lube Oil Storage ASME Section III Tenk (1986), Class 3**
- b.
- Lube 011 Cooler Manufacturer Std.
- c. AC Motor Driven Transfer Pump Manufacturer Std.
- d. Tank Vent &
Drain Lines ANSI D31.1-1967
- e. Engine / Aux. Desk ASME Section III Interconnecting (1986), Class 3**
Piping
- f. Lube Oil Storage ANSI B31.1-1967 Tank Fill Line 5, ccabustion Air and Exhaust System ,
- a.
- Intake Air Filter Manufacturer Std.
b.-
- Exhaust Silencer Manufacturer Std.
- c. Piping
- 1. Exhaust ASME Section III (1986), Class 3**, fabricated per SA 691
- Class 13. Stress analyzed per ASME Soction III Class 3 components using- ANSI B31.1 (1986) stress allowables.***
- 2. Intake ASME Section III (1986), Class 3**, fabricated per !UL 105/134 Gr.B. Stress analyzed per ASME Section.III, Class 3.
- Supplied under Dieaal Generator Specification M-870.
** With exceptions as listed in Section 3.3.8.1.
*** .B31.2 allogrables were used since the operating temperature of the exhaust piping is in-excess of the range covered in-SECTION III,-Appendix I material tables I
39 e !
Rev. 1 3.3.9 Iloctrical Egyer Distr _ibution and Switchaear 3.3.9.1 Electrical Power Distribution and Switchgear Design The electrical power distribution system will provide safeguards pcVer to the D5/D6 diesel engine auxiliaries, and serve the plant distribution systems when power is required from the diesel generator sources. The power distribution system will consist of class 1E 4160 and 480 VAC switchgear, 480 VAC motor control centers, distribution panel boards.and transformers, In addition, this power and all 120V l UPS, interconnecting cable and raceway. distribution system will serve those safety related building systu.s that are essential to emergency diesel generator 480 V AC power operation such as HVAC system loadu. Normal (non-1E) distribution, and all DC power distribution will be obtained from the existing plant. The electrical power distribution system and its components will be designed to have sufficient capacity to serve all loads identified at present, plus spare capacity in terms of Separation both load current betweenand the spare nardware for unknown future loads. , safeguards trains, between voltage classes and between fire zones will be provided in accordance with the requirements of Regulatory Guido 1.75, IEEE 384 and 10 CFR 50 Appendix R. Refer to Section 5.3.9.2, Soparation Requiromants. Electrical interlocks or administrative controls will be utilized l to prevent inadvertent paralleling of power sources in all cases where alternate feeds are provided, i 3.3.10 Diese] Generator cod _t;.rols, I.DJliflation , and Alare. 3,3.10.1 Diesel Generator Controls, Indication, and Alarm System Design Each engine generator set will be provided with seven control panels: two engine auxiliaries desks, one bench board control panel, one h ' panel, one vertical control panel, one exciter monitoring system remote terminal unit (RTU) with computer and one vibration monitoring panel (RTV). Required Class 1E and non-1E , 120V AC power vill be provided to the control panels from HCC l distribution panels existing plant UPS distribution syste'm and . receptacle panels. Required ClasG 1E and non-1E 125V DC power will , be provided from existing plant 125V DC systems. The auxiliary desk (one for each engine), located near the diesel engine generator unit, will include gauges to indicate temperatures, pressures, rack position, and engine RPM. The bench board control panel, located in the diesel generator control room, will include instruments and controls for the diesel generator and auxiliaries plus the fuel oil transfer pumps, engine room cooling, and building electrical HVAC supply and return fans. l 40
Rev. 1 A vertical panel, located in the diecal gonorator control roor, , will be providea to include additional instruments and controls for the diesel generator and auxiliaries. A generator exciter panel, located in the diesel generator control room, will include excitation, voltage regulation, and field flashing equipment, and current and voltage transforners for protective relays and power measuring instruments. 3.3.10.2 Tripo and Interlocks All p: ;tective trips other than engine overspeed and generator differential overcurrent wil2 be bypassed upon receipt of an automatic entergency start uignal in response to a safety injection signal and will be annunciated in the main control room. No protective trips will be bypassed upon receipt of an automatic bus undetvoltage start signal. Protective trips are provided to automatically shut down the diesel engine and/or trip the diesel generator breaker, and protect the diesel generator units from possible damage or degradotion during routine testing. Protective trips and logic for each engine are in accordance with vendor recommendations and consist of: o Uverspeed 1/4 o Engine Lube Oil Low-Low Pressure 2/3 (per engine) o Jacket Water High-High Temperature 1/1 (per engine) o Jacket Water Low Pressure 1/2 (per engine) o Crankcase High Pressure 1/1 (per engine) o Lube oil Sump Low Level 1/1 (per engine) o '3enerator Bearing High Temperature 1 / 2 o Engine Searing High-High Lube Oil Temperature 1/1 (per engine) o ' Reverse Power 1/1 (breaker only) e Generator Differential Current 1/1 o Generator Phase Time Overcurrent 1/1 o Generator overvoltage 1/1 o Loss-of Excitation 1/1 o Electric Governor / Fuel Rack Failure 1/1 In order to run the diesel generators during maintenance and testing, start permissive signals from each engi.no will be required from the fallowing: o HT & LT Cooling Water Expansion Tank Level o Engine Oil Sump Level. o Engine Preheating Water Temperature o Prelubricating Pump Discharge Pressure All trip functions will be alarmed prior to or at trip level and the same sensing device may be used to generate both alarm and trip signals through isolation relays. 41
_ - . - - -- .- - . . - - - - - _ _ - - - _ _ - -. - - - ~_ Rev. 1 i An annunciator system will be provided to alarm abnormal operating I conditions. This system will consist of logic relays and solid-utate components located in the vertical panel and light boxes mounted above the benchboard. i The design complies with Position C.7 of Regulatory Guide 1.9. All diesel generator protective tr.ips except engine overspeed and ; generator differential will be blocked upon receipt of a safety The blocking circuits will be testable, injection (SI) signal. abnormal values of blocked parameters will alarm in the control ; room, and the bypass must be manually reset. 3.3.10.3 Diesel Generator Monitoring System Design l A non-safety related computer monitoring unit, located in the diesel generator control room, will include the following: pc-based data acquisition equipment to collect, store and o ' process analog and digital input signals from sensors in the > diesel generator unit and auxiliary systems. J o 'Tha system will be capable of monitoring operatino parameters, inte rf~:e with the plant computer, event sequencing, provide
-historical file, graphics and report generation.
o The system will be capable of providing 0-SV DC or 4-20 mA LC analog or digital outputs for remote use. A non-safety related vibration monitoring panel located in the diesal generator control room, will: o process input signals from vibration sensors mounted on the engine bloc':,. generator bearings and radiator f an assemblies, , and o provide analog and digital outputs for remote use. 353.'11 -Diesel Generator Operatina Deccriplioj} The mode of . operation of each oiesel generator set is determined by the position of the diesel generator control modo selector switch to'either " normal" or " maintenance". A brief description of the operating sequence ja as follows: r
- 1. Normal mode - Selection of " Normal" mode will allow hutomatic '
start-up, manual emergency start cr test operation of the diesel generator set. These operating tunctions can be initiated from the Diesel Generator Control Room _(" Local") or Main Control Room (" Remote") by using the N ocal-Remote" selector switch,
- a. Automatic Start Mode - Start of the diesel generator can bc initj ated automatically by either a bus undervoltage and/or l
a Safeguards (SI) signal. In response to either of thesethe diesel generator will types of automatic starts, , l, l 42 i
,-a . . , - . , _ _ _ . _ , _ , , _ . , _ , -, . . . - .
Rev. 1 accelerate to rated speed and voltage within ten (10) , seconds (FAST START mode) , from receipt of the starting signal. Emergency start signa n w .. or SI) differ from the bus undervoltage start signal, in that normal engine or generator trips are not bypassed during a bus undervoltage-only automatic start. A Safeguards (SI), cr EMERGDICY manual start will block all of the engine and generator trips, except thuse from manual emergency stop, generator differential, nr.d engine overspeed. ,
- b. Test Mode - For periodic test purposes, the diesel generator may be started and stopped through tha usa of a manual start-stop Test Switch. Two (2) acceleration, rates are available in this mode, SLOW and FAST.
The SLOW start mode is operator-selected and provides for a longer acceleration time via a pre-set speed ramp within l The ! the diesel generator governor control system. l acceleration time is at least twice that of the FAST start
- mode.
The FAST start mode is operator-selected and provides a direct simulation of the rapid acceleration rate required - in response to any automatic start signal. Both the SLOW and FAST start moden provide automatic operation of the field flashing circuitry, resulting.in a
" Ready-For-Lead" condition when synchronous speed has been ,
reached.
- 2. Maintenance Mode - Selection of " Maintenance" position will l.
allow the following operation similar to test modo except: t,
- a. Permit individual operation of either engine _1 or 2 through the use of the diesel engine selector switch when the generator is decoupled.
- b. Allows hydraulic or electric governor operation,
- c. Diesel generator set will not respond t3 an emergency start signal while on maintenance mode.
- d. Maintenance operation can only be initiated from the DG Control Room by way of Mcy-locked selector switches.
- e. Field flashing circuit. requires manual operation.
- 3. Shutdown clode - Diesel genwator shutdown sequen:e may be initiated in either normal (emergency or test) or maintonance modes. Emergency shutdown can be manually accomplished through
Rev. 1 the use of an emergency stop pushbutton, located on the bench board in the diesel generator control room, or automatica13/ on receipt of overspeed or generator dif f erential signal. While in maintenance or test mode, nanual shutdown is initiated by placing the start-stop selector switch to the "stop" position or automata ally upon tactivation of any of the diesel generator protec+..' devices. However, 12 an emergency (SI) start signal is receiu n while in test mode, the diesel generator cannot be stopned through the start-stop switch and must go through the normal thutdown sequence upon termination of the emnrgency condition. Following shutdown, the diesel gencrutor set is immediately available for operation as long as no maintenance and/or repair is to be performed.
- 4. Load Sharing and Speed control - Diesel generator speed control and load sharing between the two engines is accomplished through the electric governors with associated speed sensoro, LVDT rack transducers and actuators. The electronica governors are backed up by hydraulic units. Idle / rated speed setpoints and uroop/isochronous modes are preset and will automatically overrido all manual settings upon receipt of an emergency start signal.
3.4 FUEL OIL STORAGE AND TRANSFER SYSTDi 3.4.1 EUDEt.i. Qual hqpirementS ADiES.P_.QIlp_tiGD The following are general functional requirements and descript. ions of systems and structures. Detailed design parsmeters and requirements are given in Section 3.4.2. 3.4.1.1 Basic System Description The Fu 21 Oil Storage and Transfer System provides lon.] term storage of fuel for the new Unit 2 Diesel Generators (D5 and DC) . The DS/D6 Diesel Generator Fuel Oil Storage System consists of four safety related fuel oil storage tanks and one non-safety related receiving tank, and includes transfer pumps, piping, instrumer.tation , and controls necessary for supplying fuel to the diesel engines vic. Fuel 011 Lay Tanks for suven days of continuous 100 percent operation at rated full load, without being replenished. Thn four storage tanks will be contained in an underground concrete vault struccure provided along the west wall of the new diesel generator. building. The vault will provide the tanks and piping components gr:tection from tornado generated missiles and flood. It also provides a 3-hour fire protection barrier between tanks for each diesel generator set and from surrounding environment. The receiving te7k is provided to receive and hold fuel oil from delivery trucks for testiig prior to placing oil in the storage tanks. The receiving tank will be located outdoors and mounted on 44
l key. 1 , a diked concrete pad along the south wall at the west corner of the D5 and DG Building. . Two storage tanks will be dedicated for each diesel generator set. Two 100% capacity transfer pumps will be provided for each diesel - generator set with suction piping interconnected and valved 6.o that any pump can be used in transferring fuel from any storage tank of the associated diesel generator not on day tank low level control signal. This provides system flexibility to ensure operability of both diesel generator sets under all potential single active failure conditions. The storage tanks are filled by means of gravity flow from the outdoor receiving tank. The storage tank to be fil7ed is selected by manual valve operation. Figure 3-5 depicts the fuel oil storage and transfer rystem for the D5 and D6 diesel generators. Figures 3-6 and 3-7 depict the fuel ; oil systems for the D5 and D6 diesel generatots, recpectively. 3.4.1.2 Tank Capacity
- a. Storage Tanks Each diesel generator set will be provided with two storage tanks each with a usab?.e voP1me of 30,800 gallons. Usable volumes have been determined by actual elevations of the overflow piping and cuction piping. These volumes were determinnd to provide sufficient capacities to allow for operation of a diesel generator set for seven days of continuous 100 percent operation at rated full. The conservative calculation method given in ANSI.N195-M76load.
has been used to determine fuel oil storage requirements. The tanks are sized so that if one is not in service, the capacity of the . remaining three is . sufficient to. supply DS and D6 continuously for seven days at actual load. ' Interconnecting piping ' is provided between the storage tanks for D5 and D6 such that the fuel oil storage system can supply sufficient fuel to operate one diesel generator f or 14 dLys at actual load in the event of a
-design basio flood.
In addition to level instrumentation, each fuel oil storage tank will be provided with e stick gauge connection for determining fuel level in the tank. The connection-will be accessible through a ceiling hatch. b.-Receiving Tank The receiving tank will be designed to receive and hold fuel oil until it.has passed all required testing for use. The tank will have usable capacity of 13,800 gallons. 45
-- . . - ~ . -.- - -~ --.-.- - - . - - - -.- - .
Rev. 1 3.'(.'t.3 Pump Requirements
- a. Transfer Pump i
There will be' four transfer pumps for the D5 and D6 diesel All pumps will generator sets, two for each diesel generator set. be identical and have sufficient head and capacity to transfer oil - to the associated day tank. The pump will start when the day tank reaches the designated low liquid level. The transfer pump suction and discharge lines for each pair of pumps associated with the diesel generator set will be cross-tied to allow fuel to be transferred from any storage tank to the day tank by any transfer pump.
- b. Recirculating Pump A recirculating pump will be provided with the receiving tank. A cleanup filter is provided on the pump discharge side to provide filtering while the fuel oil in being recirculated prior .to transfer to the storage tank. .
3.4.1.4 Process Piping The fuel oil transfer piping will be capable of transferring oil at
- design temperature and pressure from the storage tank to the day tank. The return line from the day tank will be sized to handle continuous overflow by gravity to the storage tanks. }
With . the exception of the - transfer pumps, controls, and relief valves, no other active or automatic devices The are storage requiredtankfor operation of the fuel oil transfar process. piping system will be designed to allow manual control of flow. The piping system will allow oil stored within each fuel oil storage tank to be pumped- directly from one safety related storage The fuel oil transfer system tank to . the other storage tank. piping includes five micron duplex filters. be capable of The receiving tank recirculation piping will recirculating fuel oil from the receiving tank by means of the recirculating pump, through the cleunup filter and return back to
-the: receiving tank.
Sampling points will be provided as required at the inlets to filters. Samples will- be taken while recirculating storage tank contents.
'3.4.1.5. . Electrical Power Supply and Controls The Safeguards electrical power supply to the fuel oil transfer pumps will be 480 Volt, 3-phase, 60 Hertz, and of adequate capacity. '
to power -the drive motors. Safeguards Class 1E 120V AC and 125V DC associated control and power will be provided for all instrumentation circuitry. Non-1E power will be provided for indication'and alarm circuitry. 46
I Rev'1 Controls for the fuel tank transfer operation will be automatic, with provisions for manual override. l The storage tanks will be provided with high and loa level alarms to be annunciated in the 05/06 control rooms. High pressure ; differcntial across the transfer system fuel strainers or filters will also be annunciated in the 05/D6 Control Room. The storage ' tanks will be provided with level indication to be displayed locally and on the DG benchboard control panels. On-off operation - of the transfer pumps will bo initiated by level switches in the fuel oil day tanka. Operating status will be monitored and , alarmed. The receiving tank will be provided with a locally mounted level indicator. The recirculating pump will be provided with on-off operation initiated by a local control switch. Trouble in the recirculating pump and associated cleanup filter will be annunciated in the diesel generator control room through low /high -i differential pressure twitches across each pump and filter. Temperature inside the belou-grade vault will be above the fuel oil cloud point temperature since the vault is insulated and located below the trost line; therefore, heat tracing will not be required. 3.4.1.6 operation Fuel oil shipments, received by truck delivery, will be held in the receiving tank and tested for specification conformance. After specifications are verified by test, the fuel oil will be transferred to the storage tanks, on a periodic basis, the fuel oil in each storage tank will be tested for water content, sediment and viscosity. Algae growth in the storage tank will be inhibited by an additive furnished in the fuel oil. 3.4.2 Desian Raouirements
- 3.4.2.1 Tank Design
- a. Storage Tank The fuel oil storage tanks will be horizontal cylindrical tanks t made of materials compatible with the stored diesel fuel. oil. '
Galvanized . material will not be used. The tanks will be shop fabricated and will meet the requirements of NFPA 30 and designed and fabricated in accordance with the requirements of ASME Section III, 1986 Edition, Subsection ND with the following exceptions: Extending below the fill inlets of the Fuel Oil Storage Tanks will , be vertical spargers with numerous holes. This arrangement will disperse the fuel during filling and minimize turbulence. Similarly, the outlet originates with a horizontal tube with 47
- -. - . -. c_ - .- . . - , - , . - .
Rev. 1 numerous holes which is raised above the tank bottom. A bell shape sump at the tank bottom with drain plug will provide a collection and removal point for water and sludge. (1) No N-stamp is required. i (2) Maintenance of a current ASME Certificate (NA-8100) or valid stamp is not required. - (3) Filing of a quality assurance manual with ASME (NCA-3463, NCA-3862) is not required. The tank manuf acturer is required to apply its QA program, which has been evaluated and found to meet 10CFR50 Appendix B. This will provide sufficient assurance that the tanks will meet the design, material-and fabrication requirements of Section III. In addition, I design reports and Authorized Nuclear Inspector certified data 7 reports will be supplied.
- b. Receiving Tank The fuel oil receiving tank will be vertical steel cylindrical shop :l fabricated atmospheric tank designed and fabricated to the requirements of API 650. The tank will be installed outdoors on a Non-Seinmic Category I concrete pad with vertical enncrete walls :
(diked). The dike is sized to contain the tah
- volumetric contents, should a leak or rupture occur, plus an additional volume equivalent to 30 minutes of fire suppression water flow. The tank will be located such that the outside tank surface is separated from any adjacent structure by at leaut 5 feet. .
- c. General All tank fill and drain connections will be designed to avoid any turbulence that may stir up the sediment accumulated at the bottom -
of the tank. All tanks will be provided with a drain connection to remove sediment or water from the tank bottom. Each storage tank will be provided with liquid level indication (analog loop), to be monitored inside the D5/D6 Building (NSP UST , policy for inventory requirement) on the Benchboard panel. The receiving tank will be provided with spill protection at the fill connection. Fill inlet connection and vent outlet connection will 7e protected from flood conditions and will be positioned above the maximum
. probable flood. level.
3.4.2.2 Underground Storage Vault l The emergency storage tanks will be installed in a Seismic Category I reinforced concrete vault enclosure located below seismic grade
' level and adjacent to the west wall of DS/D6 Diesel Generator l
48 ,
Rev." 1 Building. The vault will provide the required 3-hour rated fire protection barrier, including DS/D6 west wall penetrat.j ons, for enclosed fuel supply tanks, and in addition, will withstand the effects of tornado generated missiles, site flood, and buoyancy force considerations. The vault will be divided into two compartments by a concrete ' partition wall to separate each pair of tanks serving a single , diesel generator set and provide fire and flood protection between ! each diesel generator sets fuel supply equipment. The vault will be sized to provide a minimum cicarance of 15 inches t from all tank surfaces. Leakproof hatches will be provided on top of the vault for tank internal and external inspection access and to allow removal of tank internal baffles and other appurtenances. Level instrumentation will be botton mounted. The underground storage vault will be insulated suf ficiently to protect the fuel oil from reaching a minimum system operating temperature. The vault temperature will be indicated on a wall nounted panel in the respective engine room and monitored by operations. This indication serves the function of fuel oil temperature indication (ref. SRP 9.5.4). The vault will be provided for containing leakage of the tank cont.onts and any accumulated seepage water. The vault floor will slope to a sump, which will contain a leak detector. Leak detection instruments will be provided to alort presence of fuel or water in the sump. This-indication will be locally alarmed, and will provide an input to the general trouble alarm in the main control room. The detailed structural design requirements for the concrete vault structure will be as specified in Section 4.0 The vault's walls and bottom will be provided with a waterproof membrane. All hatches and penetrations on the top slab will be
'eak-tight.
3.4.3.3 Pump Design
- a. Transfer Pump The. transfer pumps will be of the rotary positive displacement type. .The pump casing will be constructed of carbon steel or other ,
materials that are compatible with diesel fuel oli. The cransfer pumps will be located in the D5 and D6 pit areas at an elevation that will ensure the available net positive suction head (NPSH) will conservatively cnvelope the required NPSH. The transfer pumps of each diesel generator set will ise separated by a 3-hour rated fire barrier. l-L 49 , t
, . . . , , ~ , , - - - . - . . ., .
~ - _ - - - .- - - _ - _ -.- - - - . .- - - . . . _ - - -
Rev. 1
- b. Recirculating Pump The receiving tank recirculation pump will be of the horizontal centrifugal type. Pump casing will be constructed of carbon steel or other material compatible with the stored fuel oil. The pump will be located in the D6 pit area.
l 3.4.3.4 Piping System i All piping, fittings, valves, and associated components and supports connecting the emergency storage tanks, transfer pump, diesel engine day tanks, and the emergency fill station will be , designed and fabricated to the requirements of ASME Section III, l 1986 Edition, Subsection NDA with the following exceptions: (1) No N-Stamp is required. (2) Maintenanca of a current ASME Certificate (NA-8100) or valid stamp is not required. (3) Filing of a quality assurance manual with ASME (NCA-3463, NCA-3862) is not required. Manu**cturers are required to apply their QA programs, which have been valuated and found to meet 10CFR50 Appendix B. Tnis will i provide sufficient assurance that the piping systems will meet the design, material and fabrication requirements of Section III. In l addition, design reports on piping systems and supports will bc ) supplied. All piping and isolation valves protecting the safety related pressure. boundary will be located within the Category I diesel generator building or Category _I buried vault structures whsre they are protected from tornado missiles and site flood conditions. l Pipe supports will be designed to the requirements of ASME Section III, 1986 Edition, Subsection NF with exceptions as noted above. Pipe support welds to plant structural members and.in transitional structural sections will be per AWS Code D.1.1 - 1988. All piping and components associated with the receiving tank and connected beyond the safety related piping pressure boundary
' isolation valves will be designed to the requirements of ANSI B31.1 L
and designated as non-safety related. The recirculation pump piping ' loop will contain a duplex cartridge type filter which will provide high solid removal efficiencyA for cleanup of any new fue3 differential pressure alarm received at the storage facility. will be provided to alert the operator of a plugged filter. Manual action can then be taken to valve in the redundant filter. Sample stations will be provided in the transfer piping to the day tank.and also at the receiving tank recirculation piping. All. l l ' 50
Rev." 1 i stations arn located inside the diesel generator engine rooms to - allow convenient fuel test sample retrieval for the required > chemical testing of stored fuel. All fuel oil piping will be located inside the concrete structures , or over concrete slabs. Containment curbs as required (dikes) will , be provided to collect all potential fuel leakage or spills to These structures will be provided prevent ground contamination. with local leak detection instrumentation to provide indication of any leakages from piping.
.The transfer pumps, recirculating pump and all fuel oil piping will be ' designed to allow for inspection, maintenance and testing.
Strainers are provided on the transfer pump inlets to protect pump
-internals from debris in accordance with ANSI N195-1976. Pump and valve maintenance envelope space requirements will be in accordance with manufacturer's recommendations. Flanges are permitted where required for maintenance (e.g. pump connections).
Piping material w..ll be of carbon steel having a minimum ANSI pressure-temperatore rating of lud lbs. . The contents of any storage tank can be recirculated through-a 5 micron duplex filter without preventing the other storage tank for the same DG set from feeding the day tank. , Any storage tank can receive fuel from any other storage tank while the first storage tank is feeding its associated day tank. 3.4.2.5 Electrical and Controls Electrical-power distribution will be accomplished by means of a 400V AC, 3-phase,. 4-wire, grounded system. Transformations from this service to 120 (single-phase) will be provided as necessary. ; overcurrent protection will be provided by means of molded case l thermal-magnetic circuit breakers. Proper coordination of all overcurrent protection devices . will be provided down to (and Circuit breakers 'for safety including) local panelboard(s). related circuits will be testable. . Separation between redundant trains (by 3-hour rated barriers) as , well as . that ' required between IE and non-1E circuits will be provided in accordance with Regulatory Guide 1.75, IEEE 384, and 10 Separation CFR 50, l Appendix R. Refer to Section 5.3.9.2, Requirements. All controls and instrumentation will be electric and/or electronic - and will be designed to operate within the design basis environment of 50 F to - 12 0*F inside the D5/D6 engine room areas. -Electrical equipment inside the fuel storage tank vault will be designed for - ' 10*F.to 120*F. Transfer Pump control switches and storage tank level indicators will be located on the diesel generator control room bench board. 51
Rev. 1 I All pressure indicators and the receiving tank pump controls and i eMitional storage tank level indicators will be mounted locally. l
%e following conditions will be monitored and alarmed in the diesel generator control room with a common trouble alarm in the main control room:
- a. High and low ctorage tank levels. 1
- b. Low dif ferential pressure across the recirculating pump or high (
pressures across the recirculating clean-up differential filters.
- c. High differential pressure across transfer pump strainers.
from the fuel storage tank level sensors will be i Signals transmitted to the RTU for computer monitoring and to the Control Room and local Annunciator Panel for high/ low alarms. Power supplies for the D5 and D6 fuel oil storage tank pumps will be separated for redundancy and protection from common mode failure. Power cable will be routed separately from any control l wiring. Non-safety related power and control cables for the l receiving tank and its pump will not be routed with safety related cables or piping. 3.4.2.6 Mechanical Design and Fabrication Codes f The design fabrication code for piping and equipment for the fuel oil storage system are as follows:
.3.4.2.6.1. Pipe / Pipe Support Installation Codes ASME Section III (1986) Class 3 with the following exceptions:
(1) No N-Stamp is required. (2) Maintenance of a current ASME Certificate (NA-8100) or valid stamp is not required. (3) Filing of a quality assurance manual with ASME (NCA-3463, NCA-3862) is not required. will apply its QA program to piping, fabrication and NSP installation, including supports. This will provide sufficient assurance that the piping will meet the mat -ial.and fabrication requirements of -Section III. In addition, design reports and will be Authorized Nuclear Inspector certified data reports , supplied. Pipe support welds to plant structural members and in transitional structural sections will be in accordance with AWS D1.1-1988. Integral pipe attachment welding will be per ASME Section III (1986), Class 3, with exceptions as noted above. 52
Rev. 1 3.4.2.6.2 Design and Fabrication Codes . Dssion & Fabrication Code
- 1. Tanks
- a. Emergency Storage Tanks ASME, Section III (1986), Class 3** I
- b. Receiving Tank API GSO-1984
- 2. Pumps
- a. Transfer Pumps Viking Pump Commercial Grado dedicated for Safety-Related use.
- b. Recirculating Pump Viking Pump Manufacturer's Std.
- 3. Piping, Pipe Support Components and Valves
- a. Fuel Oil Transfer Piping ASME Section III system (except vent and (1986), class 3**
drain lines)
- b. Receiving Tank Piping & ANS1 B31.1-1967 Recirculating Piping System
- c. Storage Tank Vent ASME Section III (1986), Class 3**
- d. Drain Lines and ANSI B31.1-1967 Instrumentation Tubing after First Isolation / Root.
Valve
- e. Strainers Commercial Grade dedicated for Safety-Related use.
** With exceptions as listed in Section 3.4.2.6.1.
3.5 DESIGN STANDARDS In addition to the codec and standards listed in the design requirements given above in Section 3.4.2.6, the following NUREG 0800, IEF.E standards, and regul story guides are adopted in whole as desigt. criteria requirements for the D5 and D6 Diesel Generator and
~ Auxiliary Systems as described in Section 3.0.
53
1 l 1 Rev. 1 3.'5.1 lil)lEC 0800 Standard Review Plan fSPP1 SRP 3.2.1 Rev 1, 7/81 Seismic Classification SRP 3.2.2 Rev 1, 7/81 System Quality Group Classification SRP 9.5.4 Rev. 2, 7/81 Diesel Engine Fuel Oil Storage and Transfer System (except no fuel oil temperature indication is provided. Building temperature is controlled and vault temperature is monitored) SRP 9.5.5 Rev. 2, 7/81 Diesel Engine Cooling Water System S*P 9.5.6 Rev. 2, 7/81 Diesel Engine Starting System SRP 9.5.7 Rev. 2, 7/81 Diesel Engine Lubrication System SRP 9.5.8 Rev. 2, 7/81 Diesel Engine Combustion Air Intake And Exhaust System O, 7/81 Criteria For Alarms And Indications BTP PSB-2 Rev. With Diccel-Generator Unit Associated Bypassed And Inoperable Status 3.5.2 IEEE Standard,g IEEE 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations IEEE 308-1974 Criteria for Class IE Electric Systems for Nuclear Power Generating Stations Standard for Qualifying . ass 1E Equipment for IEEE 323-1974 Nuclear Power Ge.terating Stations (Note: IEEE 323 is invoked as a guideline document the determination of to provide a basis for qualified life of equipment. It for is not intended to environmental be invoked as a basis qualification. 10 CFR 50.49 requirements which are met by methods described in RG 1.89 (endorsing IEEE 323) do not apply to the mild environment of the new D5/D6 Building). for the Periodic Testing of IEEE 338-1977 Standard Criteria Nuclear Power Generating Station Safety Systems IEEE 344-1987 Guide for Seismic Qualification of Class I Electrical Equipment for Nuclear Power Generating Stations (Note: Seismic qualification for the D5/D6 Diesel Generator, HVAC duct dampers, damper actuators, and the Class IE Motor Control Centers cites the 1975 revision. Refer to documentation for details.) 54
__. . . .-. . _ . ~ - . . __._ __- _. .=_ - ~ . _ - . ~ - . - . - . - . . . - -, .- Rev. 1 ; IEEE 379-1972 Guide for the Application of the Single Failure Criterion to Nuclear Power Generating Station Protection Systems IEEE 383-1974 Standard for Type Test of Class IE Electric Cable, Field SpMces and Connections for Nuclear Power Generating Sections. IEEE 384-1981 Criteria for Separation of Class IE Equipment and : Circuits (See note under Reg. Guide 1.75) (Note 1: The 1581 revision is specified because it f addresses comments contained in Regulatory Guide # 1.75, Rev. 2 on the 1974 revision of.the standard.) (Note 2: The identification requirements of IEEE 384 for tagging intervals of cable, cable tray and raceway may not be strictly followed. Guidance provided by the USAR Will be adhered to as introduction of a different set of requirements ' would be confusing.) IEEE 387-1975 Diesel Generator Units as Standby Power Supplies (Note: Certain provisions of the 1984 revision of , the standard are included . in the DS/D6 Diesel - Generator npecification because they provide guidance for issues not. fully addressed in the 1975 revision which was referenced in Regulatory Guide 1.9,-Rev. 2.- These provisions include Appendix A guidance for development of a load profile, Appendix B for the format to define diesel generator service conditions, and Table B2 format for use in defining those components with less than a 40 year' operating life.)
- 3. 5. 3 ' Reculatory Guides Regulatory Guide 1.6, 3/10/71 Independence Between Redundant Standby (On-site) Power Sources and Between Their Distribution Systems Regulatory Guide 1.9, Rev. 2, 12/79 l Selection Design and Qualification'of Diesel Generator Units Used As Standby (On-site) Electric Power Systems at Nuclear Power P3 ants
' Regulatory Guide 1.29,-Rev. 3, 9/78 Seismic Design Classification Regulatory Guide-1.32, Rev. 2, 2/77 Criteria for Class 1E Electric Systems for Nuclear Power Generating Stations 55
. - -- .. .. ~ .- _ - _ . . _ _ - - _ _ -- _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
4 Rev. 1 Regulatory Guide 1.47, 5/73 i Bypassed and Inoperable Status Indication for Nuclear Power Plant ! Safety Systems i l Regulatory Guide 1.53, 6/73 i Application of the Single Failure Criteria to Nuclehr tower Plant Protection Systems Regulatory Guide 1.61, 10/73 Damping Values for Seismic Design of Nuclear Power i'tants i Regulatory Guide 2.62, 10/73 Manual Initiation of Protective Actions Regulatory Guide 1.75, Rev. 2, 9/78 Physical Independence of Electric Systems (Note 1: Separation criteria of RG 1.75 and IEEE 384 will be met within- the new diesel generator structure. As a- minimum, requirements of the USAR will be met for new equipment and system L designs within the existing plant.) (Note 2: For regulatory position C.10, cables will be marked at 10 foot intervals, rather than the 5 foot interval specified, in conformance with USAR Section 8.7. 5 which has been found to be sufficient to ensure proper cabie installation.) , Regulatory Guide 1.81, Rev. 1, 1/75 Shared - Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants (Note: For regulatory position C.3, the onsite emergency a.c. electrical system for each unit will be separate and independent, but the capability to interconnect the emergency (safeguards) 4kV a.c. buses within separation criteria divisions (i.e. , Unit 1-Train A to Unit 2-Train A, etc.) will be retained for use during Station Blackout- (access to Alternate A.C. (A.A.C) source) and other similar circumstances.) Regulatory' Guide ~1.92, Rev. 1, 2/76 Combining Modal Responses and Spatial Components in Seismic Response .inalysis Regulatory Guide 1.100, Rev. 2, 6/88
- Seismic Qualification of Electric and Mechanical Equipment for Nuclear Power Plants-Regulatory Guide 1.108,. Rev. 1, 8/77 Periodic Testing of Diesel Units Used As On-site Electric Power Systems at Nuclear Power Plant Regulatory Guide 1.118, Rev. 2, 6/78 Periodic Testing of Electric Poker and Protection Systems 56
Rev'. 1 Regulatory Guide 1.122, Rev 1, 2/78 Development of Floor Design Response Spectra for Design of Floor-Supported Equipment or Components 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 Bulletin 79-02, Rev. 2, 11/79 Pipe Support Base Plate Designs Using Concrete Expansion Anchor rolts 3.5.4 NFPA Standards NFPA 30-1987 National Fire Protection Association Standard for Flammable and Combustible Liquids Code .l NFPA 37-1984 National Fire Protection Association Standard for Stationary Combustion Engines and Gas Turbines (Note: Paragraph 5-8.1 can not be met. Fuel will be fed to the engines by gravity from non-integral day tanks.) 3.5.5 ANSI Standards ANSI-N195-1976 Fuel Oil Systems For Standby Diesel Generators 3.5.6 porthern States Power Standarda Prairie Island - Updated Safety Analysis Report Prairie Island - Final Safety Analysis Report Prairie Island T2chnical Specifications USP Underground Storage Tank Policy Compliance Gulds, dated October 3, 1989 (exception: fuel inventory management system not provided). Prairie Island O{erations Manual Section Hil, Electrical Construction Standards. Prairie Island Security Plan. 3;5.7 Fluor Daniel Procedures Pipe Stress Analysis and Pipe Support Design Procedures for SBO Projects Procedures No. 834473-1 (latest Rev.) 57
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R e v .' 1 4.0- NEW D5/D6 BUILDING The new D5!and D6 Building will house two SACM diesel generators (DS and D6) , with associated control par.els, auxiliary equipment, electrical distribution equipment, fuel oil and lube oil tanks, and diesel engine raciators. The D5/D6 Building will be an above-grade Seismic Category I reinforced concrete structure, designed-to withstand design basis load combinations. The D5/D6 53uilding vill be located along the west wall of the Auxiliary Building (Column Row 15) between Column Rows G-and K, and has approximate dimensions of 68 ft. x 124 ft. x 61 ft.- high including penthouses. The 05/D6 Build'ng will not be connected structurally to the existing main plant Auxiliary Building and Turbine Building The ( <isting cooling water emergency discharge line, Turbine Room Alt ernate Discharge Line, Fire Hose Station HH7, the high mast lighting and below-grade communication duct bank and security cable are to be relocated to accommodate the new building. . Building space will be provided for future addition of batteries, battery charges, inverters, MCCs, and distribution panels. Figures 4-1 through 4-9 depict the layout of the D5/D6 Building. Since the. new D5/D6 Building will occupy the area in which the condensate storage-tanks.and associated piping were situated, the Condensate Storage Tanke 21 and 22 were relocated to west of the Unit 2 Containment Building along the south wall of the new DS/D6' Building.
~ 4 .1 - SEISMIC DFSIGN CLASSIFICATION The seismic design classification for the D5 and D6 building' systems are as follows:
4.i.1' Structurcs L The D5/D6 Building will be a Seismic Category I structure. 4.1.2 Electrical /Mechaqj. cal /JVAC BuildiDe Sup. port Systeng All safety related electrical, mechanical and HVAC systems and components will be designed .to withstand a Saf e Shutdown Earthquake (SSE) and remain functional (Seismic Category I). All non-safety related systems and components and their supporting systems will be designed to ensure that the SSE would not cause their structural failure resulting in' damage to safety related systems or components (Seismic II .over I) . 71
I Rev. 1 4'.1.2.1 Electrical Support Systems The potential failure of electrical support systems that are non-safety related anywhere within the Building could endanger the functioning of safety related systems and will, therefore, be supported caismically.
.The mounting of lightiag, communications, and fire detection systen components will be designed to withstand seismic conditions (Seismic II over I) .
The mounting of security cor. trol system components will be designed for seismic conditions in areas where structural failure of security system components could result in damage to safety related equipment. Normal power distribution equipment, raceways and supports within the new building will be supported seismically to preclude the possibility of damage to safety related equipment (Seismic II over I). Safequards power distribution equipment (seismic active), raceways and supports (both seismically passive) will be seismically qualified. 4.1.2.2 Mechanical Support Systems All station air, plumbing, fire suppression, and other non-safety related piping and supports witnin the new Building will be seismically supported to withstand the SSE without structural failure (Seismic II over I). Non-safety related piping will be supported seismically to assure that the failure of the piping cannot damage safety related systems or components (Seismic II over I). 4.1.2.3 HVAC Support Systems All components of the DS/D6 Building HVAC System shall be Seismic
~
Category I. Instruments .nd concrols that are requirad for the operation of safety related fans and dampers will also he Seismic Quality Class I. Instruments that perform indication and alarming and controls for non-safety related cooling equipuent will be supported seismically (Seisnic II over I). 4.2 SAFETY DESIGN CLASSIFICATION It - safety design classification for the 05/D6 building systems are as fol' lows: 4.2.1 Structurgn All structures are classified as se.fety related or non-safety related. I l
- . . .- .~ -, n . ,n
o- , 1 l 1 R e v'. 1 ) EbFETY CLASCIFICATION_OF STRUCTURES structurg Classification D5/D6_ Building Safety Related
-As2.2 BuilsLLD.<T Support Systents The' design classification for electrical, mechanical & HVAC support systems is as follows:
- 1. Electrical Support System Shssificat12n
. a. Lighting, communi-- Non-Safety Related cation, & normal power distribution b._ Safeguards power Safety Related & distribution system class 1E components serving HVAC
- c. Fire Detection Non-Safety Related, Fire Protection Related
- d. l Security Control Non-Safety Related, Security.Related
- 2. Machanical Support Systems Clagpification
- a. Plumbing, service Ncn-Safety Related air, & fire suppression
- .b._ Fire' suppression & Non-Safety Related L systems L -3. Normal HVAC Support Systens .Qh s_tdfica312D
- a. ~ Components of1the Non-Safety Related L ' lube uil1 storage tank / fuel oil day tank rooms exhaust system
- b. - D5/D6 control room Non-Safety Related g
L c. Switchgear Area Non-Safety Related auxiliary cooling L system ,
- d. Controls for auxiliary Non-Safety Related heating, cooling &
i ventilation systems l l-l' 73 l l-
~. __ _ . . . __ _ _ , . . - - . . -
Rev. 1
- e. Instrumentation (indi- Non-Safety Related cation & alarm only)
- f. Future battery room Non-Safety Related
- 4. Safety-Related HVAC Support Systems
- a. Cooling fane/ modu- Safety Related lating dampers (control switchec, temperature sensors, transmitters &
controllers)
- b. Instrumentation (indi- Non-Safety Related cation & alarm only) 4.3 BUILDING STRUCTURE DESIGN 4~.3.1 Desian Loads, All- structures will be designed to withstand various loads as follows:
All mechanical,and electrical equipment and appurtenances will be-supported in accordance with their design classification. Supports for non-aafety-related items will be designe. and installed such that their supports do not fail under seismic conditions and endanger. the operation of any adjacent safety-related items (Seismic.II over I). All the major loads to be encountered or to be postulated are listed below. All the loads listed,.however, are not necessarily applicable to all the structures and their elements. Loads and the
- applicaule load combinations for which each structure has to be designed will depend on the conditions to which that particular structure is subjected.
4.3.1.1 Dead Loads (D) , The . dead loads include the weight of framing, roofs, floors, walls, H partitions, platforms and all permanent equipment and materials. L The' vertical and lateral pressures of liquid will also be treated I :ac dead. loads, as indicated in ACI Codes. L Floors shall . be checked for the actual equipment loads. For l permanently attached small equipment, piping conduits and cable trays, a minimum of 50 psf .shall be added where appropriate. 1. ! 4.3.1.2 . Live Loads (L and L ) Live loads will be as specified in Subsections 1 and 2, below, but in no case less than the minimum design live loads specified in 3.
- l. 74
Rev. 1 l
- 1. Live Loads (L) .
1 These include floor area loads, equipment handling loads, and similar items. The ficor area live load will be omitted from areas occupied by eguipment whose weight is specifically included in dead load. Live load will=not be omitted under equipment where. access is provided (for example, elevated tank on legs). The ~ lateral earth pressure will be treated as live load as indicated in ACI codes.
- 2. Live Loads During Operation (L.) l 4
In loading combinations including earthquake, the live loads shall be limited to "L.", which is defined au the live load expected to l be present when the plant is operating. The value of Li will be considered to be 50 psf. l j
- 3. Minimum Design Live Loads l
The following minimum live loads will be used in the design. Certain other applicable loads are listed separately in succeeding sections. Roofs 50 psf Stairs & Walkways 100 psf Railings 25 psf or 200 lbs. applied in any direction at' top of railing Platforms & gratings 100 psf Ground Floor'(except control room)- 500 psf Control-Room 250 psf All other floors 200 psf'
-4.3. 1'.'3 Construction Loads Structures and . components will be . designed considering all applicable' construction load conditions, L4.3.l'.4 Earth Pressure Earth pressures will be in accordance with tne requirements of UBC.
-In load combinations, loads due-to earth' pressure will be treated
. as live. load.
4.~3.1.5 Groundwater Pressure For structural and buoyancy calculations, the high groundwater
- table will ba. as specified below:
Water Levels-(Ref. USAR) 75
n . ._ , - .. -_ 4
- Rev. 1
+ Normal ground n ter- El. 674'6" Low ground. water El. 672?6" Probable Maximum Design Flood El. 703'7" The effect of a design flood will also be considered. In load combinations, loads due to water pressure will be treated as dead load.
4.3.1'.6 Environmental Loads (USAR Sec. 12) These consist of wind (W) and snow loads. Sncw loads of 50 lbs per sq. ft. of horizontal projected area will he used in the design of structures and components exposed to snow. Roof loads from rain ponding is not significant. The main roof slab at elevation 755' is sloped to collect roof drainage at four locations. The roof drains are sized for 3 inches per hour of precipitation. The roof drains of the new building are connected to the existing plant drains and the roof slab does not have curbs.
'Because of the flat roof construction, and lack of parapet and curbs, the water will run off the roof from the sides if the intensity of precipitation should exceed the design intensity or if There will be no ponding on the roof drains should get plugged.
the roof slab except for a very shallow trough created for the roof drainage. The design wind speed is 100 mph. Wind pressure, shape factors, gast f actors and. variation of winds with height shall be determined in accordance with the procedures given in the American Society of Civil Engineers, (ASCE) paper No. -3269 '" Wind Forces on Structures", Transactions of the American Society of Civil Engineers, Vol. 326, Part II (1961)4 4.3.1.7 -Tornado Loads (K) (Ref. Regulatory Guide 1.76) Tornado loadings used in the design will consist of the following:
- a. A lateral force caused by a funnel of wind having a rotational speed of 290 mph and a maximum translation speed of 70 mph.
b.'A pressure drop of 3.0 psi, the rate of pressure drop being 2.0 psi /sec.
- c. The design tornado generated missiles as shown on Table B.
These . tornado, wind and missile loads represent current NRC
. guidance and were used in place of those from the USAR.
76
~
Rev. 1 4.3.1.8 Seismic Loads The following seismic loads will be used in the design.
- a. Operating Basic Earthquake (OBE) (E)
The Operating Basis Earthquake loads based upon a maximum horizontal and vertical ground acceleration of 0.06g.
- b. Safe Shutdown Earthquake (SSE) (E')
The Safe Shutdown- Earthquake -loads based upon a maximum
-horizontal ground acceleration of 0.12g.
- c. Uniform Building Code Earthquake Loads All structures that are not required to be designed for OBE or SSE loads as-shown above, will be designed in accordance with the requirements of the Uniform Building Code. This code specifies the location of the plant site to be in a "Zero" earthquake area. However, for conservatism earthquake loads applicable to Zone 1 areas will be used in the design under this
. category.
4'.3. 1.9 ' Temperature Loads (To or Ta) Thermal effects and loads during normal operating or shutdown conditions, based on the-most critical transient or steady state condition. 4.3.1.10 Pipe Reaction Loads (Ro or Ra) Pipe reactions during normal operating or shutdown conditions, based on the most critical transient or steady state condition. 4.3.? 11 High Energy Pipe Break Loads The only system in the D5/D6 Building which is considered a high inergy line is the Diesel Generator Air Start system. The Piesel Generator Air Start system was evaluated against the guidance of Standard Review Plan ~3.6.1 and 3.6.2. Branch Technical Position MEB 3-1, " Postulated Rupture Locations in Fluid System Piping Inside and outside Containment," indicates that circumferential breaks should be postulated in fluid system piping runs exceeding a nominal pipe size of one inch. The air start piping runs do not exceed one inch; therefore, circumferential -breaks are not postulated. Similarly, longitudinal breaks should be postulated in piping runs exceeding four inches nominal pipe size. The air start piping runs do not exceed this criterion therefore no high energy pipe creak loads need to be considered in the design. Therefore, no 'aigh - energy pipe break loads need to be considered in the design. 77
- l Rev. 1 A' leakage crack in the air start piping may result in the blowdown of a single air receiver. However, as stated in Section 3.3. 3.1 of j the SBO/ESU Design Report, only two of the four receiver bottles l are required to start.the diesel generator. In addition, the leakage of air will not result in an adverse environment in the diesel generator room.
4.3.2 Etructural Desian Basis j 4.3.2.1 General
.All steel structures will be designed by the elastic *iorking stress method. All reinforced concrete structures will be designed using the Ultimate Strength Design (USD) method.
Under normal loading conditions, a minimum factor of safety will be provided for all structures as shown below: Overturning: 1.50 Sliding: 1.50 Buoyancy 1.25 l Minimum' factor of safety for buoyancy under design flood conditions will be 1.1 (SRP 3.8.5). Design characteristics assumed for the various materials used are stated in Section 4.3.3 " Construction Materials". 4.3.2.2 Safety Related Structures
-1. Seismic Design
- a. General The building will be modeled as'a three dimensional finite element lumped mass model. The soil will be represented by six spring elements. The computer program STARDYNE.will be used for modal' integration to obtain floor response, acceleration time histories and subsequent gcneration of
, the floor response acceleration spectra. The spectral acceleration will be used for the design of the floor slabs and the procurement of equipment based on their design classification. The codal responses obtained from ' the spectral analysis will be combined in accordance with the Regulatory Guide 1.92. All three components of seismic accelerations, two horizontal and one vertical component, will be considered to act simultaneously. The spatial components will be combined by the Square Root of Sum of Squares (SRSS) method,
- b. Design Input Response Spectra l
Input horizontal and vertical seismic spectra for the seismic design of the DS/D6 Building will be based on the 78
l Rev, 1 Regulatory Guide 1.60 Rev. 1, July 1981 spectra for a . maximum ground acceleration (zero period acceleration) of 0.06g for the Operating Basis Earthquake (OBE) and 0.12g for the Safe Shutdown Earthquake (SSE). These zero period accoleration values are in compliance with the PI Nuclear Generating Plant Updated Safety l Analysis Report.
- c. Time Histories Acceleration time histories for the three directions of motion (two horizontal and one vertical) will be developed using the reverse shock spectrum feature (DYNRE 7) of the STARDYNE MICRO computer program. These time histories will be developed independently for the three directions using randomly generated input values by iteratively adjusting the frequency content so as to match the resulting response spectrum with the design response spectrum for a chosen damping value. Comparison of the resulting spectra for various damping values with the corresponding OBE input design response spectra curves will be done to ensure acceptability of the final time histories. The requirement of SRP 3.7.1 for the enveloping criteria will be satisfied.
No separate SSE time histories will be developed. The OPE response spectra values will be doubled to obtain corresponding SSE values. These time histories will be used as input motion for the mathematical model to generate response spectra for all floors.
- d. Critical Damping Values The. percentage'of critical damping-values for the.OBE and SSE levels used in the analyses will be in accordance with Reg. Guide 1.61, October 1973. These values will be used for seismic qualification of equipment and systems.
The values for material and radiation damping within the soil medium will be taken as 10 percent of critical damping for the translational (3 directions) ,' rocking and torsional motions of the building structure. These values will be
-the same for both OBE and SSE levels.
- e. Soil-Structure Interaction Soil-structure interaction will beuse accounted of soil forsprings in the seismic- analyses through the representing the six degrees of freedom (three translations and three rotations) of the rigid foundation mat. Soil Spring constants will be computed using the formalas. given in " Design Procedures for Dynamically Loaded Foundations" by R.V. Whitman and F.E. Richart, Journal of the Soil 79
- Rev. 1-
.. . Mechanics and Foundations Division, ASCE, November, 1967.
Material properties used in these formulas will be taken from the John A. Blume & Associates Report / JAB-PS-02 which provided the basis for the original seismic design for Prairie Island. The set of six springs will be placed at the-mass center of the foundation slab. The ground motion time histories will'be applied directly at the base of the foundation slab,
- f. Interaction with Existing Structures The D5/D6 Building and its foundatior, are physically separated from the existing plant structures. The gap filled with compressible material between the D5/D6 Building and the adjacent structures will be sized to avoid a contact of the two structures for the maximum out-of-phase motions.
- g. Mathematical Model The dynamic model will consist- of several " sticks" representing the ' shear walls with nodes at each floor level. Each of these nodes will be . connected by rigid link, representing the rigid diaphragm action of the. floor slab.
The shear areas and moments of inertia of the concrete walls between floors will be used to calculate the stiffness characteristics of the elements between nodes of the individual wall " stick". The foundation slab will be treated as a rigid member for in-plane and out-of-plane motions. In order to incorporate the effect of the actual floor slab stiffness on the vertical response spectra, vertical spring mass systems will be attached, at the center of mass of each floor to represent the vertical flexibility- -of the slab at that elevatic n. The slab mass along with the equipment loads will represent the mass o. the spring-mass system. This will be done by sole.ing the problem twice, once with the lowest flexibility of the slab and second with the highest flexibility. This will provide an enveloping spectrum. Composite behavior of the concrete slab and steel beams will be considered in the computation of the spring constants, where appropriate. ,
- h. Spectral Peak Broadening The spectral accelerations obtained from the STARDYNE l program will be smoothed and its frequency 'at peak acceleration will be broadened ( 15%) in accordance with the requirements of Regulatory Guide 1.122, Rev. 1.
80 l
k-Rev.* 1
- 2. Tornado-Winds Structures will be analyzed for stresses due to tornado and missile loads. Stresses due to tornado loading will be combined with stresses due to dead loads and operating loads to obtain total stress. Maximum stresses will be limited to those specified in Section 4.3.6.
- 3. Design for Missiles i i
- a. Externally Generated Missiles ;
Missiles shown in Table 4-B will be considered for design. All tornado generated missiles will be assumed to impact 1 end on at 90 degrees to the surface being impacted and all areas of Safety Related structures exposed to either falling or horizontally flying tornado missiles will be investigated. In.accordance with SRP 3.5.3, Local Damage of Barriers (Penetration, Spa? ling and Scabbing Effects) and their overall response is investigated. Where elasto-plastic behavior of steel barriers is relied upon, a maximum ductility' ratio of 20 is used.
- b. Internally Generated Missiles The safety related portions of the diesel engine auxiliary support systems are all located within the new D5/D6 building and the attached underground fuel oil storage vaults. These structures hre located outside of the
~ turbine missile trajectories defined in Figures 12.2-36 and 12.2-37 of the Prairie Island USAR. Therefore, the auxiliary systems are not subject to turbine missiles.-
The only potential missile sources within the 05/D6 outuing are the diesel generators themselves. The diesel generators are each surrounded by reinforced concrete barriers ranging . from 12 to 20 ~ inches thick. The two trains of auxiliary support systems are also completaly separated by these protective barriers. The design, fabrication, and inspection of the SACM engine block, connecting rods, cylinder liners and pistons is performed to ensure that there are no catastrophic failures which could generate missiles. During more than 57,000 hours of operation of over 250 diesel generator sets 'in nuclear power - plants around the world, SACM engines have never experienced. a failure resulting in internally generated , missiles. In addition, the diesel engine overspeed trip logic is configured such that an overspeed signal in either of the two tandem engines will result in a trip signal to-both engines. This redundancy ensures the rcliability of l l the overspeed trip function. 81 _ . . ~ _ _ _ _ _ ,~ _ . -- - _
1 . \ ' Rev. 1
. The design provisions and operating experience described above ensure that the safety related diesel auxiliary support systems are protected from internally generated missiles.
The only piping within the DS/D6 building which is considered high energy is the diesel generator air start system piping. This piping is not subject to breaks whicn could damage the diesel auxiliary support systems due to pipe whip or jet impingement, as discussed in 4.3.1.11.
- 4. Flood Protection The Diesel Generator Building Structure will be protected against the probable maximum flood at an elevation of 703'7".
The base slab and the exterior walls will be designed to resist the full hydrostatic head of the probable maximam flood. Except for the exit doors, all openings to the exterior wall will be above elevation 705' 0" . All mat and exterior wall construction joints below elevation 705' 0" will have water stops. In the event of a design basis flood, exit door openings through the exterior walls will be protected by water tight bulkhead closures. 4.3.2.3 Non-Safety Related Structures Structures in this class are designed for the conditions of loading specified in Section 4.3.4.2 and in accordance with the design methods and allowable stresses specified in the codes. Stresses are combined as before and reviewed to assure that they are within limits. 4.3.3 Construction Materials The principal construction materials for Safety Related structures are: concrete, reinforcing steel and structural steel. Concrete design compressive strength will be as follows: All structures 4000 psi Mud slab and concrete fill 2000 psi Reinforcing steel will be deformed billet steel, conforming to ASTM Designation A-615, grade 60. Structural steel will conform to ASTM designation A-36 or ' A-572 G nde 50. 4.3.4 Lead Combinations The following loads and loading combinations will be used in the design and. analysis. 82 )
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. I Rev. 1 l 4.3.6.1. Safety Related Structures Safety related structures will be analyzed for the following conditions of loading:
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- 1. Load-Combinations for Concrete Structures (Ref. SRP 3.B.4)
For concrete structures using ultimate strength design method, the load combinations will be in accordance with the following: For normal / service load conditions, the following load combinations will be considered: (1) 1. 4 D + 1. 7 L (2) 1.4 D + 1.7 Lo + 1.9 E (3) 1.4 D + 1.7 L + 1.7 W Where thermal stresses due to' To and R. are present, the following combinations shall be considered: (4) ( 0. 7 5) (1.4D + 1.7L + 1.7To . + 1. 7Ro) (5) (0.75) (1.4D + 1.7Lo + 1.9E + 1.7T o+ 1. 7Ro) (6) (0.75) (1.4D + 1.7L + 1.7W + 1.7To + 1. 7 R ) InLaddition, the following combinations will be considered: (7)_ 1.2 D + 1.9 E (8) ~1.2 D + 1.7 W For factored load conditions which represent extreme
-environmental, abnormal, abnormal / severe environmental, and abnormal / extreme environmental conditions, the following load combinations will be considered.
(9) D + Lo . & oT + E' (10) D + L, + To + Ro + W, (11) D.+ Lo + T. + R, + 1. 5 P. ' (12) D + L, + T + R, + 1. 2 5 P + 1. 0 (Y, + Y + Ym) . + 1.25E 3 (13) D+Lo + T. + R, + 1. 0 P. + 1. 0 (Y, + Yj + - Ym) + 1. 0E ' In combinations (11) , (12 ) , and _ (13 ) , the maximum values of P., Yj, Y,, and-Y , including an appropriate dynamic load T., R., factor will be used unless a time-history analysis is performed to justify otherwise. Combinations (10) and (12) and (13) and the corresponding structural acceptance criteria of- Section 4.3.6 will be satisfied first without the tornado missile' load in '(10) and without Y,, Y, and Y, in (12) and (13). When 3 l L considering these concentrated loads local section strength L, capacities may be exceeded provided there is no loss of function of any safety-related system. any reduces the effects of other loads, the Where load corresponding coefficient for that load will be taken as 0.9 if 1 83 l l
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. Rev. 1 1 it can be demonstrated that the load is always present or occurs !
simultaneously with other loads. Otherwise the coefficient for that load will be taken as a zero.
- 2. Load Combinations for Steel Structur<is (Ref. SRP 3.8.4) !
For steel interior struct2res using elastic working stress design' methods, the load combinations will be in accordance with the following: For normal / service load conditions, the following load conditions will be considered: (1) D+L (2) D + L, + E (3) D+L+W If thermal stresses due to To and R are present, the following l- combinations will be also considered:
.(4) D+L+To + R.
(5) D + Lo + To + Ro +E (6) D+L+T o +R o +W-For f actored load conditions the following load combinations will be considered: (7) D+L +o To + R o + E' (8) D + L,3 + - To + R o +Wi
.(9)' D+L + o T,a + R, + ' P.
(10) D+Lo + T. + R, + P + 1. 0 ( Y, + Yi+ Y.) +E (11) D+L + o T, + R, + P. + 1. 0 ( Y, + Y3+ Y) + E' In the above factored load combinations, thermal loads can be selected when.it can be shown that they are secondary and self-limiting in nature and where the material.is ductile.. In combinations.(9), (10), and (11), the maximum values of P., T.,- R., Yj , Y, and Ym, including an appropriate dynamic load f actor will be used unless a time-history analysis is performed to
-justify otherwisc. Combinations . (8) , '(10) and (11) and the corresponding structural acceptance criteria of Section 4.3.6 will first be satisfied without the tornado missile ad in (8)
'and without Y, , - Yj , and Y, in (10) and (11). When considering
'these concentrated loads, local section strength may be exceeded provided there . will be no loss of function of any safety-related~ system.
Where any load. reduces the effects of other loads, the corresponding coefficient for that load will be taken as 0.9, if it can be demonstrated that the load is always present or occurs simultaneously with other loads, otherwise, the coefficient for j that load-will be taken as zero. 84
4 Rev. 1 Where the structural effect of differential settlement may be . significant, it shall be included with the dead load, D. 4.3~.4.2- Non-Safety Related Structures Non-safety related structures will be designed for the greater of the following two combinations of loads:
- 1. Dead, Live and Environmental loads (wind ce snow) or
- 2. Dead, Live and Uniform Building Code Earthquake loads specified in Section 4.3.1.8 which for the Prairie Island site is 0.05g (Ref. USAR Sec. 12)
~4.3.5 Desian and Analysis Procedures The design and analysis procedures utilized for structures, including assumptions on boundary conditions and expected behavior '
under loads, will-be in accordance with the following:
- a. For safety related concrete structures, the procedures will be
-in accordance with ACI 349-85, " Code Requirements for Nuclear Safety Related Structures".
- b. For non-safety related concrete structures, the procedures will be in accordance with either ACI 349-85 or ACI 318-83.
- c. For steel structures, the procedures will be in accordance with the AISC Specificatior., eighth edition.
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Rev. 1 4.3.6 H.f;.rustMra1 AcG.RP10DC3; _CritstiA -(Ref- S RP 3 - 8 . 41,. For each ok.' the loading combinations delineated in section 4.3.4.1 of this criteria, the '.c11owing defines the allruable limits which constitute the structural acceptance criteria i
- a. In combinationa_fpy_q.oncreto Limit )
All Load Combinations U
- b. In Combinationp_,f,2r Steel Limit Load Combinations (1), (2), (3) S j Load Combinations (4), (5), (G) 1.5 S Load Combinations (7), (8), (9) 1.6 S*
Load Combinations (10), (11) 1.7 S* Notest. i S- For struct. ural steel, S is the required section strength based on elastic design methods and the allowable stresses defined in part.1 of the AIGC " Specification for the Design, Fabrication, and Erection of Structural Steel for Buildings" The 1/3-increase in allowable stresnes for steel due te seismic or wind loadings is not permitted. U For concrete dructures, U is the section strength required to ' resist design loads based on the strength design .metnods described in ACI 349 Code. ;
- For these two combinations, in couputing the required section strength, S, the plastic.section modulus of steel shapes, except for those which do not meet the AISC criteria for compact sections, may be used.
4.3.7 S.t;nycturdl/ ArglLilectural Fire Protect;.19.n Rqguirementa 4.3.7.1 Separation Barriers diesel. Gencrators will be separated from each other and the temainder of the plant by reinforced concrete walls having a fire rating of at least 3-hours. In light of its proximity to the Turbine Bu.1 ding and Auxiliary Building, the east wall and a 8 portion of the - north wall are also ~;-hour fire rated. All > penetrations in fire wallu sil be 3-hour fire rated. Each redundant 6.lectrical train will we separated by 3-hour rated' fire barriers. 'the pipe trench running through both fire areas on the gr:.de leve] will be separated from the remainder of the building , area by a 3-hour rated bLrrier. Fire barriers are listed in, Table ! .4-C. Fire doors of equivalent rating will be provided in fire
- walls.
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1 Rev. 1 4.3.7.2 Fire Area Soundaries and Penetrations . Cable and cable tray penetrations as well as piping and ventilation duct penetrations through fire area boundaries, will be scaled with a penetration seal having a 3-hour fire rating. Adequacy of these sesla was previously demonstrated by fire tests conducted in accordancu with ~2EE C 4-1978 by Southitest Pescarch Institute (test reports SWRT 03-1402/ Quadrax-!!OR-0176 and NOR-0179, PO 5364). The die.sel fuel oil day tank and the lube oil storage tank room era cach contained in a separate room constructed of reinforced concrete with 3-hour fire rated walls, floor and ceiling. Room doors and fire dampers in ventilation ducts are fire rated for 3-bours. All penetrationa through the room boundaries that are fire area boundaries are sealed with three hour penetration seals. Floor drains and curbs are provided for each room which discharge into the building sump pit. In high intensity fire areas, all structural steel forming a part of or supporting a fire barrier wall or slab will be coated with fire proofing material to provide a fire rating equal or greater than the fire barrier. 4.3.8 jlg1Mina Ext.gI191_,Oneninas All building exterior openings except exit doors will be protected from access by access-controlled Security Devices. These opnnings will be protected frore tornado generated missiles. All openings that serve at inlet or outlet for HVAC Systems, will be provided with screens to preclude entry of birds, leaves and other debris. 4.4 BUILDING ELECTRICAL DESIGN 4.4.1 Ligitting 4.4.1.1 System Functions Lighting for the new DS/D6 Building is provided by two systems. 1., llormal Lighting System FInction This system will provide general and local illumination for oo rating and maintenanen activities.
- 2. Emergency Lighting System Function This lighting will provido protection of personnel and allow continued safe plant operation in the event of normal lighting failure. It will consist of fixed self-contalned battery pack lighting.
Fixe.d self-contained lighting with individual 8-hour minimum battery power supplies will be provided in areas that must bc 87
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- Rev. 1 e manned for safe shutdown (in the event of a firo) and for access and egress routes to these areas.
4.4.1.2 System Design
- 1. General System The type of fixture and foot candle requirements for the various areas of-the new Building will be as required by NFPA 70 and in accordance with the guidelines of the Illuminating Engineering Society (IES) Handbook.
Conduit for lighting systems will be run embedded and exposed, and-grounded. Separated conduit system will be provided for thn 277V, normal lighting and 120V receptacles which pruvide power to and emergency lighting units. All lighting fixtures are to be pendant or surface nounted. Lighting wire insulation will be type XfUN, rated 90*C. t Seoarate neutrals will be run with each phase of branch circuits. A common neutral will be run with each 3-phase f eeder
' circuit, Full-of.ze neutrals will be used for feedor and branch circuits.
The combined - voltage drop of both feeder and branch circuits will not exceed 5%. Lighting _ wires will be labeled.as to pane 2 and circuit.
- 2. Normal Lighting System Normal lighting fixtures will be 277V fluorescent, HP sodium or metal halide and'120V incandescent.
Fixtures will be switched from the lighting panelboard, using molded case circuit breakers rated for switching duty. l l The. normal lighting panels will be 480/277V, 3-phase, 4-wire fed L from--two new normal McC's in the new diesel. building. . 1
- 3. Emergency Lighting and. Exit Signs System Emergency lighting will be incandescent and provided with self-contained 8-hour rated battery packs.
Exit lights will' be incandescent and provided with self-contained 8-hour rated battery packs. L 88
4 Revs 1 4.4.2 Power Distributi.gp_3nd Loacig 4 4.2.1 System runction The power distribution system will provide electrical energy to all ncn-Class 1E building loads, including lighting cyctoms, . communication, security and fire detection systems, convenience outlets and miscellaneous building equipment. Normal (non-safeguards) 480 VAC electrical power to serve building loads will be obtained from normal 480V motor control centers. The building normal power distribution system will consist of motor control centers, transformers, distribution panel.a and associated cable and raceway systems. Safeguards 480 VAC electrical power will be obtained from new safeguards motor control centers and 480V switchgear in the D5/D6 Building for the safety-related HVAC cystems and dansel generator support systems' . This portion of the power distribution system will be Class lE. 4.4.2.2 System Design Electrical ~ power distribution will be acconplished by means of a 4 80 VAC, 3-phasu, 4-wire, solidly grounded system. Transformations from this service to 120 and 208 V AC will be provided by panel , boards mounted in motor control centers. - Electrical' supply equipment will have the capacity to supply tne power requirements of all identified and anticipated loads plus r spare capacity for future loads. All components of the power distribution system'will be rated for 600V AC and be suitable for. application inLa typical industrial environment. The non-safety building electrical power distribution system will be electrically and physically independent from all safety-related systems. Segregation will also be provided between different voltage classes. Non-Class 1E circuits for lighting, communication, fire detection and security systems.are routed in totally enclosed raceway and cable . for these systems need not comply with . IEEE _383. . The j remaining non-Class 1E circuits will use fire resistant cable which j has pas. sed the fire- tests contained in IEEE 383 on UL VW-1 and is Class 1E qualified cable. j overcurrent protection will be provided by means of molded-case thermal-m.lgnetic circuit breakers. Proper coordination of all overcurrent protection devices will be provided down to (and including) local panelboard(s), in accordance with IEEE Std. 242- l 1975. 89
- Rev. 1 ,
. Transformers, disconnect switches, lighting panels, receptacle m,
panels and receptacles will be surface or floor mounted. The receptacle panels will be 120/208V, three-phase, four wire , stepped down from a 480-120/208V transformer. Power receptacles will be 120V AC, duplex with no covers, except that in the diesel pit, radiator room, air inlet room and generator room weather proof covers will be used. Welding receptacles (minimum of 4) will be, 480V, 3-phase, 4 wire. 4.4.3 Gr_Q1tns11tig
]
The electrical power distribution system will be solidly grounded , to the existing Station ground network. Load equipment, power supplies, raceways, and enclosures will be electrict. ly interconnected and form a continuous path to Station '7 ground. An addition, all load equipment will be grounded by means of a separate ground conductor routed with the circuit conductors.
-4.4.4 Communications ,
4.4.4.1 System Function . This system will provide dependable, convenient and rapid cc,mmunication between all plant araas vital to the operation and ' maintenance of the plant and the protection of personnel. The
. existing conununications system-will be extended te the new diesel generator building. .
4 4.4.2 System Design The communications system will consist of: l' ~ Telephone system insta.11ed by an independent telephone contractor.
- Page/Public Address System (Gai-tronics)
!_ - A visual signaling device will be provided in the diesel engine l- rooms to indicate plant alarm actuation. Flashing '.ights in the noisy areas (Diesel Engine Rooms) will supplement the PA system in these areas. l
- Maintenance (sound powered) sl stem.
': 4.4.5 F i r e D q t,q pjil ,Q,n ; 4.4.5.1 System Function This system will detect and alarm in case of fire. The detection devices will be appropriate to the specific area and the type of 90
- - _- _ . - . _ . _ . . - . . - - . ~ - . , . . _. .-. -,-
4
. l Reva 1 fire _ anticipated. All detection equipment will alarm on the fire .
detection panel in the main uontrol room. only one alarm will be sent to the Main control Room for the entire 4 Diesel Generator Building. The fire detection panul will be i located on the turbine building side of the north wall of the stairway. There will be no connection between the HVAC system and the fire alarm system. No HVAC smoke control system will be provided. Manual pull stations will be provided at the main exits. 4.4.5.2 System Design l Fire detectors for the diesel generator will be heat detectors that l will be single zoned and wired to activate a pre-action sprinkler i
$ystem for each diesel. All other rooms in the diesel building I will have smoke detectors installed.
All fire alarm wiring will be supervised. A single zone will be provided-in the control room for the entire building. The fire alarm and pra-action control panol will be located on the turbine side of the north diesel generator wall. Electrical power . will be supplied by an existing non-safeguardn 120V AC UPS source. Manual fire alarm pull stations will be located at the main exits. 4.4.6 Secutity security for the new D3/D6 Building is provided by three systems. .
- 1. Building Security Systen The building security system will provide protection from unauthorized access into the building. The security system will have the capability to monitor, alarm, store data and generate reports pertinent to personnel acceus/ egress into the building.
This system will function -during normal plant operation and during loss of off-site power but is not required to operate following a design basis accident or safe shutdown earthquake. The. building security syste.m will consist of card readers, electric door strikes, position switches, security lighting and cables to interface with the existing plant security system. Normal entrance / exit doors will be monitored and controlled by the plant security computer. Operation of emergency oxit doors will be monitored and alarued.
- 2. Security Lighting System The building's external lighting systen will satisfy the plant security illumination requirements in accordance with the Prairie Island Security Plan.
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- i Rev. 1 l l
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- 3. Security Fence System The new 05/06 Building and Fuel Oil Storage Vault will be locat.ed entirely within the existing protected area security fence. During construction, a temporary construction guardhouse located at the southwent corner of the existing protected area security fence will be utilized. .
l 4.4.7 Badiatiqn Monitorina l radiation monitors will beinputlocated in the DS/D6 l Three area ! Building. Each monitor alarm will be an to the existing area radiation monitoring panoin in the Control Rod Drive Rooms and the j Emergency Response Computer System. I i 4.5 BUILDING MECILANICAL/HVAC DESIGN i 4.5.1 Eirs Protection Desian An automatic pre-action firc. suppression system will protect the diesel engine rooms. The fuel oil tank day tank and lube Other oil tank areas rooms will have wet pipe automatic sprinkler cystems. > will be protected with standpipe hose stations and hand-held extinguishers as required by NFPA 10 portable Fire Extinguishern. The fire suppression system piping will be supplied from a new
- bulk main from the Turbine Building Fire Protection loop.
following areas will be provided' with autome.::ic fire The suppression in compliance with NFPA, ANI and NRC requirements.
- 1. D5 and D6 Diesel Generator Rooma 2.-Fuel Oil Day Tank Rooms
- 3. Lube Oil Storage Tank Rooms
- 4. Outdoor Fuel Oil Receiving-Tank The diesel generator rooms will each have a single interlocked pre-action sprinkler system.- Activation of the system will be by a is wired - into the local single zone heat fire alarm control panel. detection circuit thatOutput from the panel will be 24V DC to the fire detectors. The sprinkler riser will be separate from the standpipe station riser.
Three new feed mains and indicating isolation valves will be added to the existing Turbine Building 10-inch fire protection loop; one one to supply the to supply the station system standpipe riser; preaction and wet - pipe systems; and one to supply the . deluge flexibility for- removing system. This' arrangement provides - individual systems from serv ue for maintenance.
- l. Preaction Sprinkler System An automatic preaction fusible-link sprinkler system
~
will be The preaction , provided for each emergency diesel generator. 92 9
Rev4 1 t valve will be tripped by a sing.Le zoned heat detection circuit. . Piping will be supervised by air pressure with trouble signals annunciated at the local fire alarm control panel and the fire alarm control parel in the control room. 2.-Wet-Pipe Sprinkler System Each Puel Oil Day Tank Room and Lube Oil Room will be provided with an automatic wet pipe sprinkler system that will have its flow alarm wired into the fire alarm system.
- 3. Delugo System The Fuel 011 Receiving Tank will be protected by an automatic deluge system tripped by a single zoned heat detection circuit.
- 4. Hose Stations 1-1/2 inch hose stations with proper length of fire hose with fog nozzles will be provided to protect all areas on each elevation.
- 5. Fire Extinguishers Dry chemical or carbon dioxide fire extinguishers will be provided to protect all areas of the Diesel Generator Building depending on the specific hazard.
- 6. Sprinkler Systems and Hose Stations Sprinkler systems and hose stations will be provided eith separate risers such that primary or secondary protection will always be available. Hose stations in electrical equipment areas intended for electrical fires vill,be equipped with low-flow "og nozzles. :
f Sprinklero in stairways are not required by NFPA and will not be provided in the DS/D6 Building. . A fire suppression system is not required for the Fuel Oil storage Tank Vault.per code. 4.5.2 . 6umbincr / Dra ing ,
.4'.0fa.1 System Function Demir.oralized water hose stations for washdown in mechanical equipment areas will be furnished. Lavatories will not be provided due to the teuiporary habitaticn of this structure.
The building will be provided with convenient floor drains to route ,
.all note.al drains and oily waste spills to two separate sumps in '
each diesel generator room. The sumps will be sized to contain the maximum quantity of oily waste spills corresponding to the capacity 93 1 v ,,,c , .. ,,~,,,-.- -, ,.,,w- . - - - - r ,c- - -
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" Rev. 1
- of the single largest system and will be sized to accommodato credible water pipe breaks. Portable sump pumpo will be used for transfer of oil spills or water collected in the sumps.
4.S.2.2 System Design plumbing system drain piping will be designed to meet the American Water Works Association (AWWA) and other appropriate building codes and industrial standards, consistent with existing prairie Island plant systems. Service water for the hose stations will be provided from a tie to the Unit 2 Turbine Building. Potable water piping for future battery room eyewashes will also be from a Unit 2 tie-in. A waste discharge line will connect to the Unit 2 Turbine Building waste system which will toute to the olant hold-up pond. Roof drain piping and drain piping in the diesel generator radiator exhaust open area will connect to the cooling water return line in the main plant. All other general area drain piping will run to the D5/06 Duilding sump in the engine room pit area, eucept floor drains in the lube oil tank rooms and the fuel day tank rooms. Floor drains in the lube oil tank room a7d the fuel oil day tank rooms will run to the dirty oil tank located in the respective D5/D6 Building engine room pit area. Overflow piping from the dirty oil tanks will run to the D5/D6 Building oil sump located in the engine room pit areas. The building sumps are located in the diesel engine pit aruac. A portable sump pump will be used to transfer oil from the sumps to barrels for removal. The sumps will be provided with level switches to alarm high liquid level condition in the D5/06 control room, with a common trouble alarm in the main control room. Fire suppression water discharged in the diesel grating, pipe generator room will flow to the basement area through open sleeves and an access hatch. Assuming that all sprinkler heada and two hose stations (total 1500 gpm) discharge water for a period of 30 minutes, approximately 2.3 feet of water would accumulate in the basement. When the fire is extinguished and the preaction system isolated by operator action, the water would be removed from the basement by use of portable pumps. 4.5.3 11gjlLtina VegiLqti2n. and Air Conditionino J)JV!AC) 4.5.3.1 System Function The DS/D6 Building HVAC System will provide heating and ventilation and will provide for removal of electrical equipment heat loads to maintain equipment within qualification limits and operating limits during all plant operating conditions. It will also provide sufficient air fisw to prevent build-up of unwanted gases. The DS/D6 Building HVAC system will be conprised of the following subsystems for each diesel generator train: 94 ; i
Rev. 1 l o Lube Oil Storage Tank and Fuel Oil Day Tank Rooms Exhaust System , o Battery Room !!cating, Cooling, and Ventilation System (Future) o Emergency Equipment Switchgear Areas Ventilation System , o Diesel Generator Control Room and Switchgear Area Auxiliary cooling System o Local Electric Unit !! eaters The liVAC system controls will consist of temperature seasors, i temperature switches, controllers and damper control drives to l control air flows in order to maintain required temperatures in the building. Fans will ba operated by control switches with interlocks with their corresponding dampera and temperature sensors. Operating temperatures will be monitored and alarmed. Ductwork, wall, ceiling and floor openings will be provided to ' allow the later addition of a Battary Room Heating, Cooling, and Ventilation System.
!4.5.3.2 System Design The HVAC system capacities are based on an outdoor ambient temperature range of 96*F and -2 0*F. This is the 99% occurrence range from ASHRAE. The HVAC steady state heat load calculations do not.take credit for-passive heat sinks (concret walls and floors) and thermal lag. Therefore, the ITVAC design condition's are conservative, and brief upper temperature excursions up to 100*F for a few hours will not significantly affect electrical equipment operability.
The vertical benchboard and control panels in the diesel generator control- room must be maintained during all plant operating The HVAC system will conditions at a - temperature less- than 104 F. be designed to maintain component operating temperatures. A forced-air ventilation-system for each train will be provided to meet the equipment heat removal and fresh air ventilation needs of various areas serving each diesel generator.
- 1. Tank Rooms The Diesel Lube Oil Storage Tank Rooms and Fuel Oil Day Tank Rooms each have a minimum ventilation requirement of 1 cfm per square foot of floor area (minimum 150 cfm) on a year round l
, basis in order to prevent possible build-up of a flammable atmosphere (NFPA30). 2 Make-Up Air . .
.he make-up air for the Diesel Lube Oil Storage Tank Rooms and t~
- j. Fuel Oil Day Tank Rooms will be from the common building ventilation supply headers. The maximum indoor ambient l temperature will be limited t.o be 12 0 F . The -minimum l tcmperature will be limited to 50*F.
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. 3. Exhaust Air All exhaust air flows will be discharged to the outside atmosphere.
- 4. Control Room T. Electrical Equipment Ventilation The incoming air supplied by the main vent to the control room and electrical areas will be rough filtered.
The safety related ventilation system for the 05/D6 Control Room and electrical equipment areas will be designed to limit ambient critical room temperatures to 104*F without supplemental cooling. Outside air will be supplied to the area by one normally operating vano axial fanProvisions with an installed, for mixing outside operator celectable back-up f an provided. air with recirculated air will beThe made supply to limitair will thebeminimum filtered supply air temperature to 50*F. by a roughing filter. The Control Rooms and 480V switchgear areas will each be provided with a direct expansion type mechanical cooling system f or non-saf ety related auxiliary :ooling. Each cooling system will consist of an outdoor compt.ssor/ condenser unit, a roo*- mounted evaporator / fan unit to circulate room air, and the interconnecting Froon-12 tubing, control equipment and poeter supply. Fresh air will be provided to the rooms f rom the common ventilation systen independent of this system.
- 5. Temperature Control Temperature control will be accomplished by modulating dampers in the air supply ducts in responseClass to signals from room 1E power for these temperature ceasors and controllers.
dampers and th t associated instruments and controls is supplied from class 1E MCC panel boards which is interruptible. Claus 1E power for all other safety related instruments will be obtained from existing plant all other safety related 120V AC UPS distribution system. ;;on-1E power for rnn-safety related instrumentation will be obtTined from existing plant 120V AC UPS distribution system. High room temperature will be alarmed in the Diesel Generator control room, with a common trouble alarm f in the main control room.
- 6. HVAC Capacities Capacities of individual system ventilation design fans and all other drawings or components will be indicated on specifications.
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- 7. HVAC Electrical Equipment All safety related electrical equipment for the Diesel Generator Building HVAC S. ma will be powered from engineered safety features busns.
- 8. Heating Syctem The heating system will be designed to maintain spaces at a minimum temperature of 50*F.
- 9. Ventilation and Exhaust Fans D5/D6 Building supply and exhaust fans will be vane axial type with direct-drive TEAO motors. Two 100% capacity supply fans and two 100% capacity exhaust fans per train will be proyided.
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- 10. HVAC Hissile Protection All components of cach ventilation system will be protected from tornado generated missiles. The building ventilation intakes and exhausts will be missile protected.
- 11. Fire Protection Firo dampers of 3-hour fire rating will be provided in all
' openings penetrating 3-hour fire rated walls / floors,' ceilings.
No connection exists between the HVAC system and the fire alarm system. Smoke venting will be provided utilizing portable fans. l Operator action is required to shut-down the HVAC systen when necessary during a fire.
- 12. HVAC Intake and Exhaust Elevation The intake and exhaust openings for the Emergency D5/06 Building Ventilation System will be located at an elevation higher than the maximum probable flood level.
Intake openings will be located at an elevation sufficiently below the turbine building and diesel generator axhausts to prevent exhaust gas recirculation intake, i 13. Fail Safe System The HVAC dampers will fail to a safe position (i.e., a position which' permits flow to safety related areas) on loss of normal /safegaards AC Power. lu. Strt Nural Design Safety related HVAC systems were analyzed using the applicable 4 load combinations and allowable stresses from the AISC
" Specification for the Decign, Fabrication and Erection -of 97 i I
l
Rev. 1 l Structural Steel for Buildings," Ninth Edition. The seismic spectra _for 2% damping at elevation 755 feet were used in the analyuis. The largest segment of ductwork (north fan supply ducting) was analyzed, and the resulting support spans used for the remainder of the system. This design approach is conservative for the remaining ductwork, which is at the same I l elevation (south supply ducting) or lower in the building. Duct supports were qualified in a generic analysis to an upper limit design load (largest system at highest building elevation), again using ellowable stresses from the AISC Specification referenced above. This method results in I conservatively decigned supports for the remainder of the HVAC system. 1 Satety related HVAC fans are required per the purchase , specification HIAW 02707 to withstand a seismic event defined as 1 five operating Dasis Earthquake occurrences followed by a Design Basis Earthquake. 4.5.3.3 Equipment Manufacture, Inspection and Testing All ,cystem components and materials will be similar to,those previously utilized in industry and have demonstrated their reliability. r All equipment will be f actory inspected and tested in accordance ! with the applicable equipment specification. System ductwork and erection of equipment will be inspected in accordance with the design drawings and manufacturer's recommendation. System testing and balancing will be performed and evaluated prior to systen turnover. Controls on each system will be checked, adjusted and tested to ensure the proper sequence of , operations. A final, integrated pre-operational test will be ' conducted with all equipment and control., to verify system > operation. 4.5.4 . Station Air ReauirqEADj;E Station _ air for maintenance needs will be provided for the new building, serving non-safety related functions only. Thn supply of air will be from a connection to the Unit 2 station air system - operating _normally at 95 psig. Suitable maintenance hose stations will be provided where required in the new building. . 4.6- DESIGN STANDARDS The f.ollowing NURTG 0800, IEEE Standards, and Regulatory Guides are adopted 17 whole as design criteria requirements for the DS and D6 Building as de=cribed in Section 4. Within the existing plant boundary the existing design criteria as 98
Rev.' i defined in the USAR will apply except as noted otherwise in this - document. , 4.6.1 IlyREG 0800 StaDdprd ReviAw Plan (SRP) SRP 3.2.1 Rev 1, 7/81 Seismic 01assification SRP 3.2.2 Rev 1, 7/81 System Quality Group - Classification SRP 3.3.1 Rev. 2, 7/81 Wind Lordings , SRP 3.3.2 Rev. 2, 7/81 Tornado Loadings SRP 3.4.1 Rev. 2, 7/81 Flood Protection SRP 3.5.1.1 Rev. 2, 7/81 Internally Generated Missiles (outside j' e containment) SRP 3.5.1.3 Rev. 2, 7.81 Turbine Missiles (protection against turbine missiles per USAR 6.1.2.3 and 12.2.1)
'SRP 3.5.1.4 Rev. 2, 7/81 Missile Generated by National Phenomena SRP 3.5.3 Rev. 1, 7/81_ Barrier Design Procedures SRP-3.6.1-Rev. 1, 7/81 Plant Design for Protection Against Pontulated Piping Failures- in Fluid Systems outside Containment SRP 3.6.2 Rev. 1, 7/81 Determination of Rupture Loactions and Dynamic Effects Associated with the Postulated Rupture of Piping SRP 3.7.1 Rev. 1, 7/81 Seismic Design Parametero SRP 3.7.2'Rev. 1, 7/81 Seismic System Analysis SRP 3.8.4 Rev. 1, 7/81 Other Seismic Category I Structures SRP 3.8.5 Rev. 1, 7/81 Foundations ,
SRP 3.10 Rev. 2, 7/81 Seismic & Dynamic Qualification of Mcchanichl &' Electrical Equipment - 4.6.2 JJEE Standards IEEE 242-1986 Reccamended Practice for Protection and Coordination of Industrial and Commercial Puwer Systems IEEE 279-1971 Criteria for Protection Systems for Nuclear Power Generating Stations IEEE 308-1974 Criteria for Class IE Electric Systems for Nuclear Power Generating Stations IEEE~323-1974 Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations (Note: IEEE 323 is invoked as a guideline document to provide a basis for the determination of qualified life of equipment. it is not intended to be invoked as a basis for environmental qualification. 10 CFR 50.49 requirements which are l 99 i te
)
- Rev. 1 l
- met by hethedu Oncr'. bed in RG 1.89 (Endorsing IEEE
.. H do not apply t o the .aild environment of the l new D5/D6 Buildin'J.
IEEL 338-1977 Standard Criteria for tne Periodic Testing of Huclear Power Generatine; Station Safety Systems IEEE 344-1987 Guide for Seisuic Qualification of Class I Electrical Equipment. for Cuclear Power Generating l Stations j (No P.e : Seismic qual.ification for the D5/D6 Diesel j Generator, HVAC duct damper, damper actuators, und l the' Class la Motor Control Centern cites the 1975 : revision. R2f er to do':u. v entation for datails. ) . IEEE 379 -1972 Guide for the Appli. cation of the Single Failuro Criterion to Nuclear Power Generating Station Protection Systems 1EEE 303-15114 Standard for Type Test of Class 1E Electric Cables, Field Splices and Connectionn for Nuclear Power
' Genertating Stations .
IEFE 2 84-198
- Critoria for Sephratior of Class IE Equipnent and Circuits (ste note under Regulatory Guidiu 1.75)
(hJte 1: Tne 1961' revision is specified becauha it addiesues comments contained in Regulatory Guido 1.'75, Mev. 2 on ene 1974 revisior of the standard.) (Note 2. The identilication requirements ol lEEE 384 for taggit.g intervals of cable, cable tray and racoway may not be ctrictly followed. Guidance provided by the USAR will be adhered tc. as introduction of a different set of reaniraments-would be confusing. 4.6.3 ,'Reau?>di.QuGL_9.nd ,Jipqu1a_tgry _Gu1dp_q l
'10 CFR 50,' Licensing of Production and Utilization, Facilities, including all appenaject.
Occupational Safety and Health Administration (OSHA), Department of Labor, " occupational Safety and Health Standards", Title 29- Labor. Regulatory Guide 1.6, Rev. 3, 33/71 Independence Between Redundant Standby (On-site) Power Sources and Between Their Distribution Systems 9/78 Regulatory Guide 1.29, Rev. 3, l Seismic Design Classification i I 100
~
Rev. 1 ) . Regulatory Guide 1.32, Rev. 2 2/77 Critoria for Class 1E Electric Systems for Nuclear Power Generating Stations Regulatory Guide 1.38, Rev. 2, 5/77 Quality Assurance for Packaging, Shipping, Receiving, Storage and i llandling of Items for Water-Cooled Nuc1 car Power Plants / Regulatory Guido 1.53, 6/73 Application of the Cingle Failure Criteria to Muclear Power Plant Protection Systems Regulatory Guide 1.59, Rev. 2, 8/77, ERRATA '7/30/80 Design Basis Floods for Nucluar o owt,r Plants (Design Basis flood per USAR Section 2.4.5) Regulatory Guide 1.60, Rev 1, 12/73 Design Response Spectra for deisnic Design of Nuclear Pover Plants Regulatory Guide 1.61, 10/73 Damping Values for Seismic Design of.' Huclear Power Plants Regulatory 1.75, Rev. 2, 9/78 Physical Independence of Electr' Systoras c RG 1.75 p..td IEEE 384 will be met (Note 1: Separation criteria . within the new diesel generator structure. As a mi.nimum, ruguirements of the USAR will be met for n.w equipment der.ign within the existing plant.) (Note 2: For regulatory position C.10, >: ables will be marked at 10 foot -intervals, - rather than the 5 foot interval specifiad, in conformance with USAR Section 8.7.5 which has been found to be sufficient to ensure proper cable ino?.allation.) Regula*.ory Guide 1.76, 4/74 Design Basis Tornado for Nuclear Power Plants Regulatory Guide 1.92, Rev. 1, 2/76 O Combining Modal Responses and Spatial Components in Seismic Responso Analfais Regulatory Guide 1.100, Rev. 2, 6/88 Seismic Qualification of Electric Equipment for Nuclear , Power . Plants. Regulatory Guide 1.102, Rev. 1, 9/76 Flood Protuction (Flood Protection per USAR Section 2.5) Regulatory Guide 1.115, Rev. 1, 7/77 Protection Against Low-Trajectory Turbine Minsiles (Protection Against Low-Trajectory Turbine Missiles por US7.R Sections 6.1.2.3 and 12.2.1) 101
l. 4
~
Rev. 1
. Regulatory Guide 14117, Rev. 1, 4/78 Tornado Design Classification Regulatory Gtito 1.118, Rev. 2, 6/78 Periodic Testing of Electric Power and Protection Systemq Begulatory Guide 1.122, Rev. 1, 2/78 Ct.volopment of. Floor Design Response Spectra for Design o." Flocr-Supported Equipment or Components Regulatory G'ide 1.132, Rev. 1, 3/79 Site Investijations for Foundations of Nuclear Powar Plent4 (Site-Investigation per USAR Sections 2.5 & 2.6) "l: Regulat7r- Ctide 1.137, Rev. 1, 10/79 i
Fuel 01. /stens for Standby Diesel Generator Regulatory Guide 1.138, 4/78 Laboratory Investigations of Soils for Engineering Analyaj a and Design of Hvclour Power Plants t (Laboratory Investigation-of Soils por USAR Secsions 2.5 an 246) ; Regulatory Guide 1.142, Rev. 1, 10/81 Safety-helated concrete Structures for Nuclear nouer .91 ant.s ' (other than Reactor Vessels and Containment) Regulatory Guide 5.65 Vital Area Access Controls, Protection of Physic'l Security Equipment, and Key and Lock Controls 4.6.4. NFPA Standards NFPA 10-1988 National Fire Protection Anno, lation 3tanderd for Portable Fire Extinguishers NFPA 13-1989 National Fire Protection' Ar.sociation Standard for Sprinkler Systems NFPA 14-1986 . National Fire Protection Association Stu dard for the Installaticn of Standpipe and Hose Sy .tels NFPA'30-1987 National Fire Protection Association Standard for Flammable Liquids NFPA-72A-1987 National Fire. Protection Association Standard for Signaling Systems, Local Urateetive NFPA 72D-1986 National Fire Protection Asacciation Standard for Signaling Systems, Proprietary Protect iva l NFPA 72E-1987 National Fire Protection Association Standard for Vire Detectors l,
'02
.w - ~! .-
e c ' Rov. 1
. NFPA 255-1984 National Fire Protection Association Standard .
Methods of Fire Tests of Building Construction & Matarials
?
4.6.5 MEI... St audE51n ANSI A58.1-82 American National Standard Instituto Code Requirements for Minimum Decign Loads in Buildings and other Structures A'tiSI D31.1-1967 American National Standard Code for Power Piping ANSI N45.2-1971 Quality Assurance Requirements for Nuclear Power Plants
.4.6.6 Buildim Codes AIS1 American Iron and Steel Institute
" Specification for the Design of Light Gage
~ Cold-Formed Steel Structural Members" 1980 Edition Minnesota Building Code (1985) AWS D1.1 American Welding Society, " Structural Welding Code" - ACI 318-83 American Concrete Institute " Building Code Requirements for Reinforced Concrete" As.I 349-85 American Concrete Institute " Code Requirements for Nuclear Safety Related Concrete Structures" ANSI /ANWA American Water WoJks Association, ,"AWWA Standard for Welded Steel Tanks for Water Storage" ASTM American Society for Testing and Materials Applicable standards for the various construction materials specified in Project specifications. ASCE AS"E Paper No. 3269, -" Wind Forces cn Structure", Transactions of the American Society of Civil Engineers, Volume 126, Fart II (1961) API 650 Welded Steel Tanks for oil Scorage (Seventh [ Edition) UBC International Conference of Building 103 I, W -' . . . - ' '
Rev. 1 Officials, " Uniform Building Code" (1988 Edition) AISC American Inutitute of Steel Construction l'
" Specification for the Design, Fabrication and Erection of Structural Steel f or Buildings,"
Ninth Edition. UL-555-73 Standard for Fire Dampers 4,6.7 Northern States Power Standarc]E Prairie Island - Updated Safety Analysis Report Prairie Island - Final Safety Analysis Report
- i. Prairie Island Technical Specifications Section 3.4 1
{ NSP Underground Storage Tank Policy Compliance Guide, , i l October 3, 1989. (Exception: Fuel Inventory Management System not provided). Prairie Island operations Manual Section H7, Specification for the Analysis of Piping Systems . Prairie Island operations Manual Section H11, Electrical , Construction Standards Prairie Island Security Plan 4.6.8 Other Refer.gnce Documents SER-NRC Fire Protection Safety Evaluation Report, Sept. 1979 ASHRAE Handbook American Society of lleating Refrigeration and Air-Conditioning Engineers Handbook: Equipment (1988 Edition); HVAC Systems and Application (1987 Edition) . i l 104
Rev. 1 TABLE 4-A (Ref. Reg. Guide 1.61) DAMPING PACTOP,S (Percent of Critical Damping) Operating Basis Earthquake or 1/2 Safe Safe Shutdown Strurture or Component Shutdown Earthauake* __,Earthuuaho_,. Equipment and large- 2 3 diameter piping systems, piping diameter greater than 12 in.** Small-diameter piping 1 2 systems, diameter equal to or less than 12 in. Welded steel structures 2 4 Bolted steel structw es 4 7 Prestressed concrete 2 5 structures Reinforcad concreto 4 7 structures
- In the dynamic analysis of active components, these values should also be U':,4 for SSE.
** Includen both material and structural damping. If the piping system consists of only one or two spans with little structural damping, use values for small-diameter piping. {
105 l
l Rev. 1 l , TABLE 4-B l (Ref. SRP 3.5.3) l TORNADO GEllERATED MISSILES l Hasa Volocity* Misslien Dimension (mg,tgrel. (Kiloctrans) (MetarEjj_g,p.1 Wood Plank 0.092 x 0.289 x 3.66 52 83 6-inch Schadule 40 pipe 0.168 Diameter x 4.58 130 52 1-inch Steel Rod 0.0254 Diamotor x 0.915 4 51 Utility Pole 0.343 Diameter x 10.68 510 55 12-inch Schedulo 40 pipe .0.32 Diameter x 4.58 340 47
-Automobile 5 x 2 x 1.3 1810 59 I
Velocities are horizontal velocities. For vertical velocities, 70 percent of the horizontal velocities ! shall be used. L t I L i l < l' l t i. l- , l I p 106 l
i
- l Rev. 1 j TABLE 4-C Pace 1 of 2 FIRE BA.RRIERS ,
3 HODR FIRE 3 HOUR FIRE 3 HOUR FIRE RATED WALLS RATED CEILING RATED FLOOR l I v1,=vation 695' South Wall D5 x North Wall D6 x East Wall Diesel Bldg. x Torbine & Diesel
. Bldg. Wall x Stairway South, West Walls x l North, East Walla x n o y.a t i o n _ 2 F '
West Wall X North Wall x East ' fall x South Mll D5 x Norih Wa11 D6 x Staira'r y North, East Walls South,' West Walls x l Elevation 718' South Wall D5 x North Wall D6 x Day Tank DS , North, East, x West Walls Floor x
. Ceiling x Day-Tank D6 South, East, x' West. Walls Floor:' x Ceiling x
-Diesel Bldg. x East Wall Turbine-Diesel x '
Bldg. North.
-Wall Stairway i
North, East Walls x ! South, West Walls x l l' 5 i 107
Rev. 1 TABLE 4-C Phgg 2 of 2 FIRE BARRIERS 3 HOUR FIRE 3 110UR FIRE 3 IlOUR FIRE ' RATED WALLS RATED CEILING RATED FLOOR Elevation 735'_ North Wall D6 x South Wall D5 -x Lube oil Tank D6 North, East, x
' West Walls = x Floor Ceiling x Stairway l I
North, East Wall x South, West Walls x l Diesel Bldg. East- Y Wall Turbine-Diesel. Bldg.. x North Wall i I
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Rev. 1 5.0 DE SEL GENERATOR INTERFACE AND ELECTBJMAL... SAFEGUARDS UPGRAp3 The Plant Interface and Electrical Safeguards Upgrade scope includes the following: o Electrical tie-in of the DS and DS Diesel Generators to the existing plant safety related auxiliary power systems. l o Modification of the voltage restoration, load rejection and load estoration schemes for Unit 1 and Unit 2. o Electrical tie-in of the D5/D6 system to the existing plant Emergency Response Computer System. o Improvement in voltage support, principally at the 480V level, in Units 1 and 2. o Replacement of two existing 480V safeguards buses in each of l Units 1 and 2. o Provide alternate feeds to 480V safaguards buses in Units 1 and 2. o Improve circuit coordination by eliminating subfed 480V MCC's on safeguards 480V buses. o Provide additional 480V safeguards buses and 4.16kV switchgear capacity for. future loads, Units 1 and 2. o Provide safeguards 4160V sources to the 121 Cooling Water Pump. , o Replacement of 4.16kV Safeguards Edses in Unit 2 and expansion of Unit 1 4.16kV-buses. o -Replacement of Main Control Room "G" Panel. The existing panel.contains controls and indicators for the existing D1 and D2 diesel generators and safeguard electrical system. The new panel will be unitized and contain. controls and indicators for D1, D2, D5 and D6 diesel generators.and the safe. guards electrical system, Unit 1 and Unit 2. l ( 1 L l~ 118
Rev. 1 ' 5.1 SEISMIC DESIGN CLASSIFICATION
- All safety related electrical systems and components provided in I
-the Plant Iaterface and Electrical Safeguards Upgrade scope will ,
be designed to withstand a Safe Shutdown Earthquake (SSE) and i remain-functional (Seismic Category I per R.G. 1.29). Seismic _ qualifications shall be per IEEE 344 and Regulatory Guide 1.100. All non-safety related systems and components and their supporting systems will be designed to ensure that the SSE would not cause their structural failura resulting in damage to safety related systems or components and adversely affect their ability to perform the safety _related function. 5.2 SAFETY DESIGN CLASSIFICATION The following electrical power distribution systems and the associated control circuits provided in the Plant Interface and l- Electrical Safeguards Upgrade scope are classified as safety L related electrical._ l
- 1. 4160V safeguards switchgear buses 15, 16, 25*, 26*, and 27*.
- 2. 480V safeguards switchgear buses 111, 112, 121, 122, 211*,
212*, 221* and 222=~ 3.'4kV and 480V loads connected to the switchgear and buses listed above.
- 4. 4160V alternate power scurce to each bus listed above.
- 5. Voltage restoration, load rejection, load restoration equipment-and circuitry, including the new Unit 1 and Unit 2*
load cequencer cabinets. 6.-Main Control. Room "G" Panel.
- New equipment in the DS/D6 Building, claasified as Class,1E. l The.following systems are classified as non-safety related.
1, 4160V sources from transformers CT11, CT12,.2RY and 1R-Y winding up to the breaker connection at safeguards switchgear 15, 16,.25 and 26,
- 2. The' Emergency-Response Computer System (ERCS).
- 3. Annunciator circuits to Main Control Room.
119 t.
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. l Rev. 1
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5.3 UPGRADED SAFEGUARDS AUXILIARY'AC POWER-SYSTEM DESIGN 5.3.'1' General Descriotion l Figures _2-1-and 2-2 illustrates:the existing.and upgraded 4160V
~
. Safeguards Auxiliary.AC Power Systems, respectively.
a The planned modification will provide two1 dedicated emergency . o diesel generators tor each unit; D1 and D2 are dedicated to Unit 1, and D5 and-D6 are dedicated to Unit 2.- These diesel- l generators will be independent of-the other-unit's electrical. support systems, and will-be capable of:being connected manually to the-other' unit's associated safeguards-bus using two bus tie circuit. breakers. No~ automatic closure!of:the bus tie breakers ' will be provided. Each diesel generator will be capable of
. supplying thefrequired SBO shutdown loads for either unit.
i5.3.2 Preferred.' Alternate, and Standbv Power Source Conficuration Three separateLpower sources consisting =of preferred and-
. alternate offsite sources and standby onsite sources will'be
'provided to each of the plant's 4160 safeguards buses. }
+
- 1. Startup;fransformers (Preferred or Alternate)~ Source Startup Transformer-1R, Y-Winding provides power to Unit'l Buses 15 and 16 and Startup Transformer 2RY provides power to l Buses 25:and126.
I 12. Cooling = Tower Transformers-(Preferred or Alternate) 1: I Cooling _. Tower Area Transformer CT11 will provide-power to Unit .. 1 Bus 115 in addition to currently-providing power-to Bus 16. p p . Transformer"CT12 will continue:to provide power to. Bus 26:and jn' addition, will provide power.to Bus 25. Normally,'one safeguard-bus per unit.will be connected to a startup/ transformer source:and the other safeguards' bus _will be-connected to a. cooling tower transformer source. L
- 3. . Standby Source .
If the Startup1 Transformers and the Cooling Tower Areal
-Transformers should: fail, standby power is providediby'onsite ~
e safetyJrelated diesel generators. , b; Thisfconfiguration provides two independent offnite sources to- '; 'each 4160V.AC: Safeguards Bus without relying on the bus' tis-D breakers between_ units within separation criteria divisions
-(i~e., Unit 1-Train A: to Unit 2-Train A, ' etc. ) . 'These bus tie-g ;,.
breakers would~be used only during Station Blackout (for; access
-tc. alternate AC (AAC) source) and other similar circumstances.
L 120
. .t . u.- . . , . . -- .. .. .. . . . - -- . - -. - . ,
_. . _. _ __ _ = _ _. s
- i Rev. 1 ,
i i 5.3.3. 4160V Configuration - Snfeauards,Buseg The Unit 2 4160V safeguards switchgear will be replaced and located in the new Class I DS/D6 Building. Thic will be accomplished using two new 4160V safeguard svitchgear line-ups. The present Unit 2 4160V safeguard loads will be reconnected to t the new switchgear. The new Unit 2 switchgear will include space for future growth. Portions of the present Unit 2 4160V safeguards switchgear will become Unit 1 safeguards switchgear by means of a bus interconnection after the new Unit 2 switchgear has been.
. installed. The resulting Unit 1 4150V safoguards switchgear will have' space for future growth.
A new 4160V safeguards switchgear line-up Bus 27, will be installed in the D5/06 Building and will be capable of being supplied from either Unit 2 4160V switchgear train A or B. This , ! line-up will be the-safeguard source for 131 Cooling Water Pump. 5.3.4 480V Confi,qyrat;;lon - figfevuards Buseg Four new Unit-2 480V safeguard buses (two per train) will be
. installed in the new DS/D6 Building to replace the two existing buses. The present Unit 2 safeguard loads will be reconnected to these new 480V buses. The reconnected loads (safeguard MCCs) will'be divided between the buses of a given train.-
The. existing Unit 1480V safeguard buses will be replaced and two additional 4R9V safeguard buses will be added. The additional buses will be located in the present Unit 2 4160V switchgear rooms after the existing 4160V switchgear has been removed. The resulting Unit .1 configuration, two buses' per train, will be similar_to Unit 2. The present Unit 1 safeguard MCC loads will be' divided between the buses-of a given train. Alternate power sources _from the same train of the opposite unit, to be used primarily-for' maintenance outages on 4160V buses, will be added to the 480V safeguard. buses. Each alternate source-line-up will include an incoming line compartment, and a 4160-480V-transformer section. One alternate source line-up per' train will be provided for use by either or both 480V safeguards buses. Loading on the alternate source transformer will be administratively controlled within ratings. Voltage regulators will be added to each 480V safeguards bus in Unit 1 and Unit 2. This will improve the voltage at each 480V safeguards load. l 121
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~
i . Rev. 1 The new 480V safeguard configuration will accomplish the following goals: o Increase capacity for future growth, o Provide additional circuit breakers to allow improved MCC feeder circuit coordination, by eliminating subfed 480V MCCs from safeguards 480V buses, o Provida dual feeders (main and alternate sources) to the Screenhouse MCCs 1AB1 and LAB 2 through transfer switches. o Improve voltage regulation at the 480V level, o Provide alternate feeds to all 480V safeguards buses. o Reroute cable to reduce wrapping (fire barrier) and its resulting cable ampacity dorating. o Replace th original Siemens switchgear with new Class lE equipment. 5.3.5 Voltaae Restoration / Load Reiection/ Load _ Restoration Upon bus undervoltage or a sustained degraded bus voltage condition on the 4.16kv Safeguards Buses in Units 1 and 2, a sequence of events take place to restore proper voltage to the safeguards loads. These events may include automatic starting of the Emergency Diesel Generators, automatic load shedding and a subsequent reloading using the preferred or standby power sources. The control scheme that will initiate and control these events will be a new load sequencer systems. 5.3.6 Emernency Response Computer System-The Emergency Response Computer System (ERCS) will serve as an aid to the cortrol room operator in monitoring the status of the D5 and D6 diesel generators. It can replicate some functions of the engine monitoring system, local control panels or the hard-wired control room instrumentation; however, it will only monitor inputs and provide data to fulfill a specific need for the operator. Areas identified to cate include: o Annunciator system support to identify, on demand, a specific input that generated a group alarm. o Operations data logging of surveillance testing events. o Provide analog process infornation. 122
s Rev. 1 5.3.7 p5/D6 Control Schene Tie-In with Existino Plaut When the local Generator Control Mode switches, located in'the D5 4 and D6 Control Rooms, are in the remote position, control of the DS and D6 emergency diesel generators is transferred to the Main Control Room. Emergency start, manual start and stop, voltage adjust, speed control, main breaker control and synchronizing are among the controls that will be available in the Main Control Room.
-The design of the control circuitry between the D5 and D6 Control Rooms and the Main Control Room will include the intermediate termination of all control cables at terminal cabinets located in the Relay Room and then circuit continuation to the Main Control Room.
The DS and D6 tie-in to the existing plant will also include all appropriate alarm circuits to the annunciator cabinets. 5.3.8 Pdlin. Control Room "G" Panel U,pdificatioll The existing controls for the safeguards diesel generators and their associated 4160V buses located on the Main Control Room "G" Panel will be replaced and additional reatrols for the new diesel generators will be installed. The existing panel will be replaced and smaller controls will be installed to accommodate
-the' additional controls in the original space. All chancas have taken human factors into consideration.and will be approved by the Control Room Design Review Committee. Annunciator alarms for the new-diesel generator will be installed concurrently with the "G" panel work.
~
This work will be done during the.1992 Unit 1 Refueling Outage. Current construction plans are-to also have-a Unit 2 outage during this~ panel work. All required panel' controls will be moved to a temporary panel during this two-unit cutage and then transferred back to the original panel after it is replaced. This method will minimize the.use of temporary panels and the risks involved with electrical _ construction work on safeguards 2 equipment. 5.3.9 . Detailed =Desian 1 5.3.9.1 General Requirements The-Plent Interface scope can be divided into two parts. The part thet involves the existing plant components and systems and the part that involves new plant components and systems. The design, which will modify the existing plant, shall maintain or improve the present safeguard power distribution system reliability and availability. Throughout this criteria, any l 123
l t Rev. 1 design that affects existing plant components or systems and any design that adds new components oc systems within the existing plant will be in conformance with the USAR as a minimum. 5.3.9.2 Cable and Racewry Separation 5.3.9.2.1 General Requirements o Cable and raceway separation and segregation within the DS/D6 Building will conform to the requirements of IEEE 384 as modified by NRC Regulatory Guide 1.75. o Cable and raceway interconnections between 05/D6 Building and existing plant facilities including all duct runs and other raceway systems, as well as til cables and raceways routed within existing plant facilities will be separated and segregated in accordance with the requirements contained in USAR Section 8.7 as a minimum. o Cable and wire used to interconnect equipment will be certified by the manufacturer as passing an approvod flameThis test per IEEE 383 as endorsed by Regulatory Guide 1.131. l requirement does not apply to wire internal to factory assembled devices or pieces of equipment (such as the internal wiring of a computer display terminal). Custom assembled equipment (such as control boards or switchgear assemblies) will be specified wi th flana resistant wiring which meets the intent of IEEE 383. 5.3.9.2.2 Specific Requirements - 05/D6 Building and Fuel Oil Storage Area o Safety related cables will be segregated into two distinct redundant safety divisions designated Train A and Train B, which include Emergency Diesel Generator D5 and D6, respectively. o Redundant safety train caoles will be routed in areas separated from one another by three hour fire barriers. o Cables and raceways associated with Train A will be located in separate fire areas or cubicles from those with Train B. o Cables designated as non-safety related will be segregated from the safety related cables by routing them in raceways which only contained non-safety related cables. o separation between safety related raceways and non-safety related raceways will conform to the requirements in IEEE 384 Section 6.1.8 for fire hazard areas (diesel rooms including diesel control rooms, fuel oil day tank room, lube oil day tank room, and fuel oil storage area), o Separation between the safety related raceways and non-safety related raceways will conform to the requirements in IEEE 384 124 i
--" ----_-_m.-.___.,,_____ _, _ _ _ _
Rev. 1 Section 6.1.4 for limited hazard areas (building electrical equipment rooms). o Safety related cables will be separcted from non-safety related cables within equipment enclosures located in both-fire hazard and limited hazard areas in accordance with the requirements in IEEE 384 Section 6.6. Cables will be separated by at least six inches, or one train of cables will be enclosed in metal raceway, or the safety and non-safety cables will be separated by a barrier with a minimum one-inch separation between cables and the barrier, except in the immediate vicinity of isolation device terminals. Non-safety related wiring which is not physica]ly separated from safety related wiring will be analyzed to show that the lack of-physical separation does not degrade the affected safety related circuits. 5.3.9.2.3 Specific Requirements - Existing Plant Areas o Safety related cables will be segregated into two distinct safety divisions commensurate with the present plant design, as a minimum. o New Non-safety related cables will be separated and segregated from the safety related cables by routing in separate raceways. o Cable tray separation between redundant divisions will conform with USAR Section 8.7.2, es a minimum. Separation between conduits of redundant divisions, and between safety related and non-saf ety related conduits, will be a mirimum of one inch. o Cable separation within control panels betweer. redundant divisions, or between safety and non-safety related cables will conform with USAR Section 8.7.7. . o Cables associated with safe shutdown circuits ao identified in the Prairie Island Fiie Hazards Analysis will be separated or protected in accordance with the requirements contained in USAR Section 8.7.4. o cables associated with redundant safe shutdown circuits will be routed through separate fire zones as defined in the Fire Hazards Analysis if at.all possible. If routing redundant cables in the same fire zonn is unavoidable, then the redundant cables will be physically separated frou one another per 10 CFR 50 Appendix R, Section III.G. If the physical separation distances specified in 10 CFR 50 Appendix R, Section III.G are unattainable, or if there are intervening combustibles, then one of the division cables and raceways will be enclosed in an approved fire barrier protective 125 1
L . ) Rev. 1 material which has a one-hour rating for fire zones with suppression systems and a three-hour rating for fire zones without a suppression system. 5.3.9.2.4' Specific Requirements - 121 Cooling Water Pump o power cables associated with Dus 27 and the 121 Cooling water pump will be treated as a separate cable divicion and will be onparated from all other Train A and B cables in accordance
' with the requirements contained in Section 5.3.9.2.2 and 5.3.5.2.3 above.
5.3.9.3 Safeguards AC Auxiliary Power System
- 1. 'ihe new Unit 2 safeguard switchgear Buses 25 and 26 shall consist of indoor air uagnetic medium voltage metal clad 2000A assemblies which have a nominal voltage rating of 5000V, continuous main bua, 350MVA rating and 50kA interrupting capacity. Each switchgear lineup shall contain the following breakers:
3-2000A for diesel generator and offsite source supplies 3-1200A for transformer feeders 9-1200A for existing and future motor feeders 2-1200A for bus tio and Bus 27 feeder
- 2. The new safeguarf. switchgear 30s 27 will have the sane rating and shall contain 2-1200A motor feeders.
A portion of existing Unit 2 4160V safeguard switchgear will e 3. be used to expand the number of breakers in the existing Unit 1 Safeguard Switchgear 15 and 16. The additional circuit
- breakers will be used for:
Bus 15 addition - 2 future feeder breakers
- 1 feeder breaker Bus 16 addition - 2 feeder breakers 1 future feeder breaker e
- 4. The eight new Unit 1 and Unit 2 480V safeguard buses vill consist of 600V rated indoor lcw voltage switchgear assemblies 1000 kVA each itaving a 1000/1333kVA dry type transformer, voltage regulator, 2000A main bus, 30kA instantaneous and 22kA [
delay trip interrupting capacity, 2000A main breaker, 600A manually operated and 600A electrically operated feeder breakers and future compartmn7ts. The breaker interrupting capacity will exceed the maximum f ault duty from a 3-phase
- bolted fault at the breaker load te::minals.
126
Rev. 1 5.3.9.4 loltage Restoration / Load Rejection / Load Restoration Both units will have a new control scheme to initiate, diesel generator s' cart, load rhedding and sequential load restoration. The undervoltage protection scheme will be revised per Branch Technical Position PGB-1. The logic and tining fune.tions vill be based on programmable controllers. The interfacing devices between the controller und the field equipment will be relays. The power supply to the controller will be safety r21ated 120V AC UPS from the existing plant system. 5.3.9.5 Electrical Cable Requirements safety related circuit design will comply with the ger.eral l requirement given below.
- 1. No distinction between existing plant and new plant will be i made regarding cable purchases. Therefore, all insulated cable shall be qualified in accordance with IEEE 383 and Mgulatory Guido 1.131.
- 2. Oniv copper conductor will be used.
- 3. Nes, alte installed power, contr;A, and instrumentation cable l insulation will be ethylene propylene rubber (EPR) or cross-d linked polyethyltne (XLPE), Cable jacket material will be chlorosulfonated polyethylene (CSPE) . Neoprene and PVC j materials will not be use-1 in insulation or jacket materials.
Switenboard wire will be flame resistant SIS type or
]
4 equivalent. i
'_S.3.9.6 Cable Tray and Conduit Requirements
)
i Tray and conduit systems t;ill comply with the general J requirements listed below: l
- j 1. Exposed rigid galvanized steel conduit and embedded intermediate metallic *3' ng will be used throughout >e plant where the use of alum!. trays is not practical.
- 2. Instrument cables will not share raceways with power, or control cables.
- 3. Safety related trays and conduits will be supported with Seismic Category I supports.
- 4. Existing plant cable trays and raceways to which new circuits ,
- are added will have their supports analyzed to verify continued acceptabilita.
127 l
- i. . .- . _ _
4 Rev. 1
- 5. The design will ensure that safety related, Seismic Category l 1 systeus-and components are not prevented from performing their safety.related functions by aeismically induced physical interaction with non-safety related non-seismic Category I systems or components. Supports for non-safety related items will be designed and installed such that their supports do not fail under seismic conditions and endanger the operation of any adjacent safety-related items. This interaction will be identified as Seismic II/I.
Seismic II/I supports will not fail during an SSE to the degree that they degrade, to an unacceptable level, the ability of safety related systems to perform their required l functio: . New installations in the existing plant will be ovaluated to
- identify potentia 7 Seismic II/I concerns.
Certain non-Ceismic Category I components whose weight and configuration are such that even if their support failed, the nature and force of their impact would not prevent safety
'related components from performing their safety-related function may ba excluded by cnalysis from Seismic II/I considerations.
- 5. Protection of safety related tray and conduit from potential l pipe break failure hazards, missile hazards, hot pipe concerns, and seismic interaction of closely spaced components will be provided by barriers, restraints, separation distance, orientation, or the appropriate combination rhereof.
One train of cables-for each unit-from the D5/06 building will be routed in new cable enclosures in the Turbine Building. Tnese cable enclosures have been evaluated to ensure that the criteria listed above for safety related cable raceways are
. met.
543.9.7- Cable and Cable Tray Coding The identifying code to be used on the electrical' design drawings, the cable tray system and the cable will Le as presented in Attachment 5-A. Color codes and markings will be in accordance with USAR Section 8.7.5. 5.4' DESIGN STANDARDS - For new plant components and systems the Class 1E system design will comply with the following standards. 128 .
i l l Rev. 1 S.4.1 NUREG 0800 Standard Reyiew Pl @ (SRP)._ SRP 8.1 Rev. 2, 7/81 General Requirements SRP 8.3.1 Rev. 2, 7/81 On-Site AC Power Systems
.)
7/81 Adequacy of Station Electric ' BTP PSB-1, Rev. 1, Distribution System Volcages. BTP PSB-2, Rev. O, 7/81 Criteria For Alarms And Indication p Associated With Diesel-Generator Uni; Bypassed And Inoperable Status BTP 10SB-2,'Rev. 2, 7/81 Guidance for Application of b Regulatory Guide 1.47 5.4.2 ' JJJilE Standards IEEE 279-1971 Criteria 'for Protaction Systems for Nuclear Power Generating Statir ns IEEE 308-1974 . Criteria for' Class 1E Electric-Systems for
' Nuclear Power Generating. Stations -
IEEE 323-1974 Standard for Quali1ying Class 1E Equipment for Nuc.'nar Power Generating Stations (Note:IEEE 323 is invoked as a guideline document to provide a basis for the determination of qualified life of equipment. It is not intended to be invoked as a baais for environ- mental qualification. 10 CFR 50.49' requirements which are met by methods described.in RGl.99 ' adorsing IEEE 323) do not apply to the'm3 environment of the new l D5/D6 Dailding).
.IEEE 338-1977 IEEE 5tandard Criteria for the Periodic <
Testing of Nuclear Power Jenerating Station Safety _ Systems IEEE 344-1987 Guideitor Seismic Qualification of Class-1 Electrical Equipment' for Nuclear Power Generating Stations
.(Note: . Seismic qualification for the DS/36 Diesel Generator, HVAC duct dampera, damper actuators, and the Class IE Motor Control Centers cites the 1975 revision. Refer to documentation for details.)
IEEE 379-1972 Guide for the App?.ication of the Single Failure Criterion to Nuclear Power Generating Station Protection Systems 129 l
\
I Rev. 1 IEEE 38?-1974 IEEE Standard for Type Test of Class 1E , Slect*:'.c Caoles, Field Splices, and
- Connections for Nuclear Power Generating
, Estations. .
IEEE 384-1981 Criteria for Separation of Class 1E Equipment and Circuits (thte 1:, The 1931 revision is specified becau.fe it addresses comments contained in Regulatory Guide 1.75, Rev. 2 on the 1974 revision of the scandard.') (Note 2: The idenr.ification requirements of IEEE 384 for tagging intervals of cable,
, cable tray and raceway may not be strictly follcwcd. Guidance provided by the USAR will bs adhered to as introduction of a different set of requirements.would be confusing.
IEEE 187-1975 Dissel-Generator Units as Stanuby, Power Supplies (Note: Certain provisions of the 1984 'l' revision of the standard are included in the
' 05/DG Diesel Generator specification because.
they provide guidance for issues not fully 4 addressed in the 1975 revision which was referenced in Regula. tory Guide 149, Rev. 2. R *.'hese provicioas include Appendix A guidance " for development of a load profile, Appendix B for the format to define diesel generator service conditions, and Table B-2 format for ^ use in defining those components with less than_a 40 year operating life, i IEEE 634-1978 IEEE Standard Cable Penetration 71re Stop j Oualification Tests . a 130
l Rev. 1 \ i
'l J5.4.3 Reculatory_quJdes-i Regulatory Guide 1.6, Rev. O, 3/10/71 1 Independence Betycon Redundant Standby (Onsite) l Power Sources and De';neen Their Distribution Systems Regulatory Guide 1.9, Rev, 2, 12/79 Selection,. Design and Qualification of Diesel Generator Units Used as Standby (Onsite) Electric
- Power Systemu at Nuclear Power Plants Regulatory Guide 1.29, Rev. 3, 9/78 Seismic Design Classifica* ton Regulatory Guide 1.32, Rev. 2, 2/77 Criteria for Class 1E Electric Power I.ystems for Nuclear Power Generating Stations Regulatory Guide 1.47, 5/73
-Bypassed and Inoperable Status Indication for Nuclear. Power Plant Safety Systems Regulatory-Guide 1.53, 6/73 Application of the Single Failure Criteria to Nuclear Power Plant Protection System ,
Regulatory Guide, 1.62, 10/73 Manual-Initiation of Protective Actions Regulatory Guide 1.75, Rev. 2, 9/78 Physical 7Independence of Electrical Systems (Note: For regulatory position C.10, cables will be marked at 10 foot' intervals,-rather than the 5 foot interval specified, in
.conformance1with USAR Section 8.7.5 which.has been found to be sufficient to ensure proper cable installation.)
Regulatory Guide 1.81, Rev., 1, 1/75 Shared Emergency and Shutdown Electric Syutems for Multi-Unit Nuclear Power Plants (Note: For regulatory position C.3, the onsite emergency a.c. electrical system for each unit will be separate and independent, but the capability to interconnect the emergency (safeguards).4kV a.c. buses within saparation criteria divisions.(i.e., Unit 1-Train A to Unit 2-Train A, etc.) will be retained for use during Station Blackout (access to alternate AC (ACC) source) and other similar circumstances.) Regulatory Guide 1.100, Rev. 2, 6/88 Seismic Qualification of Electrical and Mechanical Equipment for Nuclear Power Plants 131
.i I , r 3
Rev. 1 i Regulatory Guide 1.108, Rev.-1, 8/77
-Periodic Testing of Diesel Generator Units Used as Onsite Electrical Power Systems at Nuclear Power Plants Regulatory Guide 1.118, Rev. 2, 6/?8 l Periodic Testing of Electric Power and Protection System Regulatory-Guide 1.131, Rev. O, 8/77 Qualification Tests of and Connections for Light-Water-Electric Cables, Field Splices, l Cooled Nuclear Power Plants Regulatory Guide 1.152, Rev. O, 11/85 Criteria for Programmable Digital Computer _ System Software in Safety-Related Systems of Nuclear Power Plants 5.4.4 ANSI Standards
- ANSI /IEEENational American - ANS - Standard, 7-4.3.2 - 1982 Application Criteria for Programmable Digital Computer Systems in Safety Systems of Nuclear Generating
' Stations-l Northern States-Power Standards 5-4.5 Prairie Island - Updated Safety Analysis Report Prairie Island - Final Safety Analysis Report Prairie Island Technical Specifications-Prairie Island Operations Manual Section Hil, Electrical Construction St 3ndards Prairie Island SecurityfPlan 5.4.6: Electrical Eauipment Plan N distinction between existing plant and new plant shall be made therefore, all Plant regarding electrical equipment purchasec, Interface scope Class 1E equipment will be qualified for service !
in nuclear: power generating stations-in accordance withlIEEE 344 and Regulatory Guide 1.100. Switchgear assemblies and circuit breakers rutJ1 be-designed and tested in accordance with anplicable U.S. industry standards, NEMA SG-3 and 5 and ANSI C37. Structural RequiEements [ 5.4.7' Relevant structural requirements such as seismic loading shall be l ca contained in the Installation Design Criteria in Section 3.0. 132 b
Rev. 1 ,
-ATTACEKENT 5-A ELECTRICAL CABLE AND CABLE TRAY CODING cPAGE 1 OF 5 1.0 CABLE TRAY CODING:
1.1 Each tray section of the cable tray system shall have an identifying code indicated on the electrical design drawings and this same identification shall be stencilled on the tray after it is installed. Stencilling shall be applied at each straight section of tray where the identifying code changes. Any tray that is continuous thru walls or floors-shall have the identifying code stencilled on both sides of the wall or floor. > '1.2 The identifying code shall be based on the following system: Example:
-1TG-L
- 1
-Numerical sequence Safeguard and Reactor Protection Designations only See coding listing Paragraph 1.4.
L - Ladder (Power) T - Trough (Control or Instrumentation) Plant Location - See coding listing i Paragraph 1.3. Generating Unit No. (Where required) 1.3 ADB- Administration Building FHR- Fuel. Handling Riser ADR Administration Building Riser RR- Relay Room AG- Aux Bldg. Grd. Fl. SG- Switchgear Rm-Grd. Fl. AM- Aux Bldg.'Mezz Fl. SM- Switchgear Rm-Mez. Fl.
'AU- Aux Bldg. Upper F1. SH- Screen House
'AR- Aux Bldg. Riser SR- Screen House Riser
'BR- Battery Rooms TB- Turbine Rm-Cond Pit CV- Containment Vessel TG- Turbine Rm-Grd. Fl.
DR- D1 and D2 Diesel Em. TM- Turbine Rm-Mez. Fl. 133 , 1
1 Rev. 1
'i ATTACHMENT 5-A ELECTRICAL CABLE AND CABLE TRAY CODING PAGE 2 OF 5 FHG- Fuel Handling Grd. F1. TF- Turbine Rm.-R0of FHM- Fuel Handling Mezz. Fl. TR- Turbine Rm.-Riser
'FHU- Puel Handling Upper Fl. SM- DS/D6 Switchg. Rm-Mez.
DBG- D5/06 DS1 Rms & Cont. Rm. SU- D5/D6 Switchg. Rm-Cper BR- D5/D6 Diesel Bldg. Bat. Rm DBR- D5/D6 Dal. Bld. Riser DBS- DS/D6 MCC and Cable Spread- H ing Rms. DBB- DS/D6 Bldg - Basement DBM- 05/D6 Mech. Rms-Mezz. DBU- DS/D6 Mech. Rms-Oper. 1.: 4 *Saf3gpard De,ylgnation
'A -
A Train B - B Train cA/B - 121 Cooling Water R - Re: actor Protection Channel I W. - Reactor. Protection Channel II I X- - Reactor Protection-Channel III Y - Reactor Protection Channel IV
'2.0 CABLE CODING 1 2.1 Each electrical cable shall have an identifying code indicated on
~
-electrical _ design drawing and. cable routing list. This same code will be affixed at each end of_the cable with permanent tags.
2.2 The identifying' codes shall be based on the following systems: j 2.3 4 KV Swit.gfigs,Ar Cable Example: 7_J 4 07 - 1 I ~ Numerical sequence for power Alphabetical-p _ sequence for control Cubicle No. 4kV Electrical Bus No. 1 134
. - _ ~ .. . . . . - . . --
J Rev. 1 . ATTACHMENT 5-A-ELECTRICAL' CABLE AND CABLE TRAY CODING IPAGE 3 OF 5
, 2.4 A30V Stiltghnear Cable Codasl.
Example: 1 11 B - - - 1 A Add alphabetical - sequence for control I Numerical sequence for connected auxiliaries Breaker No. . 4TiOV Electrical Bus No. (Bus 211) 2.5- Mgtor Control Center Cable Codes: Example: 2TA 1 - 1 A Add alphabetical scquence for control l Numerical sequence for connected auxiliaries , MCC Bus No. MCC Identity No.
.2.6 DC Cable Codes:
Example: 1 DC A - 1 Numerical Sequence For safeguards only-A or B Train 125 V DC Generating Unit No. l s 135 i
Rev. 1 ATTACHMENT 5-A , ELECTRICAL CABLE AND CABLE TRAY CODING PAGE 4 OF 5 2.7 Control & Instrumentation Cable Codes: Example: 1 * - 1 Numerical Sequence
- Control or Instrumentation Funct1.on See Listing Below
----Generating Unit No.
- C -
Miscellaneous CA - A Train , CB - B Train CAB - A/B Train CX - Reactor Protection Channel III (Blue) CF - Reactor Process Instrumentation (Foxboro) CLD - Part Length Rod Drives ' CM - Radiation Monitors CN - Nuclear Instrumentation Systems CP - Computer CR - Reactor Protection Channel I (Red) CRD - Rod Drive - CRP - Rod Position CS - Substation CT -
. Cooling Tower CV -
Invertor Bus & Distribution CW- - Reactor Protection-Channel II (White) CY - Reactor Protection Channel IV (Yellow) 2.8 Pre-Fabricated Cables (Control Board Modules) Example: P- 49022 Control Board Cutout No. Prefab Cable 136
1 Rev. 1 , ATTACRMENT 5-A ELECTRICAL CABLE AND CABLE TRAY CODING
'PAGE 5 OF $
.3.0 Color Codino Assianments The following colors will be utilized to identify th2 specific grnup which the-cable tray, conduit and cables are assigned:
Orange - Safeguard Train "A" Green - Safeguard Train "B" Yellow / Black - Safeguard Train "A/B" 4.0 Cable Trav Hanaer Codino 4.1 Non-trained cable tray 2 DBG - H 0001 Sequential / L Hanger Area code [ Unit l l -4.2 Trained cable tray 2 DBM - H A 0001 Sequential # 4 Trained designation A or B Hanger Area code Unit 137
i
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Rev. 1 6.0 COOLING WATER SYSTEM MODIFICATION 6.1 SYSTEM FUNCTION The Cooling Water System has been designed to provide redundant cooling water supplies with isolation valves to auxiliary feedwater pumps, diesel generators (D1 and D2), air compressors, component cooling water heat exchangers, containment fan-coil units, and the auxiliary building fan-coil units, plus other non-essential loads, The Cooling Water System simplified flow diagram is shown on Figure 6-1. Normal operation utilizes two horizontal pumps (11 and 21) with a vertical motor-driven pump (121) as a standby. Two vertical diesel engine pumps (12 and 22) are provided in the eventuality that all power supplies are lost. The diesel engine-driven pumps are used whenever an engineered safety features sequence is ! initiated, when auxiliary power is lost, or when header pressure decays below its set point. The diesel cooling water pumps, the vertical motor driven pump (121) ' and their associated equipment are located in the Class 1 portion of the cooling water screenhouse as shown on Figure 6-2. All three pumps drar suction from the same pump bay for cooling water from the Mississippi River. An emergency cooling water intake from'a branch channel of the river is also provided in case the river level _ drops suddenly or the intake canal is blocked. A ring header which is shared by Unit 1 and 2 can be isolated automatically to provide two redundant independent sources of train cooling water for all essential services. One train of_the essential services for each unit is supplied from each side of the isolatable loop. Each side of the loop is designed to supply the needs for train of essential services for both units. Thus, failure of one_ side of the loop still Frovides for the operation of all equipment required for the safe shutdown of both units. As' stated above, two diesel engine driven pumps are provided common to both Units 1 and 2. Redundant (Train A and B) Safety Injection signals start both engine driven pumps in case of a DBA in either unit. Each engine driven pump is provided with both local and Main Control Room manual controls. _6.2 121 COOLING WATER PUMP UPGRADE The 121 Cooling Water Pump (121 CLP) was purchased as Quality Assurance Type 1 pump but is presently powered from a non-safeguard power source (4kV Bus 14). The pump will be upgraded to function as a back-up to the 12 and 22 diesel engine driven pumps during maintenance and normal operation by repowering the 138
3 i Rev. 1 , 1 pump motol from the.4KV safeguards buses and modifying the pump control system. The 121 CLP will also retain the function of a stand-by pump to-the two horizontai pumps during normal operation. The 121 CLP serves both units as part of the shared Cooling Water System and will be manually aligned with and powered from either of the Unit 2 Safeguards 4.16 KV Buses. The upgraded Unit 2 Auxiliary Power System has sufficient _ capacity to power the 121 Cooling Water Pump from either Unit 2 Safeguards Buses 25 or 26.
.For emergency power, the new Unit 2 DS and D6 emergency diesel generators have each been sized to start and operate the additional 1000 HP load. Thus the 121 CLP will have power source independent from the diesel driven safeguards 12 and 22 Cooling Water Pumps.
The existing 121 Cooling Water Pump motor was originally purchased as safety related. The motor safety design classification will be upgraded as necessary by analysis and special maintenance to safety related using the methodology applied to original plant equipment. The safety design classification of the pump remains as safety related. The seismic design classification of the 121 Cooling-Water Pump will be upgraded to Seismic Category I using the seismic qualification documentation prepared for the original equipment. The controls of the 121 Cooling Water Pump will be modified to provide an automatic-start for any Safety Injection (SI) signal: Unit 1, Unit 2,-Train A,.or Train B. When both diesel driven
-pumps are operable, all three pumps will start on the SI signal.
'If both diesel driven pumps come up to speed, then 121 CLP will trip. If one diesel driven pump does fail to start, then 121 CLP will remain running.
The1four existing cooling water header isolation valves, listed below, close on a Safety Injection signal to separate the safety trains and assure cooling water system redundancy. The present control scheme aligns the 121 Cooling Water Pump to in parallel with a discel-driven cooling water pump,-depending on which unit has an S7 signal. This control scheme will remain unchanged except as discussed below. l l~ l 139 i
Rev. 1 Valve Safety Train Automatic Action MV 32034 A Closes on SI Signal in Unit 2 MV-32035 B Closes on SI Signal in Unit 3 MV 32036 A Closes on SI Signal in Unit 1 MV 32037 B Closes on SI Signal in Unit 1 When it is necessary to take a diesel driven cooling water pump out of service for maintenance, the 121 Cooling Water P mp will be manually aligned to replace the out of service pump. The appropriate MOVs will then be placed in the desired position (open, close) and then administratively controlled in position by opening the MCC circuit breakers for the valve operators. The change improves the reliability of the Cooling Water system during an angineered safety features initiation by providing a safeguards power supply to the 121 Cooling Water Pump that is manually selected from either Unit 2 4KV Safeguard Bus. The motor driven pump provides a diverse means of providing cooling water that is-independent of a common-mode failure of the diesel drives for the 12 and 22 Cooling Water Pumps. This modification to the 121 Cooling Water power supply and control scheme, plus administrative controls will provide a significant basis to allow one diesel driven cooling water pump to be taken out of service for maintenance without initiating a limiting. condition for operation (Ico) condition. This will require a Technical Specification change with supporting analysis, which will be requested ir. a separate submittal to the NRC. I l l 140
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4 Rev. 1 . i 7.0 IMPLEMENTA7 ' LAN FOR ADDITION OF DIESEL GENERATORS AND ELECTRICAL l SYSTEM UP(.~LE sOR PRATRIE ISLAND UNIT 1 AND , I k Ul'IT 2 fie initial planning and scoping for this projcct began in September 1986 with the subsequent generation of the Project Major Milestone . Schedule. This schedule logic projects completion of all construction and final documentation by approximately December of 1994. What is discussed here are the major Administrative, Training, Ccnstruction, and Testing activities that are deemed necessary to r evide an overall view of'the project. This will show that the project is being implemented in a safe, logical, and economical manner. The extensive engineering and procuremont effort that is required to replace the entire electrical safeguard system for Unit 2 and upgrade the Unit 1 system is not portrayed but is implied as a prerequisite to support - all these activities. Because the' new construction ' effort will occur within the plant protected area and next to an operating unit, special attention has been given to encure all the operational and site security rules are adhered to. This plan was developed while observing the constraints Of major construction having to occur within the existing plant as a backfit effort. Although it is especially difficult to interface with existing equipment and even harder to replace older equipment with new, we are confident this can be schieved by an extensive 6ctailed effort. Installation of. cable tray, raceway, cable, and various equipmenb ' determined not to require a unit' outage will be installed jn the Turbine,. Auxiliary and New D5/D6' buildings during Unit operations. These actions will support more efficient efforts during the outagess l Electrical and mechanical interface activities with major existing plant systems will be done'during refueling and maintenance outages to j
~
minimize impact on plant operations. The only exception being the modification!of the Main Control Room Panel "G", which will be :
. performed during a two-unit outage, c In order to meet the objectives of the plan Se activities have been [
segregated into three major design changes.
- 1. Diesel Generator Building 2.- D5/D6 Diesel. Generator Installation
- 3. Plant Interface. .
.The. highlights for the execution of each of the parts will be discussed-in the'following text. The integrated schedule for completing the. major SBO/ESU Project activities remaining as of October 1, 1991 is'shown in Figure 7-1. General descriptions of these '
activities is included. in the follcWing subsections. 143 .
Rev. 1 7.1 SBO/EFU PROJECT INTEGRATED SCHEDULE CONSTRUCTION ACTIVITIES: 7.1.1. DS /D6 D.Q_,_EQLLQlllG HVAC_ INSTALLATION: Tnese activitius include HVAC sheet metal ductwork, plenums, stifferers, hangers, dampers, grills, registers, nozzles, diffusers, access doors, controls, electric heaters, air conditioning units, miscellaneous fans, filters and fan installation. 7.1.2. M]Ji PLANT INTERFAC" ELECTRICAL INSTALLATION 6ND POWER SOURCES: This includes work in the existing plent to support the installation of tray, raceway, and conduits to facilitate the installatien of new power sources for Unit 2 4160V equipment, 480V buses and Motor Control Centers, 120V UPS and distribution panels, and 125 VDC panels. Cable, wiring and equipment installation in the existing plant is also included. An etuphasis on pc 2r sources for startup of D5/OG Auxiliary equipment is shown in the last quarter 1991. 7.1.3. M]R5 HIGH/ LOW TEMP CQOjyG WATER INSTAiLATION: These activities include installation of pioing, hangers, components, and integrity testing for the High and Low Temperature cooling Water Systems. 7.1.4. Mjj5 STARTING AIR INSTALLA'J.IQ111 These activities include installation of piping, hangers, components,-and integrity testing for the Starting Air Systems. 7.1.5. D5 /06 LUBE QL_S_YJTEM INSTALLh1LQ1{1 These activities include installation of piping, hangers, components, and integrity testing for the Lubc 011 Systems. 7.1.6. M]J6 F.O. VAMLI, RECEIVING, AND TRAN_S.FLR SYSTEMS: These activities include site preparation, excavation earthwork architectural and structural items including reinforcing steel installation, structural steel crection, and concrete placement for the walls-floors-ceilings-accesses. Inrtallation of the bulk fuel oil storage tanks, the receiving tank, and associated piping, hangers, and components for the Fuel Oil Storage and Transfer system is also included. 144
T 1 Rev. 1 , 7.1.7. D5/06 COMBUSTION AIR / EXHAUST SYSTEM INSTALLATION: These activities include Justallation of piping, hangers, components, and integrity testing for the Combustion Air and Exhaust Systems. 7.1.8. D5/D6 ELECTRICAL IPSTALLATION (AC DISTRIBUTION) These activities include installation of all electrical components, equipment, hangers, tray, raceway, conduit, cable, and wiring. Construction testing of terminations and equipment function-is also included. 7.1.9. M.LDs FIRE PROTECTION INSTALLATION: These activities include-installation and integrity testing of the automatic sprinkler systems, standpipe riser with hose stations, and deluge system with open head sprinklers.
. 7. 2 - SBO/ESU PROJECT _ INTEGRATED SCllERVJ&_,,STARTUP ACTIVITIES:
-Following-most of the construction installation activities is an activity for the Startup Group to perform-prerequisite and preoperational testing on each of the systems.
At the end of these activities the system will be ready for the initial engine runs and integrated preoperational. tests. A target date of July 27, 1992 for preliminary turnover for operations is projected. This will allow sufficient time'for operations personnel to perform surveillance and routine preventative maintenance befers the tctual tie in to the plant. Finally, the Unit 1,and Unit 2 outages which include construction tie-in to the existing plant and preoperational tests of the final' configuration are shown for October and November of 1992.
- 7. 3 - SBO/ESU PROJECT INTEGRATED SCHEQULE SUPPORT ACTIVITIES:
7 . 3 .' J. Submit Revision 1 Desian Report to NRC:
.This includes the submittal of Revision 1 of the Design Report which was previously submitted-to the Nuclear Regulatory.
Commission as Revisions to incorporate chann-t in project-schedule, scope, and design are included. C;arifications and ndditional information requested by the Nuclear Regulatory Commission are also included. 7.3.2 Licensinn Amendment: This includes tre submittal to be made to the Nuclear Regulatory Commission for the actual Safety Evaluation, supporting documentation, and the proposed technical ! . specification-changes. 145 y;
T Rov. 1 7.3.3 SBO Proiect Suppgrt Proceglures: This includes the development and use of the new procedures required for operations and maintenance once the new systems have been turned over to Plant Operations. . 7.3.4 D,5/06 TIainina Overyiew (Encine Rtul and Outa.se Re101ggl These activities include lesson plan development and actual training on all equipment, new system functions, pro"edures, and design changes associated with the inodification. Training will be performed by site training p9rsonnel and equipment manufacturers for operations, maintenance, and engineering personnel. w 146
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A e Rev. 1 8.0 AiMIQWiRDS AUXILIARY POEER SYSTEM OPERATION
'8.1 EXISTING SAFEGUARDS AUXILIARY POWER SYSTEM DESCRIPTION Each existing diesel generator (D1 or D2) is capable of supplying power, in the event of loss of off-site power (LOOP), to all the necessary safeguardL equipment of one Unit in an accident condition, alus the auxiliary loads for a safe (hot) shutdown of the other Unit. The maximum automatically connected loading which for these conlition1 per USAR Table 8.4-2a is about 2785KW, The D1 occurs in the first minute of diesel generator operation. ,
and D2 diesel generators installed at the Prairie Island plant l have an 8760 hour (continuous) rating of 2750 kilowatts. The 2000 hour rating of thoce machines is 3000 kilowatts and the 30 minute rating of the' machines is 3250 kilowatts. 1 Paragraph C-2 of Regul.atory Guide 1.9 statos that the predicted l load on each machine will not exceed the smaller of 90% the 2000 of thehour 30 rating or 90% of the-30 minute rating of the set. minute rating of the Prairie Island diesel generators is 2975 kilowatts, and is less than the 2000the hour ratings total predicted of 3000 connected ! kilowatts. As shonn on Table 2-A, ' load on either diesel generator is 2825 kilowatts. O.2 EXISTING SAFEGUARDS AUXILIARY POWER SfSTEM OPERATION Each. diesel generator is automatically started by either of the following events: l
- a. Loss of volte ge or degraded voltage on either of the ,
associated 4160-volt buses (buses 15 and 26 for D1 and buses ) 16 and 25 for D2); I
- b. Initiation of a Safety Injection Signal (both diesel :
generators start on this signal). ) With a loss of voltage or degradedthe voltage on any autoraatic sequence of=the isfour as l j safety-features 4160-volt buse' l follows: i ' a.' Start associated diesel ge* cator (D1 for buses 15 and 26; D2 for buses 16 and 25), l
- b. Trip all associated source breakers-to bus,
- c. Close breaker to offsite source if voltage is present; (Bus 15 Reserve Auxiliary Transformer 1R) (Bus 25 Reserve Auxiliary Transformer 2R) (Buses 16 and 26 - Cooling Tower 4160-volt p
Subs .o. tion) . If this source is.not available:
- d. Close bus tie breaker to associated 4160-volt safety features bus of the other Unit, if voltage is present; (Bus 15
' associated with bus 26) (Bus 16 associated wi+4 bus 25) If this source is not available: , 148 i
l 1 . Rev. 1 ,
- e. Shed designated loads on the affected 4160-volt bus and associated 480-volt buses experiencing undervoltage,
- f. Close dieael generator breaker if voltage and frequency of the diesel generator meet established criteria.
Relays are provided on buses 15, 16, 25, and 26 to detect loss of voltage and degraded voltage (the voltage l<. vel below which safety related equipment may not operate properly). On loss of voltage, the automatic voltage restoring scheme is initiated immediately. When degraded voltage is sensed, the voltage restoring scheme is initiated if acceptable voltage is not restored within a short time period. This time delay prevents initiation of the voltage restoring scheme when large loads are started and bus voltage momentarily dips below the degraded voltage setpoint. The undervoltage trip signal to the diesel generator source breakers is blocked if the safety injection signal is present, thernby preventing load shedding of the emergency buses when th2y are being supplied by the diesels. After voltage is re-established on the subject 4160-volt bus, either from an offsite source or from a diesel generator, the diesel unit continues to run (loaded or unloaded) until manually shutdown. The 480-"olt buses are immediately energized at the same time as the 4160-volt buc from which it is fed. Running loads which are not de-eacrgized by the load shed - sequcnce and have maintained contact circuitry in their starting circuits will subsequently be re-energized when bus voltage is restored. Motors not running prior to the loss of voltage condition would not start upon restoration of voltage, until manual or subsequent automatic action is initiated. If there is a requirement for engineered safety features operation coincident with or following bus undervoltage, load shedding as cescribed in step "e" is initiated, followed by sequential starting of the safety features equipment. 8.3 UPGRADED SAFEGUARDS AUXILIARY POWER SYSTEM DESCRIPTION The Upgraded Safeguards Auxiliary Power System: Dedicates new EDGs D5 and D6 to Unit 2
- Dedicates existing EDGs D1 and D2 to Unit 1
- Dedicates Cooling Tower offsite source Transformer CT11 to Unit 1 with connections to Safeguards Buses 15 and 16 and Transformer CT12 to Unit 2 with connections to Safeguards Buses 25 and 26.
149
( 1 ( . Rev. 1 i
- Retains dedication of offuite source Transformer in, Y Winding to Unit 1 with connections to Safeguards 4160V Busen 15 and 16 and Transformer 2RY to Unit 2 with connections to Safeguards 41COV Buses 25 and 26.
The offsite source and emergency diesel generator existing and proposed voltage restoration sequence are summarized in Table 8-A. The sources for Unit 1 Safeguards Buses 15 and 16 will be Transformer 1R-Y Winding, Transformer CT-11 and EDGs D1 and D2. The sources for Unit 2 Safeguards Buses 25 and 26 will be Transformer 2RY, Transformer CT-12 and EDGs D5 and D6. The new additional emergency diesel generators (D5/D6) dedicated to Unit 2 Safeguards Buses will have a 8760 hour (continuous) gross rating of 5A00 kW. At present. as shown on Table 8-B, the (preliminary) total predicted connected Unit 2 Safeguards steady state load, excluding steps ic, 2c, 4c, 5c and 7c This whichrepresents are reserved for future loads is 3758 kW per train. ' approximately 70% of the diesel generator continuous gross rating. Approximately 400 kW ot Unit 2 Emergency Diesel Generator D5 and D6 running auxiliary loads per unit is included in Load Step 6B. 8.4 UPGRADED SAFEGUARDS AUXILIARY PGUER SYSTEM OPERATION one safety train from eacn unit will be normally supplied power from the "R" transformer while the other safety train will be supplied from the "CT" transformer. With this arrangement, the loss of a single offsite source transfer will cause the loss of only a single safety train per unit. On undervoltage, the automatic voltage restoring scheme is actuated after a short tiue delay to prevent actuation during normal transients (such as motor starting, and protective relaying operation during faults. The unaervoltage setpoint is 75 i 2.6% of nominal bus voltage. the minimum setpoint ensures equipment operates as it is above t'.e limiting value od 75% (of 4000V) for one minute operation. The maximum setpoint is chosen to ensure adequate voltage during starting. The under voltage time delay of 4 i 1.5 seconds has been shown by testing and analysis to be long enough to allow for normal transients and short enough to operate prior to the degraded voltage logic, providing a rapid transfer to an alternate source. When degraded voltage is sensed, two time delays are actuated. Again, the first time delay is long enough to allow for normal transients. The first short time delay annunciates that a sustained degraded voltage condition e :ists and enables logic for automatically performing the following upon receipt of an SI signal: 150
. . - . ~ . -- -..-_ -.~ -.~.- - . - ~.- -- - ..--- - -
e b Rev. 1
- 1. Auto start the diesel generator
- 2. Separate the bus from the grid
- 3. Load the bus onto the diesel gene.ator
- 4. Start load sequencer (including SI loads)
The second longer time delay is used to allow the degraded voltage condition to be correcced by external actions within a time period that will not cause danage to operating equipment. If voltage is not restored within that tine period, the logic automatically performs the following:
- 1. Auto start the diesel generator
- 2. Separate the bus from the grid
- 3. Load the bus onto the diesel generator
- 4. Start load sequencer The negraded voltage setpoint for Unit 2 is 87.5 3.5% of nominal 4160V-bus voltage. The Unit i setpoint is 90 1 2t; however, it will be the same as Unit 2 after modificaticna '
scheduled to be completed by 1994. Testing and analysis have shown that all safeguards Joads will operate properly at or above the minimum degraded voltage setpoint. The maximum degraded voltage setpoint is chosen to prevent unnecessary. actuation of the' voltage restoring scheme at the minimum axpected grid voltage. .T;te first degraded voltage time delay of 8 1 0.5 seconds has been ahown by testing and analysis to be long enough to allow for normal transients (i.e. motor starting and fault
- clearing). It is also longer than the time required to start the SI pump at minimum voltage. The second degraded voltage time delay is provided to allow the degraded voltage condition to be corrected within a time frame which will not cause damage to permanently connected safety related leads.
i A A 4 I 151
.. ..a.__..,__.,
( f e ( 0 Rev. 1 TABLE 8-A EXISTIliG & PROPOSED VOLTAGE RESTORATIOli SEQUEllCE EX1STI!1G VOLTAGE RESTORATIO14 SEQUE!1CE BUS BUS BUS BUS M bi M 21 1RY 2RY 2RY llormal Source 1RY CT-11 2RY Cr-12 First Choice IRY Bus 74 e Bus Tic Bus Tie B"o Tie Second Choice to 16 to 15 to 2c to 25
' D2 D2 D1 Third choice D1 UPGPJsDED VOLTAGE RESTORATIOli SEQUE!1CE (see note)
BUS BUS DUS BUS M .M M 25. IRY CT-11 2RY CT-12
!1ormal Source CT-11 1RY CT-12 2RY i First Choice D2 05 D6 Second Choice D1 f4OTE: For normal operation of the Upgraded Voltage Restorntion Sequence, the choice of the normal source f ol. each bus may be reversed to the other dedicated source for that unit, provided that each bus is powered fron a different source. This pravents both safegunrds buses in a unit from simultaneously losing power in the event of a single power source failure.
152
Ocv. A PRAIRtE ISLAND NUCLEAR GENERATING PLANT
, UNIT 2 -- SAFEGUARDS. AUXILIARY POWER SYSTEM T7BLE 8-B PAGE i OF 3 PROPOSED LOADING _SEGUENCE* l .
i MOTOR STEADY TIME INTERVAL TOTAL DG AUTOMATIC STARTING STATE FROM RECEIPT STEADY , SEQUENCE MO+0R INRUSH LOAD OF SIGNAL TO STATE LOAD -l RTEP SERVICE EESCRIPTION HP KVA ff) KW START (SEC1 KW (@ raced 0 (d) Motor Voltage)
- 1. a. Safety Injection 800 4472 (j) 631 19 --- ;
Pump (4kV) ,
- b. Miscellaneous 480V ---
2513 (h) 574 (h) 10 --- Loads (e)
- c. Future Motor Load 90 542 (c) 75 10 1280 Block 1C (Total)
- 2. a. Residual Heat 200 1110 (c) 166 15 ---
Removal Pump (4kV)
- b. Containment Spray 250 1194 (a) 207 15 ---
Pump.(4kV)
- c. Future Motor 755 4530 (c) 627 15 2280 Load-Block 2C (Total) ,
20 3136 ! 1 3. a. Cooling Water Pump 1000 5225 (j) 856 i (4kV} ; t
- 4. a. Component Cooling 250 1416 (a) 207 25 ---
Pump (4kV)
- b. Containment Fan 50 686 (b) 41 25 ---
Coil Unit (2 0 25 HP each) (460V)
- c. Future Motor 754 4525 (c) C26 25 4010 Load-Block 4C (Total)
- Load data of some equipment and resulting totals are based on preliminary or estimated values; l these are in the process of being confirmed through test or other final data and the table will be updated if appropriate. .
', 153 J O r r - ._- . , _ . _ _
** s _
rov. L f PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT 2 -- SAFEGUARDS EMERGENCY POWER SYSTEM TABLE 8-B . PROPOSED LOADING SEOUE!(ME _PAGE 2 OF 3 MOTOR STEADY TIME INTERVAL TOTAL DG STARTING STATE' FROM RECEIPT STEADY AUTOMATIC LOAD OF SIGNAL TO STATE LOAD MOTOR INRUSH SEQUENCE KW START f. CEC) KW SERVICE DESCRIPTION HP KVA ff) __ _STED 0 (d) (a rated Mctor voltage) 240 30
- 5. a. Aux. Feedwater 300 1610 (a)
Pump (4kV) 30 --- Air Compresser 100 578 (b) 83 b. (460V) 264 30 4597 cc Future Motor 318 1908 (c) Load-Block SC (Total) 192 35
- 6. a. Pressurizer 192 kW 192 (c)
Heaters 35 5189
- b. EDG Auxiliary 500 3000 (c) ,0 Loads'(Estimated) 25 153 (c) 23 40
- 7. a. Control Room Chilled Water Pump (460V) 40 ---
Control Room Water 162 781 (c) 138 b. Chil?er (460V) 50 40 5400
- c. Future Motor Load- 60 360 (c) l l
Block 7C (Toral) l 3758 TOTAL CONNECTED STEADi-STATE LOAD (LESS STEPS 1C,2C, 4C, SC and 7C) IN KW: i ~ i 154 {- i _c. - t-__ . , .. .
^
A'
)
x - Rav. 1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNIT 2 -- SAFEGUARDS EMERGENCY POWER SYSTEM TABLE 8-B PAGE 3 OF 3 PROPOSED __ LOADING SECUENCE Notes: (at KVA in rush cased on vendor data - motor locked rotar impedance. (b) KVA in rush based on vendor data - motor starting current. (c) Estimaced l (d) Time zero is defined as the instant at which one of the following is first sensed:
- 1. Automatic Safety Injection Signal f Manual Safety Injaction Actuation by Pushbutton.
2. l
- 3. Undervoltage on the 4160V Bus supplied by the Diesel Generator (e) One 4160/480V, 1000 KVA, 8% impedance transformer which pravides power to all 4SOV loads will be energized as soon as bus voltage is restored.
(f) Starting power factor assumed at 0.2. j (g) Deleted ! (h) Step lb KV?. in rush and kW loads based on 12/28/88 study. (j) KVA in rush based on actual test data. i l l l l l l j i i 1 2 155 - _ _ _ _ _ _ _ _ _ _ _ 2}}