ML20148F464
| ML20148F464 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 02/28/1978 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-03-12, TASK-3-12, TASK-RR WYR-78-23, NUDOCS 8011050645 | |
| Download: ML20148F464 (38) | |
Text
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YANKEE ATOMIC ELECTRIC COMPANY
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20 Turnpike Road Westborough, Massachusetts 01581 - ~. Ya% uxes,, '
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February 28, 1978 /; . m'A u Sk' s United States Nuclear Regulatory Commission Washington, D. C. 20555 hh.?. . . n. .#[$N b.2,j8 s/
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i,. %&9 ~[E%*. ' , Attention: Office of Nuclear Reactor Regulation s ..
Reference:
(a) License No. DPR-3 (Docket No. 50-29) (b) USNRC letter to YAEC, dated December 1,1977 (c) USNRC letter to YAEC, dated December 23, 1977 (d) YAEC letter to USNRC, dated February 15, 1978 (WR 78-14)
Dear Sir:
Subject:
Systematic Evaluation Program (SEP) Your letter, Reference (c), requested informaticn of those plants which are participating in the Systematic Evaluation Program (SEP) pertaining to identification, service environmental conditions and environmental qualification of safety-related electrical equipment. The attached equipment list identifies the equipment, its class, and locatien. Attachment A to the equipment list defines the limiting service environmental conditions for this equipment and the requirements for the operation of the equipment under DBE conditions. Attachment B l to the list provides a determination of the current status of environ- i mental qualification and identifies supporting documentation. The l sections of the Attachments which are appropriate for each item of I equipment are identified on the list. Similar items of equipment with l similar environmental requirements have been included on the list as one item. 1 In the determination of the current status of environmental qualification for safety-related electrical equipment, no significant safety concerns have been identified. If you have any questions on this submittal, please contact Mr. David A. Hansen of this office. Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY D. E. Vandenburgh 0{ Senior Vice President s DAH/kg ir 80 n ono GI-r5- p
-m EOUIP!:ENT LIST -
ID # EQUIPMENT (DESC.-FUNC. ) MFR MODEL, TYPE OR CAT f CLASS LOC ENV PEqT ENV Q' Reactor Protection System Linear Amp RPS WEST FN IE MCR Al - B1-Indicator RPS WEST KX24 - MCR- Al Bl Bistable RPS WEST FN IE MCR Al R .. Relay and Control Panel RPS WEST FN IE MCR Al B1 MC-FD- Diff. Pressure Detector MC Loop Flow BARTN 244 IE VC A2 B2 AOCT Current Xformer MCP Current Phase WEST ECI IE SWGR A2 B3 Current Relay IIC Flow Scram WEST 1876-072 IE SWCR A2 n3 Relay MC Flow Scram COUCil 4C37B IE SWGR' A2' B4 D Time Delay Relay Delay Scram 200 tas AGAST 2422-PA IE SWGR A2 84
-PD- Pressure Detector MC & Pressurizer BAILY K1X IE VC A2 B3
-LD- Level Detector Pressur izer Level BAILY BR117XX MODEL XNX IE VC A2 Bh
'1003 Level Xmitter SG FP 13D2495J-BC-BBB-NS IE VC A2 B7 Power Supply for Xnitter LT-1003 LArtBD Lf1262 IE MCR Al B8
- \-1003 Bistable Pscactor Trip RIS ET-215R IE MCit Al - B9 N Test Swi tch for Xmitter T 3 ES 28204A-2 -
!!CR Al n10 e er eb hrm N '
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ID J EytIIPffENT (DESC. -FilNC . ) MFR MODEl., TYPE OR CAT # ~ CLASS- LOC FJJV R EQT .. ENV QfAi r Cll-3,4,6 5 Comp Ion Chamber UEST UL6377 .IE- VC' . A2 - B12' Cll-6,7,6 8 Ionization Chamber WEST UL6937A IE. 'VC A2 B 12 C Intermediate Range Panel UEST TYPE FN IE MCR. Al- "B 1 Power Range Panel WEST TYPE FN IE !!CR " Al- B1' Bistable Panel WEST TYPE'FN IE MCR Al' B1 62CX Relay Trip BFP ACAST ND22-0 - MCR 'Al B3 BK1 Breaker Rod Scram Bkr WEST DB25 IE SWGR A3. B3 , Pit Switch flanual Scram UEST UT IE MCR Al B3 TC-420 E Thermal Converter / Permissive 15MWE SANG CW-10 IE MCR- Al "B3-BS-420 Current Alarm Unit / Permissive 15 MWE ACR0 871-S-8 - MCR Al as ! l I Alarm & Serna Panel WEST FN IE MCR- ; A1 B1 Scrh n A.ipli fier WEST FN IE 'MCR Al 31 , Current Reference UEST FN IE MCR Al Bly AC-DC Panel Power Supply USST FN IE MCR Al 31 ' Safety Injection System ' SI-MOV- Motor Oper. SI . Loop Fill I!dr Isol LIMIT SMB-00 .IE VC . A6' B13 L SI-PP-LP Motor Low Press S1 Pump EMMCO TYPE IC IE PAB A4 B3
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o a iD J EQUIP:!I:NT (DCSC.-FUNC.) MFR 110 DEL, TYPE OR CAT f CLASS LOC ENV REQT E!!V QliAL - SI-PP-IIP Motor liigh Press SI Pump GE SK404AK174 IE PAB A4 B3-S I-:;0V-1 Motor Oper. SI Accumulator Isol LIMIT SMB-1 IE PAB A4 B13 , LI-SI-l Electronic Transmitter Level SI TF GE 555 -- PAB A4 B14 Power Supply Level SI TK GE 570-04 - MCR Al B15 Vcrtical Ednewice Meter Level SI TK GI 180 - MCR Al B16 S I -LS - Level Switch SI Accumulator MAGNT 0-751-X1-SP-SIM3 IE PAB A4 B17 SI-UL- Switch SI Initiation Circuit IJEST UL IE MCR Al B3 SI-1-X Relay Multiplier A/B 200E441Z1 IE MCR Al B3 SI-PS- Pressure-Switch VC Pressure STAT 12N-S4-04-X2 IE PAB A4 B18 SI-PS-X Relay SI Initiation Circuit WEST SG IE t1CR Al B3 SI-PS-14 Pressure Switch SI Initiation BARKS B2T-It3255 IE VC A6 B19 SI-FT-1 Transcrit ter S1 Loop Flow BARIN 386 - VC A6 B2 Power Supply SI Flow GE 570-04 - MCR Al B15 Indicator SI Flow GE 180 --
?!CR Al B16
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u-ID # EQUIPMENT (DESC.-FUNC. ) MFR 110 DEL, TYPE OR CAT # CLASS LOC ENV REQT CUV QUA Switch Auto-Manual Bypass Selector WEST OT IE MCR A1 33-LSX- Relay Vent Accumulator WEST llFA IE MCR Al B3 TDC- Relay Pressurize Accumulator AGAST 7012FD IE MCR A1 , B3' NS-SOV SOV Pressurize Accumulator ASCO IIV-2 02-301-3-U-125 IE PAB A4 B20 NS-SOV- SOV Vent Accuculator ATKOM 31820 IE PAB A4 B21 Switch Test Sw GE CR2940UT200R - MCR Al B3 PU-MOV-541 flotor Ope r. Rectre LIMIT Sr1A-000 -- PAB A4 Bil PU-?:OV-542-8 Motor Oper. !!ccire LItt1T S718-5000 - PAB A4 B13 Charging and Volume Control System P !!otor Charging Pump NEST 19N3044 - PAB A4 B3 Cll-MOV-521 Motor Oper. CVCS Charging Pump Suction lit!IT SMA-00 - PAB A4 B13 Cll-:;0V-526 Motor Oper. CVCS Orifice Isolation LIMIT SMA-000 -- VC A6 B13 Containment Inolation System CIS-SOV- SOV Cont Isol ASCO IIV-202-303-16 IE PAB A4 B20 CIS-UL- UL Switch Cont Isol Act WEST 803-A448601 IE PAB A4 B3 CIS-K9- Relay Cont Isol Act GE 11GA11J52 IE ttCR Al B3 C15-5801 Switch / Manual Cont Isol & Valve Test GE CR294QU207 IE MCR Al B3
[ . ID # EQUIPMENT (D ES C. -FU NC . ) MFR MODEL, TYPE OR CAT # CLASS LOC ENV REQT Etru QUA{ CIS-PS Pressure Switch Cont Isol Act STAT 12f;NL4-C IE PAB A4 B18
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Cvmponent Coolinn Synten . P lotor Component Cooling Pump WEST 19N3369 - PAB A4- B3 Chznical Shutdown System CS-MOV-529 Motor Oper. Chem Shutdown Mix Tk Dsch LIMIT SMA-00 - PAB A4 B13 CS-:iOV-540 liotor Oper. Chem Shutdown LIMIT SMA-000 - PA1 A4 B13 Dt:-:MV-65 5 110 tor Oper. Demineralized Water Line 1.I? LIT SitA-000 -- PAB A4 B13 Se rv i c e- Wa ter Sys tem P Motor Service Water Pump UEST 19N3044 - SCRN A7 B3 Main Coolant S/ stem - tic-:10V- Motor Oper. Main Coolant Inlet / Outlet LIMIT SA-3 - VC A6 B l .
*tC-PI Press Xnitter LTOP ROSMT 1152-GP --
VC A8 B23 Power Supply LTOP LAMBD LCS-A-03 - MCR Al B8 Recorder LTOP L&N Speedomax M - MCR Al B23 RM- I'.me rn Ga mm. Gu:ird/ffenitor Camnta Level NMC GA-2TF. MOD 1 -- MCR Al B24
1:QU ll';1ENT (DESC.-FUNC.) !?FR r10 DEL, TYPE Olt CAT # CLASS LOC ENV ItEQT ENV ,QifA!.
- 11) #
Forr% a r er Sys tem
!!otor R9ller Feed Pump WEST 18N6512 -
TB A9 B3 " ~ P Motor Condens:ste Pump WEST 18N8216 - TB A9 D3 BAILY Att MCR Al B22 GG-SEV- Pneum Cntrl Sta F W Flow - Stm Gen BAILY KP-1320A - TB A9 B22. SC-PIT- Press Xmitter Level Xmitter Stm Ccn 11AILY BR-116X -- VC ALO B25 SG-LT-Ma in Coolant Drain T. Sampling Systens Loop Drain LIMIT SMA-000 -- VC A6 B13 VD-:10V- Motor Oper. VD-:;0V-509 Motor Oper. Pressurizer Drain LIMIT SMA-000 -- VC A6 B13 VD-MOV-510 Motor Oper. Drain !!cader LIMIT SMA-00 - VC A6 213
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10 f EQUIPMENT (DESC.-FUNC.) .MFR It0 DEL, TYPE OR CAT # CLASS LOC ENV REQT ENV QUAL LPST, Shutdown F. Spent Fuel Pit Coolinn System SC-MOV- Motor Oper. Shutdown Cooling Inlet / Outlet LIMIT SMA-1 , VC A6 B13:
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P-23 Motor LPST Cooling Pump WEST 19N3369 - PAB A4 B3 P-21 Motor Spent Puc t Transfer Pitmp WEST 19N3370 - PAB A4 33 Prensure Control and Reifef System PR-:iOV-512 Motor Oper. Press Sol Re1 Stop Valve LIMIT SMA-00 - VC A6 B13 Pit-SOV-90 SOV Press Solenoid Relief Valve MMM - VC A6 B34 Per.t Accident flydronen Vent System FN Motor Post Accident Recirc Fan WEST 72Y51238 - VC A6 B26 liv-SOV- SOV Ilydrogen Sample ATKOM URAMIC 30,000 Series -- VC A4 B21 P r ien ry Pur p Scalwater Systen P- Motor Seal Tank Makeup Pump RELIA M484 - PAB A4 B3 P Motor Purification Pump GE SK4234A12 -- PAB A4 B3 i
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- 11) # EQilIP!!ENT (1) ESC.-FUNC. ) 11FR PODEL, TYPE OR CAT # CLASS LOC. 'ENV REQT. ' ENV - QilAll I
l l- . Electr1 cal Equil pie n t j i r . DG- Generator. Emergency Diesel Gen DELCO E-4859VB IE PAB' A5' B27 i DG-LSC-2 Level Sv Level Cntrl Day Tnk GFJ1S .. LS ' 800 IE, PAB- 'AS ,
.. B 2 8 . '
DG-SLGV-4 SOV Diesel Cen Day Tnk Fill Valve ASCO 8211856 IE PAB AS .B20 Relay Solid State / Level Cntrl Day Tnk GEMS 28196 IE PAB A5: B'28 No 1 Battery EXIDE FOP-15 .IE SWGR 'A3 - B31 No 2 Battery EXIDE FOP-19 IE SUCR A3 .B3 - No 3 Bactery C M) KU-L 5 IE PAB A5 'B3 No 1 Battery Charger - MG Set EPCO 70-D IE SWGR A3 B3' No 2 Battery Charger - MG Set LPCO 70-D IE SUGR A3 ~B3 No 3 Battery Charger - Static .C6D-ARR130H IE PAB' ;A5 B3 No 1 Battery Switchboard WEST .IE SWGR A3 B3 No 2 Battery Switchboard WEST IE SWGR 'A3 ,
.B3-No 3 Battery Switchboard WEST CDP IE PAB. A5 'B3 No 3A Battery Switchboard WEST G-10P IE PAB A5 B3 No 3B Battery Switchboard WEET WFB-2W IE PAB A5 B3-30 Volt Emergency bus 1 GE ARD-5 IE PAB A5 n3..
480 Volt Emergency Bus 2 GE AKD-5 IE PAB AS B3. -y f
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%'r 1D # EQUIPMENT (DESC.-FUNC. ) ,MFR.MODEL, TYPE OR CAT # CLASS LOC .. ENV_REQT~ -ENV. QUAI.
480 Volt Emergency Bus 3 GF,AKD-5 IE PAB AS B3 430 Volt Emerr,ency F1CC 1 WEST YS-1718 IE SWR A3 .B3 , 480 Volt Emergency MCC 2 WEST TYPE-W IE PAB A5- B3 WEST S0-18N7679 SWGR - A3 B3' Vital Bus Inverter (M-G Set) IE Vital Bus Distribution Cubicle WEST S0-18N7681 IE SWGR A3 _ B3 i , 4 }, Terminal Block 12 Point MARAT TB-6000 Series IE VC* All B29 Terminal Block 12 Point WEST 542247 IE VC All. B29 Penetration Assembly CBICO -IE 'VC- All. .B30 Control Switch GE SBM IE MCR- 'Al .3' Relay over/Under Voltage (CV-7) WEST 1875524 IE MCR Al B3 Relay Voltage (SV) WEST IE MCR Al B3-Relay Aux Self-Reset (IIFA) CE IlFA51A (Code-42) IE MCR Al B3 Relay Aux Electric-Reset (IIFA) CE IIFAS4E (Code 60) . IE . MCR Al B3-Relay Aux Self-Reset (HFA) GE !!FA51A (Code 51) IE MCR Al B3 - Relay Reverse Power (CRM-1) WEST IE MCR Al B3 Relay Time Delay TDPU 2.5-50 Sec. AGAST 2412 PD IE MCR Al B3 Relay CE I!GAllJ IE MCR Al B3 i
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I I) # EQUIPMENT (DI'.SC. -FUt:C. ) MFR f10 DEL, TYPE OR CAT # CLASS LOC ENV ItEQT ENV -QtlAI, Selector Switch for MOV-1 WEST OT211 IE MCR Al B3 Relay Aux Iland Reset (40 Stage) WEST WI. IE MCR Al B3 Cable flineral Insulated IE VC* All B31 Cable Polyethylene /PVC IE VC* All' B31 Cable Butyl Rubber /PVC IE VC* All B31 Cable Silicone Rubber / Asbestos IE VC All B31' Cable XLP/ Neoprene (or Ilypalon) IE VC* All B31 Cable PVC Shicided IE VC* All B31 Cable Coaxial IE VC* All B12 Instrumentation PT-227 Pressure Transmitter VC Press. ROSMT 1151-GP -- PAB A4 B32 Power Supply LAMBD LCS - MCR Al B8 Indicator ANALO P12455 - MCR Al B33
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. . 6 Key to Abbreviations Used on Equipment List Manufacturers WEST- Westinghouse BAREJ Barton AGAST Agastat BAI LY- Bailey FP Fischer 6 Porter LAMBD' Lambda ES Electro Switch RIS Rochester Instruments SANG Sangamo ACR0 Acromag LIMIT Limitorque ebb;CO E1cetric Machinery GE General Electric FMGNT Magnetrol A/B Allen Bradley BARKS Barksdale ASCO Automatic Switch ATKOM Atkomatic Valve ROShff -
Rosemount NMC Nuclear Measurements - RELIA Reliance C6D C6D Battery EPCO Electronic Products FMRAT Marathon CBICO Chicago Bridge 6 Iron 1 LBN Manning Maxwell and Moore COUCH Couch ordnance SIGMA Sigma Instrument-STAT Static 'O' Ring l EXIDE Exide Battery GEMS GEMS L6N Leeds 6 Northrup J Location MCR Main Control Room VC Vapor Container SWGR Switchgear Roem PAB Primary Auxiliary Building SCRN Screen Well House TB Turbine Building VC* Equipment, such as cable which is located in the vapor container, but also is used throughout the plant
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- l EQUIPMEST'LlST ATTACllME!;T A ENVIROSMENTAL REQUIREMENTS LA.1 The" environment in the main control room is air conditioned with I temper.tures maintained at 700 + 10 F. Equipment is ' mounted in '
cabinats, on racks within control boards, or mounted on a control board,-and there are no adverse vibrational effects. The room has been protected f rom the environmental ef fects of piping -system breaks. l l J The bounding environmental' condition for this equipnent is.the' occurrence of loss of offsite power, wherein the source of power i for the air conditioning systca is Icst. Ilowever, in 17 years o: plant. operation, this event has occurred only once during the great Northeast. blackout in 1965, and lasted for only 20 minutes. Therefore, it can reasonably be assured' that power will be restored within this time frace,;as each transtission line from the plant is' connected directly to a hydro-electric plant.
'A.2 The attached Table A.1 presents the transients.and the protection provided by the reactor protection system for these transients.-
Environmental _ require:ents for each reactor protection detector function are as.follows:
- a. Ilich Moutron Flux Pouer Rante and Mich Startup Rate The neutron detectors for these channels are located in sealed thir51cc in the neutron shield tank, which provides a controlled environment at a te perature of 100 F to 110 F. Coaxial cables are run fren thy0 detectors to the control room through a sealed drybox (105-115 F) around the top of the reactor vessel, and via conduits and penetre.tions (75-950 F along the route). i Connectors are of the ste.ndard coaxial cable type. None of the transients' requiring protection from these channels affect the
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normal environcental conditiens of the detectors because of the 9- double seal between the thimble and the containment air space. l
- b. Reactor Coolant Pumo Low Current flow The redundant current trans fo rcers and equipment for this !
protection are located in the controlled environment of the switchgcar room and the norcal environment is unaffected by the loss of flow transient. Backup protection for the less of flow trahsient is provided by four differential pressure detectors, with one connected across the primary side of each stca generator. The signal frem the detector is transmitted through eineral insulated cables, and ! I in cables in conduit via penetrations to the control room. The environment of the detectors and cables within the containeent or outside the containment is unaffected by the transient. 1 4
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- c. Pressurizer Low Pressure and' Low Main Coolant ~ Pressure l
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'These channels provide redundant reactor protection for events which cause low main coolant system pressure. The low main l coolant pressure channel also provides one of the initiation .1 signals for the , safety injection actuation. The LOCA 1 environmental conditions for . these detectors are shown on the l attached LOCA pressure and temperature curves (See-Figures 1 and:2). See Section=A.6 for conditions during the steam line I break.
The signals from these detectors are transmitted through mineral I insulated' cables and cables in conduits via penetrations to the' ' control room. Normal temperatures in the containment vary from . 75 F to 950F. l
- d. Pressurizer Hich Water Level -(Wide P,ance) .
This detector is located in the pressurizer compartment and the
- s,1gnal is transmitted to the. control room through a mineral insulated cable and cable in conduit via a penetration. Norcal temperatures 'in the compartment vary frca 900 F to 95 F. For reactor. protection functions, the environment:at the detector- 1 does not change. This detector and the identical narrow range :
detector areLnot required during the LOCA DBE, but provide pressurizer level indication during main steam line break conditions, which are discussed in Section A.6. 1
- c. Steam Generator Low Water Level l
One of these detectors monitors the water level in each steam gencrctor. With the exception of steam line break within I containment, none of the transients requiring protection will affect the normal environment of the detectors or cables. For steam line break inside containment this channel provides a backup trip and provides indication of level over the long term. See Section A.6 for conditions during steam line break.
- f. Turbine Trio This trip is initiated by reactor protection relay circuits located within the main control room, which actuate a turbine trip solenoid coil which is part of the turbine equipment. The
. loss of load transient does not affect the environment of the
. protection circuitry. Although this trip provides a backup !
f unction, no credit is,taken for it.in the safety analysis.
- g. Manual Reactor Trip Manual reactor trip is actuated by three pushbutton switches located on the main control board. Since manual trip can be actuat'd at any tice, the limiting environmental conditions occur 2
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1 L+ - - o; o , V .* . during ' loss of offsite-power where air conditioning is lost in < the main control room. 1 A.3 The awitchgcar room is located on the second floor level of:the turbine building and contains the following equipment: 2400V switchacar, . 2400/480V transformers, 480V switchgear and motor control centers,Lcain coolant pump current (low flow) trip cabinets, vital a-c motor generator set and vital bus. cabinet, 125V d-c No. 1 and No. 2 batteries (cnclosed), battery chargers, d-c switchboard buses, reactor scram breakers, and safety injection system valve contactors. The environment of the area is controlled and is protected against Lthe effects of pipe breaks in the turbine building and LOCA radiation levels. The limiting' environmental condition in this'arca is caused j by the loss of of f site power where a loss of ventilation would occur. ' llowever, at the same time, the 2400/480V transforcers would lose their excitation and cease being a heat source. Since power should be restored within 20 minutes, based on previous experience, and that there are no other significant heat sources, the effect of the event on the environment is 'not significant. This was demonstrated during the 1965 Northeast blackout in that no equipment operational abnormalities occurred.
-A.4 -Equipment located in the Primary Auxiliary Building which is associated with the ECCS and containment isolation systems, provides protection for the LOCA and main secam line break D3E's. Since this equipment is outside containment, it is not subjected to the steam '
and pressure environmental conditions. Being located adjacent to the containment, it is subject.to LOCA 30-day accumulated radiation
, dose of less than 10 3 R, using the source term based on 100% of the noble gases and 50% of the halogens uniformly disparsed in the . ,
containment atmosphere, and taking minimal credit for the shielding effects of the PAB Structure. If it is assuted that the safety injection system operates, this radiation dose level will be greatly l reduced because fuel daeage will be minimized. 'Therefore, the f calculated dose levels have been reduced by a factor of ten throughout 1 Attachtents A and B, and still will be conservatively higher than the donc rates expected using realistic assumptions. In the general areas of the first and second floors of the PAB, including the accunulator, safety injection pumps, component cooling pumps, and instrumentation; the nonnal radiation icvel is 0.00lR/hr. In the cubicle area where most pumps and valves are located, the normal Icvels vary from 0.01 to 0.03 R/hr, giving a total integrated 3 exposure to date of less than 5 x 10 R f or this equipment and cables. The valves, CI:-Itov-521 and PU-MOV-541, are located in areas of the PABwheretheradiationlevg1is0.8R/hr,andtheintegrateddose The normal temperature variations to date is approximately 10 R. at this location are from 65 F to 900F. Specific operational requirements are as follows: SI-!!O V-1 Operation is required during the injection phase of the 3
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. 5 LOCA. Valve operation occurs within~ the first few minutes of the
- LOCA. -
CH -MO V-521 ' Operation of this valve is required during the recirculation p ase h of a LOCA and prior to cold-shutdown following a steam line break. CS-MOV-529 & 540 & DW-MOV-655 These valves are part of the Chemical Shutdown Sys tem and are used, if ' required, for emergency boration following main steam line; breaks. Operation of these valves may be' required at any time prior to cold shutdown.
- PU-MOV-542 throuch 548 These valves are part of the post-LOCA ;
recirculation system and operate approximately twenty minutes into the LOCA. They.are not required during'a steam line break. PU-MOV-541 ThisEvalve operates on the containment isolation signal within' seconds after the LOCA. P-15-1,2,3 The charging pumps are used for hot leg injection fol16 wing a LCCA and for emergency boration, if required, following main steam line breaks. Initial operation of the pumps following a LOCA is af ter 20 hours, while emergency boration may occur in the first hour. Pump operation could continue for several months. NS-SOV-45, 4 6, 4 7, 56, 5 7, 5 39 & 540 These valves are part of the accumula tor control sys tem. Operation is required during the first minutes of a LOCA. SI-PP-LP1, 2, 3 & HPl. 2, 3 The low pressure and high pressure safety injection punps are required during the injection phase of a LOCA and a rupture of the 24" steam header which is outside the vapor container.
. Operation during the LOCA is for the first minutes up to several hours. Operation following a steam line break may be at any time prior to cold shutdown.
SI-LI-l The safety injection tank level transmitter provides an indication of tank level which is required up to several hours af ter
, the LOCA.
P-16-1 & 2 The purification pumps are used for post-LOCA recirculation. Initial. operation is f rom approximately 20 minutes i to 3 hours following the LOCA. Operation may' continue for several nonths. Seal Tank Makeun Pumns These pumps provide seal water for the purification pumps and low pressure surge tank cooling pump. - Initial operation is from approximately 20 minutes to 3 hours 4 _m __ . , . . _ . _ _ _ _ __ . __ _. . _ ,
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- following the LOCA. Operation r:ay continue for several 'nonths, p-23 The low pressure surge tank cooling pump tay be required after i J
a steam line break. Operation may continue for several months. l P-21 The spent fuel transfer pump is used to cool the spent fuel pit water, and it operates continuously. p-22A 6 3 The component cooling water pumps transfer heat from the low pressure surge tank during a steam line break and from the spent fuel pit pool cooling vater to the service water. A.5 Equipment located in the Pricary Auxiliary Building which is associated with the emergency power system provides protection for the loss of offsite pouer event. Since the local ventilation is operated by the diesel generators under this condition, there is no change in environment for this equipment. The normal temperature i variations at this general location are from 65 CF to 90 F. Within ! l the diesel generator roces the temperature varies from 55 F to 100 C F. Normal radiation level is 0.001 R/hr. The 30 day integrated f LOCA dose is <10"R. ( i 1 A.6 Equiptent located within the containment which is operated during l the LCCA DEE is subject to the steam and pressure conditions shown l in Figures 1 and 2. No valves or motors have to eperate during the ; injection phase. Those required during the recirculation phase are l i exposed to the peak conditions of the transient, but do not have to be operated for at least tuency minutes, when conditions are ,
- considerably less severe. l Detailed calculations of the containment transient resulting from rupture of a rain steam line inside containment have not been completed at this tire. Sceping analyses have, hevever, been perforced and indicate that the peak contain:ent pressure will be less than that resulting frce the LOCA DBE. These scoping analyses also indicate that although the peak vapor space temperature may exceed that occurring during the LOCA DEE due to superheating of the bloudoun fluid, it will decrease below the LOCA DBE values in the long tern.
The nernal temperature variations are from 70 to 110 F, depending on the location of the equipment in the containnent. Radiation levels at pouer operation are approximately 0.04 to 2R/hr in the general loop areas, 0.25R/hr near the pressurizer, and O.30lR/hr outside the biological shield unil. The loop cutout valves, which are mounted on the loop piping are at 2C3/hr which gives the an integrated doce to date of 3 x 10 2. The integrated doses to date in general areas are approximately 3 x ifn in .ne loops, 4 x 10% near the pressurizer, and 2 x 13-R cutside the sh!D eld wall. The 30-day integrned dose frc: the LOCA is <2 x 10 R at the center of the containment and <10"n outside the chield wall. All valves inside the vapor container which are required to operate 5
5 [- [o (o; during or. af ter a- LOCA will not' be submerged when the maximum amounts of~ water areLinjected.
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' Specific operational requirecents are as follows:
1 SI-MOV-22, 23, 24 & 25 The loop fill header isolation valves are 1 partt of the~ Safety Injection System and may be required during the , i- . recirculation phase of a LOCA. They. are cperated f rom approximately thirty; ninutes to several hours.after the LOCA. ] PR-MOV-512 & PR-SOV-90 These valves are part of the pressure control and relief. system. Operation cay be required during the recirculation phase of a- LOCA f rom approxicately twenty. minutes to several hours after the LOCA.
'These valves-may also be required following a' steam line break.
Operation of these valve cay be required at any time prior to cold I shutdown. ,
. SC-MOV-551, 5 52 - 5 53 & 5 54 . Shutdown Cooling inlet & outlet valves may be required during the recirculation phase of a LOCA. 'They.cust operate from approxicately twenty minutes .to several days af ter. the LOCA.
VD-MOV-509 & 510 The pressurizer. drain and drain header valves are E operated during the recirculation phase of a LOCA and as a second i backup bleed path for cain steam line breaks. They are operated from approximately twenty ninutes to several days af ter the LOCA. l I M -18, 1, 2, 3 The-post accident recirculation fans may be required 3 to operate during the recirculation phase for conths af ter the LOCA. They will not be started until one hour.after the LOCA. HV-SOV-1 & 2 These are the post-accident hydrogen sample valves. 1 Periedic operation of these valves is required from several days I to seve ral conths folicwing 'a LOCA. 4 Cll-MO V-5 2 6 This valve is in the bleed line and may be required as a backup bleed path during tain steam line breaks inside containrent. MC-MOV-301, 302, 309. 310, 318, 319, 325 & 326 The nain coolant loop cutout valves are recuired for a steam line break outside the vapor container.to isolate the affected steam generator. Valve operation is not required for a steam line break inside the vapor container therefore, the environmental conditions do not change when operation is required. .
\D-MOV- 505, 506, 507 &' 508 Although not required, any one of the
. loop drain valves can provide a backup for VD-MOV-509, which in
, conjunction with VD-MOV-510, provides a second backup biced path following cain steam line breaks.
6
.~ - . .- _ .. . -. ._ - .- --
-l y' ' ;,. .
SI-TT-1,- 2, ' 3, & ' 4 . The safety injection loop flow transmitter provides indication' as to the broken-loop' in a LOCA. The transmitters are, located outside-the biological shield wall and'have to operate
-long. enough (up to one hour) into the DBE to allow determination of differences between.the four: loop flows. Normal temperatures at the transmitters are 75 to 85 F. !
'Sl-PS-14 The pressure switch monitors pressurizer pressure and '
Anitiates one of the. redundant. safety injection actuation signals within' seconds after the LOCA DBE. It is located outside the 1 biological' shield wall.- Table A.2 sutmarizes the operational requirements of the equipment j within~ containment.
. A.7 The. service water pumps are located in the screen well house where norcal temperatures . vary f rom 50-100 F. The pumps provide cooling water for purification pucps'during the recirculation phase of LOCA, for component cooling during the steam line break, and spent fuel pit cooling. The limiting conditions.for these' pump motors occur '
during the loss of of f site power when ventilation is los t. As shown in Section A.1, pouer should be restored within approximately 20 minutes, and f or this amount of time, there are no significant environmental changes. A.8 The low temperature overpressurization (LTOP) pressure transmitter is connected at the same location as the main coolant pressure detector. It normally functions under normal operating conditions
- for LTOP, but provides backup pressure indication to the cain coolant pressure channel during LOCA conditions. This channel was installed in 1 77, so the ints --ted radiation dose to date is less than 2 r x10{R.
A.9 The steam driven etergency boiler feed pump provides secondary side cakeup in event of a loss of of f site power' occurring simultaneously with any steam line break. If power is not lost, the boiler feed " purps and/or condensate pumps may be used following a steam line break. In event of loss of of f site power, the condensate pumps are capable of being operated by the diesel generators as a backup to i tr e steam driven pump. A further backup is provided by manual j connection of spool pieces to provide charging pump discharge flow l J to the feedwater header. These pumps are in the turbine building and have been protected against the effects of a steam line break. Normal temperatures in this area vary from 70 to,90 F. Operation of the putps may be J j required for several days following the DBE. Also located in this general area are the pneumatic steam generator pressure transmitters which provide pressure indication during the i DLE.
Reference:
See References B.1.2 and B.l.3 in Section B.l. 7
' (h r%
l Q.) \ -)
?
p A.10 The stent generator level transmitters are located in the =ain coolant i loops and are required during the initial stages of the cain steam t line break to determine initial steam generator feed there are no requirements. changes in I If the break is outside contain:ent, If the break is inside containment, the transmitter environment. bounding environmental conditions are as described in Section A.6. II A.11 For cables, terminal blocks and penetrations in the containment, , the bounding environnental conditions are determined by the Since , to which they are connected. requirements of the equipment are genere ty the same types that i-the cables outside of containnentthe bounding environcental conditions are used inside containment, for nineral insulated cables, all cables ; are euch 1 css severe. Except and terminal blocks in contain:ent are installed in conduits or protective boxes. i 1 i I l l l l e 8
O T^8te ^ 1 - D j
' RPS TRIPS POTENTIALLY: ACTIVATED ;
RPS TRIPS POTENTIALLY ACTIVATED TRANSIENT 1 2 3 4 S 6 7 8 9 i I Loss of Feedwater Flow- X X X 2' ' Rod Group. Withdrawal X- X X. X X 3 Loss'of Load X' X X X 4 Loss of Main Coolant Flow X X Loss of Offsite Power S' X X X X X. 6 thin Coolant System Depressurization X X: X 7 Excessive Load Increase X X X X r 6 Boron Dilution X X X X X i 9 Control Rod Drop X X X X 10 isolateu Loop Startup X , X X X X ) 11- Steam Generator Tube Rupture X X X 1 1 12 Rod Ejection X X X X X I 13 Steamline Rupture X X X X X X 14 LOCA X X X
- RFS Trio Functions 4 j
- 1. High Neutron Flux Power Range 7. Low Main Coolant Pressure l
- 2. -Reactor Coolant Pump Low Current Flow (2/4) 8. Manual Reactor Trip ,
- 3. Pressuri:cr Lou Pressure 9. ' iligh Startup Rate
- 4. Pressuriner High Kater Level
- 5. Steam Generator Low Water Level E. Turbine Trip
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9.; f z. N h , EQUIP 12NT LIST ATTACH 35NT B
- ENVIR0!alENTAL QUALIFICATION b B.1' Components of the reactor protection system located.in the control room are .the 'samel type. of components that were used in contemporary l,
i U.S. !lavy nuclear submarines and are qualified f or tilitary usage. lj Although no ' qualification test data is available; the equipment is
~
j .. t of rugged military . type construction, uses simple and straightforward J- magnetic amplifier circuits,'and has been tested:for compatibility
' and overall system performance. The equipment is located in a controlled air conditioned environment protected frca the environmental ef fects of a steam line break and LOCA radiation levels.
The accuracies"specified for the basic0 circuit units The are bounding based on an ambient temperature variation of 80 F i 40 F. environmental conditions for the equipment result from t the loss'of loses its power offsite power wherein the air condit on i ng i equ ipten '! source. The original plant design did not include control room air conditioning, so the equip:ent did operate for about 10 years under the conditions which would result from this transient and has operated-satisfactorily during and since these conditions. The air conditioning was installed f or operator ' comfort, rather than for equipment, perf o rmance . The protection system equip:ent is under a periodic maintenance and testing program wherein equipment is o calibrated and operationally tested during each refueling outage
-to verify continued satisfactory operation.
References:
B.1.1 Westinghouse, Descriptive Bulletin 57-452, " Type FN Reactor Coolant Control and Instrumentation.'! B.1.2 " Report on Effects of a Piping System Break Outside Contain:ent at Yankee Nuclear Pcwer Station, Rowe, i f Massachusetts" July 1973. B.1.3 " Report en Effects of a Piping System Break Outside Contain:ent, Supplemental infor ation, at Yankee Nuclear Peuer Station, Rowe, Massachusetts" September 1973. B.2 The Model 386 differential pressure transmitter has been tested under post-accident steam environ:ents. These. tests are documented by In , F.ef erences B.2.1 and B.2.2 which are on file at the Barton Co. . " transmitters were successfully tested to a total dose addition,0 th,'e of 2 x 10 R per Reference 3.2.3. The main-coolant flov transeitters are specified for operation from 60 F to 2000 F but they only have to operate under their normal environmental conditions. In 17 years of operation with maintenance, .' calibration and testing perferred at each refueling, these transmitters have continued to perform reliably. I
Reference:
B.2.1 Final. Report F-C2667, "Perf or ance Tect of Three 1 9
, ,fm n Q V Differential Pressure Transmitters in a Simulated Reactor Containment, Post-Accident Steam Environ = cat: FIRL.
B.2.2 Final Report F-C3076, "Perforcance Test of Two Static Pressure Transmitters in a Simulated Reactor Containment, Post-Accident Steam Environment" FIRL. B.2.3 Letter, ITT Barton to YAEC, dated 3/12/76. B.2.4 Barton Product Bulletin 199-2-1 1.3 Certain electrien1 equipment was included in the original Yankee plant design because of its previously proven reliability in utility applications. These components are in the general areas of protective relays, ticers and auxiliary relays, transforcers, circuit breakers, cotors, batteries, control suitches, and other power circuit controlling equipment. This equipment had to have a demonstrated reliability because of the large economic penalties uhich are incurred when f ailures occur in the suitching large blecks of energy in power generating stations, substations, and switchyards. Components with this bachground of reliability were deemed satisfcetory for safety applications, installed in environments suitable to '; heir application, provided with apprcpriate periodic and preventive naintenance, and have continued to perforn reliably through 17 years of continuous operation. When reliability has been deronstrated in this nanner, similar equiptent has been specified for use in design changes and new installations. As noted in Section A.4, sore notors are installed in the PAB in cubicles in an area where radiation levels are higher than normal because of the fluids in the systems. The integrated :3lose to date for these totors after 17 years of operation is 5 . 10 R When the LOCA 30-day integrcted dose of,<10 R is superimposed on this, the total dose is approxicately 10"R which vill net danage the motors . or their cables. Motors associated uith totor operated valves are discussed in Section B.13. Breakers, motors, transformers, switchgcar, batteries, motor control centers, M-G sets, and protective relaying are provided with , continuing periodic taintenance and testing programs to assure l continuing prcper operation and to detect any conditions which uould ' indicate potential wear and other types of incipient failures. Any conponents chich have known f ailure rates, such as M-G set brushes and bearings, are rcplaced en periodic in te rva,is in advance of l anticipated failure. Vibrction readings are tacen conthly on the diesel generators, cotor generator sets, and all cajor motors outside of the vapor container, and readings are analyzed and plotted to provide continuous trends which vill indicate potential failure. The capacitics of the statien batteries have demonstrated by discharge tert and are equal to or greater than the capacitics required to 10
s
. . CT '(h
\_) ti supply their maxicun loads. Feriodic battery service tests en a ref ueling interval have demonstrated that the batteries will supply their anticipated loads after a loss of offsite power.
B.4 The reactor coolant pump low current trip cabinets are lecated in the controlled environment of the switchgear room and use co ponents similar to those previously discussed in Section B.1 and 3.3. B.5 The pressurizer pressure and main coolant pressure transmitters provide reactor protection for events which cause main ecolant system depressurization. In addition, the main coolant pressure detector provides actuation of one of the safety injection trains at a pressure I l below the reactor protection system pressure setpoint. The bounding environmental conditions for these detectors and their l cables during the LOCA DBE is shown in Figures 1 and 2 of Attach:ent l A. The safety injection low pressure setpoint is reached vithin ! 10 seconds; therefore, the reactor protection scran point is reached l in a shorter time period. I l The anbient temperature at the transnitter location varies frc: 75 i to 95 F and the maximum specification allowable continuous a:Sient temperature of the transmitter is 158 F. Because of the large mass of the steel detector housing, 170 i 5 pounds, and the very short time that the temperature is above 136 F, the internal terperature of the housing should not exceed the 158 F ambient tenperature allouable for normal operation. Therefore, there will be no effect ! on the transnitter internal components before the reacter protection and safety injection actuation f unctions are initiated. l The containment pressure will have no effect on trans:1tter eperation l because the housing has been tested to an internal test pressure l of 4500 psig. I l These detectors are part of the '.lestinghouse Type F'.; equiptent, and, similar to the remaining circuit components in the contr:1 recr (see Section B.1), are constructed to cilitary specifications. Although no qualification test data is available, shock and vibration tests to military standards were approved by SUSl!IPS letters. The transforcer winding is encapsulc ted and the electrical heusing is l explosinn proof and qualified watertight in accordance with "IL-STD-100 and MIL-E-2036. Fron the detector to a junction box outside the concrete shield wall, the signal is carried in nincral insulated cable. Frem the junction box to the penetration, cable with polyethylene insulatien and a polyvinylchloride jacket is run in steel conduit. For discussion of the environmental qualification of the cables, see Section 3.31. Redundant indication of pressure thrcugh the DBE is also provided by the independent low temperature overpressurization channel .:hich is qualified for LOCA conditions (See Section B.23). 11
O i v O v 6 These channels and the , essurizer vide range level channel (Section B.6) have been maintained, 'calibrateJ, and tested at each refuelidg since ini.tial plant operation. In addition, operators perform a check of each channel at least twice per day to verify continued proper operation.
Reference:
3.5.1 Dailey Meter Co., Drawing No. H6610lS4, Rev. A, Title " Electrical Pressure Transmitter" B.6 For all of the transients for which the pressurizer uide range level detector provides a reactor protection signal, there is no change in detector environment. The , cide range and narrow range detectors provide pressurizer level indication after the steam line break. The level detectors (wide range and narrow range) are constructed to the same military specificaticas as the pressure detectors discussed in Section B.S. The caly difference is that the level detectors are of the differential pressure type. The cable arrangement is the same from detector to penetration. As discussed in Section B.5, the large mass of the detector should allou the initial transient temperature to pass without affecting operation of the internal componencs, and for the long term indication function, the pressure tight and waterproof construction should provide adequate protection frc= the environment. Radiation levels should not change significantly af ter the steam line break.
Reference:
B.6.1 Eailey Meter Co., Drawing No. H6610183, Rev. A, Title " Electrical Dif f. Pressure Trans. Low Hd." B.7 The narrow range steam generator level transmitter is designed for post accident operation uith hi 53 temperature specifications, epoxy paint, specici seals, and radiation hardened transisters, and specified to be tested to Cembustion Engineering Test ?recedure, I C E-TP -1. Test conditiens were ene hour at 302 F and 70 psia, ramp down for two hours to, and then for five hours at, 22b F and 20 psia. Since these tests were of a generic nature, the documentation of test results is probably en file at the Fischer and Porter Company. Yankee is presently trying to verify this. Separate radiation testing was perf ormed to qualify the transmitter to at least ten megarads of gamra exposure. Documentation of these tests is availabic at the Yankee Westboro of fice. The sequence in which these tests were performed is not pertinent because the accumulated radiation dose during the steam line break is insignificant compared to the tested level. The cable used to connect the transmitter to the penetration has crosslinked polyethylene insulation, shicided, with a Hypalon jacket, and is in conduit.
Reference:
B.7.1 Test Procedure, ICE-TP-1, Combustion Engineering. 12
P 7.....-.._. . . . . . . 9 = .
- U)<g O B.7.2 Engineering Report, " Nuclear Radiation Invcstiga tion," Fischer and Porter Co:pany, September 14, 1970.
B.S Lanbda power supplies are designed to meet military env11. , mental specifications and for continuous operation from -20 C to +71 C ar..bient tempera tur e. These requirements far exceed the environcental l requirements of actual usage. Specific specifications are as follows: LC Series: MIL-STD-810B, MIL-E-5272C, MIL-1-6181D LM Series: MIL-STD-8103, MIL-1-16 910, MIL-E-5 27 2C, MIL-T-4807A, MIL-S-4970A Since the power supplies are connected to instrutents which provide continuous indication in the rain control room, any deviations in performance are readily detected.
Reference:
B.8.1 Lambda Specification Sheets for LC and LM Series Power Supplies B.9 These bistables are specified for operation in c=hient tenperatures ranging frc: -30 to 150 F which allous adequate cargin over the actual conditions in the control room. A ceriodit testing program is in effect on a conthly basis to allou detection cf any deviations in performance. Since installation in 1972, no abnormalities in perf ormance have been detected.
Reference:
3.9.1 Rochester Instrument Systems, Iulletin No. 214 B.9. 2 Rochester Ins trueent Systems, Iulletin No. 401 B.10 This rwitch was installed in 1972 when the stean generator lev level trip channels were added, and is of the same rug;ed cons truc tion as equiptent discussed in Section 3.3. Although designed for heavy duty application on power switching circuits, it is used only for suitching signals in the milliampere range, and only during channel test. Therefore, it does not have to function during the tir.e when protection is required. B.11 These r.eter relays are not required for the reacter protective function, but provide an alarm to indicate power supply or channel f ailure and provide long term indication of sten generator level after a ster.:. line break. Indicators sinilar to thf.s have been used extensively at both Connecticut Yankee and Maine ';ankee plants for protective f unctions and have a demonstrated reliability for providing a continuous indication function. They are speci fied f or operation fron 60 to 130 F. P.c f e r e n ce : B.11.1 Sigta specification Sheet, Series 9220 , I l l f i 13 l 1
l
. , q n '
V U I l l l B.12 "cutron detectors used for power range applications are designed to operate in high neutron and gamma fields for a specified period of exposure. In the firs t few years of operation, the sycptors of initial radiation damage . to the detector, coaxial connectors, and coaxial cables located within the detector thitbles and dry box uere evidenced by the occurrence of a few instantaneous " pips" on the normally stable power range level indications. With' relative in-thimble radiation exposure thus determined, a program of periodic replacecent of in-thimble and dry box components was established to preclude failure due to radiation damage. The controlled temperature of the neutron shield tank keeps the in-thimble components well within their specified temperature ratings of at least 80 C (176 F) 1 The coaxial cables between the loop area and the penetrations are i subject to comparatively insignificant radiation levels, so routine I replace:ent is not required. I
Reference:
B.12.1 Uestinghouse, Descriptive Bulletin 57-451, " Type FN Reactor Suclear Control Ecuipment." B.13 All original notor operators installed in the vapor container and referenced in Section A.6 vere specified to have totally enclosed motors ..*ith Class H insulation, suitable for eperation in an area j with 50-75 R/hr continuous radiation dose rate. Two Totor operators, PU "0V-541 and CH-MOV-521, which are installed in :he PAB in areas with hi;h radiation levels (see Section A.4) are clse specified to these recuirerents. (Reference B.13.1) The four additional motor operators (SI "0V-2 2, 23, 24, 25), which were installed in the vapor container in 1972, are also totally enclosed and have Class H insulation. Sin 11ar cotor operators having Class H insulation have been successfully tested under post accident steam conditions (Ref e rence 3.13. 2 ). The test conditions for these rator operators exceed expected DSE co-ditiens in the vapor centainer. The retaining coto: cators outside the vapor container are located in the PA3 (S e ct io r. 4) and are not subject to the severe environmental condit ons which result from the LOCA or rain steam line break. These notor operators havi Class B insulation as a minimun. Sin 11ar motor operators have been successfully tested under I steam tenperature and pressure conditions (Reference 3.13.3). Motor operators with Class B insulation C have also been successfully operated after irradiation to 2 x 10 F.. (Referenen B.13.4) Since there are no steam conditions in the PAB and the LOCA radiation dose plus integrated cperational dose is less than 10 S ?., these motor operators are adequately qualified for their environnental. conditions.
Reference:
L.13.1 Specification #YS-621, Stainless Steel Sten Leakof f Manual and Motor Operated Valves in Radioactive Service. l l 4 14 1
o x {al w) l l B.13.2 Qualification Test of Limitorque valve Operators j in Siculated Reactor Containment Post Accident Stean Environcent, FIRL Report "F-C3441, Sept., 1972 B.13.3 " Performance Qualification Tests of Four Valve { Motor Operators", FIRL Report #F-C 4124, April, 1973 j 3.13.4 L' CAP-7410-L, Volume I of II, " Environmental Testing of Engineered Safety Features Related Equipcent", December, 1970. B.14 The safety injection tank level transmitter is specified with a pressure rating of 1500 psig, an eperating temperature range of - 20 _to 200 F, and meets 'ilL-E-5272 humidity test (24 hour cycle 68 to 158 F at 100!; relative humidity), which f ar exceeds its application and environnental conditions. The 30-day integrated LOCA radiation dose of <10" R will have no ef fect en the transmitter within the operational period of several hours.
Reference:
B.14.1 General Electric Measurement & Control Handbook, Section SO42A B.15 The GE pover supply vcd selected for this application because of extensive reliable use at the Vernont Yankee plqnt in similar i applications and f or its cc pa tibility with the safety injection l tank level transmitter. It is rated for ambient terperature ranges of 40 to 120 F.
Reference:
B.15.1 General Electric Measurement and Centrol Handbook, Section 8063-2C. B.lf This indicator is used extensively at the Vermont Yankee plant for i indication on protective cha .nels and has provided reliable service. It is specified for operation in an ambient terperature range of - 4 to 150 F, allowing adequate targin for its envirennent.
Reference:
B.16.1 General Electric Apparatus Handbook, Section 8075, page 104. B.17 The Magnetrol level switch asce=bly is made pricarily of 304 stainless steel ar.d is rated for 100 r at 500 psig. The switch eletent counted , in the assembly is rated for 250 F. The PAB tenperature and pressure are unaffected by the LOCA envircament, allouing adecuate nargin for assured cperation. Since this operates within seconds after j a LOCA, radiation dose is not a factor. l These evitches have been tested at each ref ueling f or five years without a failure. Referenec: B.17.1 Magnetrol Product Data, '4cdel 751 Series Liquid I Level Controls 15
(O 4 w) v 3.18 Ecing located in the PA3, these vapor container pressure svitches are not subject to a change in temperature or pressure conditions during the LOCA or steam line break events. The switching element is specified for operation between - 65 0F and 180 F, allouing considerable margin over the normal (or accident) environmental temperature variation of 65 to 90 F. Radiation level will increase during the LOCA event, but the switch operates at 5 psig containment pressure and will have completed its function before any increase in radiation in the PAB. These switches are similar to those qualified by GE for use in the Vermont Yankee plant protection systems. Information on qualification and operational experience at Vermont Yankee has been submitted in the referenced letter. 9
Reference:
B.18.1 Letter, YAEC to USAEC, subject: Additional Information for Prcposed Change No. 111, dated January 16, 1974. B.18.2 Static 'O' Ring Product Data B.19 The Barksdale pressurizer low pressure switch is designed with a weather-sealed housing and a proof pressure of 4000 psig with a temperature rating of -45 to 165 F. The pressure suitch operates within ten seconds ef ter the LOCA DBE. T,ecause the pressure switch is located outside the biological shield wall and the switch operates in such a short time period, the switch internals should not be adversely affected by the temperature increase. There will be no increase in radiation level in that short a time after the initiation of the transient. This prescure switch is redundant to the main coolant pressure channel signal and diverse to the two vap'or container high pressure actuation signals which are discussed in Sections B.5 and B.18.
Reference:
B.19.1 Barksdale Product Data B.20 The ASCO Solenoid valves have Class 1 coils and are designed to operate in a tenperature environment from o C to 180 C. Since these valves are all in the PAB, the design far exceeds the environmental i conditions.
Reference:
B.20.1 ASCO Product Bulletin 8211 1 B.20.2 ASCO Product Bulletin 8302 l B.21 The Atkomatic valves are of an explosien proof construction with Class li insulated coil. The valves are specified to operate FatisfJCtorily frCm minus 420 F to plus 500 F. These specifications surpass the environrental requirements and therefore the valves are considered qualified for their application. 16
p V U L In addition, the valves have been operationally tested nonthly for a period of three years without a failure.to operate. B.22 The Bailey pneuratic control stations for the feedwater system can l be manually adjusted to position the cain feedwater valves or the l bypass valves if required after a steam line break. This pneu=atic equiptent consists of a regulating valve which adjusts the air pressure on copper tubing which is terminated at a bellows or similar air-tight device. It is non-electrical, almost all totallic and , not subject to the failure modes of electrical equiptent. For 17 l years of continuous operation, the equip =ent has been given routine maintenance, and has provided essentially trouble-free, reliable se rvice. The steam generator pressure transmitters conitor the pressure of , the steam lines and transmit a pneumatic signal fron the turbine l building to a pressure gage in the control room. The transmitter l also provides disact local readout, uhich can be used for backup indication. B.23 The low temperature overpressurication (LIOP) pressure transmitter was installed in 1977, and is specified to maintain + 0.75% accuracv af ter sequential exposure to steca pressure of 70 psig, 316 F for one hour; 55.4 psig, 303 F for seven nours; and 6 psig, 230 F for 42 hours. Radiation performance is i 2% after 5 negarads total integrated garr2 dose. Docutantation reports are on file at Rosecount. Cresslinked polyethylene cables are run from the detector to a penetration in conduit. The recorder, which was also installed in 1977, allows trending ef main coolant pressure throughout the transient with a range of 0-3000 psig. It is of the latest L&L recorder design, continually monitored to allow detection of any deterioration in perforcance and suitable for operation in ambient terperatures from 16 to 122 F.
Reference:
B.23.1 Rosemount Product Data Sheet 2235. B.23.2 Leeds & Northrup Co. Manual, 177823 B.24 The high range emergency gatna-guard provides an indication of the radiation IcVel in containment after the LOCA DBE. The detector I is mounted high on the turbine room wall, above the control room l roof elevation, and the circuitry and readout is in the control rees. Monitors of this type have been used for area monitoring purposes since initial plant operation, cad the scintillator tubes used f or detection are periodically replaced every three years. The readout circuitry is under continuous surveillance by the control room operator and the detector and cables are testei conthly to assure proper operation. The only change in environment during the DSE is at the detector and the coanial cable in the turbine building. The 120-day integrated dose is less than 1R which will have no adverse effect. 17
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B.25 These transmitters are sini".ar in style to the pressurizer level transmitters discussed in Lection B.6, except that they are rated for 1500 psia, rather than .3000 psia, and are of weatherproof l construction, rather than explosion proof. The Euna-S 0-rings which provide the housing seals are rated for operation up to 212 F. Since , I there is no radiation dose increase associated with the steam line break and continued eperation is required for less than one-hour, i there is reasonable assurance that the transmitters will provide f a signal adequate to cllow the operators to obtain a comparison of ! steam generator levels. ] Uhen. levels have been restored to the narrow range level of operation, the level detectors discussed in Section B.7 provide indication. These detectors are quclified for LOCA conditions.
Reference:
B.25.1 Bailey Product Specification E21-7. B.26 The recirculation fan totors have been designed to operate in an atuosphere of steam and dissolved boric ceid at a te perature of 275 F and a pressure of 50 psig to an integrated dese of 10'R. A prototype motor has been qualification tested at the Franklin Institute Research Laboratory and docutentation is on file at YAEC.
Reference:
B.26.1 Specification YA-719-Y (rev. 1), Specification for Fan Motors for Ilydrogen Control System. l l B.26.2 Letter, Uestinghouse to YAEC, dated 3/9/7' B.26.3 Letter, Uestinghouse to YAEC, dated 3/27/73 l B.27 The referenced letter contains a complete description of the standby l diesel generators as ecil as information regarding their satisf actory performance to date in their periodic testing and taintenance programs.
Reference:
B.27.1 Letter, WYR 78-5, YAEC to SSSEC, dated January l 20, 1978,
Subject:
Standby Diesel Generator Questionnaire B.28 The Gets level switch is designed for fuel oil day tank applicatic,ns. I In the f uel oil environnent, the switch assembly ,till function between l 0 F and 230 F, up to a pressure of 150 pei. The solid state relay that is used in conjunction with the level switch is a conpletely encapsulated unit, free fron the affects of oil, dust, humidity and i vibration. In addition, the system has been tested at each refueling l interval for five years with no failures.
Reference:
B.28.1 Cens Technical Bulletin, Series LS-800 B.28.2 Gems Product Data, Model 28196 ] 1 B.29 Tercinal blocks used inside containment are enclcsed in protective l j boxes and their environmental qualification has been discussed with t f 18
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MRC and addressed in the referenced letter. The sane terminal blocks are used throughout the plant outside containment and are exposed to cuch less severe environmental conditions.
Reference:
B.29.1 Letter, YAEC to USNRC,
Subject:
IE Bulletin
#78-02, Terminal Block Qualification, dated Feb ruary 14, 1978 .
B.30 The ref erences contain qualification inf ormation for the penetration assemblies at Yankee Rowe. -
Reference:
B.30.1 YAEC letter tl USSRC dated November 30, 1977, UYR 77-116 B.30.2 YAEC letter tc USSRC dated December 1, 1977, WYR 77-118 B.30.3 Test Report: Associated Nucleonics, Inc., AN-115, dated May 15, 1959 S.31 The equiptent within the containter t to which cables are connected consists of valve totors, recirculation fan totors, and instrucents. Equiptent which was originally inct.111ed in the plant was wired in a consistent manner. Instronentatian wiring within the loop compartments and the picssurizer ccr.partment consists of mineral insulated cable to a junction box c:tside the biological shield wall; and from there, polye thylene insulared cable with a PVC jacket in condui t to the penetration. Simila:ly, the pouer and control wiring for valve cotors censists of cineral insulated cable within the biolcgical shield wall; and free thele, cither polyethylene or butyl , rubber insulated cable with a PVC jatket in conduit to the penetration. l Instrucentation and totors which were installed later in plant life were connected by cables in conduit from the equipment via enclosed junction boxes to the penetrations. This equipment is specifically the recirculation fan rotors, the LTOP transmitter, the stean generater narrow range level transmitters for ree.ctor protectica, the pressurizer pressure switch for saf ety injection initiation, the saf ety injection 1 cop flow transmitters, and the solenoid valves for hydrogen sampling. PVC shielded cables were specified for these' installttions, unless otherwise noted in :he discussion of the envircr.: ental qualifications of the equipment to which it is connected. Othervise, it tay be ascuned that the cables connected to equipment are tnese of the initial installation mentioned above. The nineral insulated cabic used uichin the biological shield wall is specified to cet or exceed the ';ational Elect ric Code requirerents for MI ccble. It is generally rated for cperation at temperatures j in excess of 300 F and is not susceptible :o radiation dama;;e for I doses exceedir.g 10 9;. 1.fter sore prchlens during initial power i l l 19
F~~.......-...._.__-----_--.-----1.------- o
- - - - - - - - - - - - 1
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U () h I cperation due to noisture at the fittings, the ':1 ccbles have operated essentially trouble-f ree for 17 years 'and have shewn no evidence of radiation effects. The polyethylene insulated cable with PVC jacket has been successfully tested in a steam environment at 260 F and 21.5 psig for a period of 45 minutes. This allows nargin over the notentary peak enticipated LOCA temperature of 2450F. Test results are on file at YAEC (Reference B.31.4). Butyl rubber insulation is generically rated for service up to 250 F. which equals or exceeds the service rating of the polyethylene and PVC insulation material. Since the polyethylene and PVC have been satisfactorily tested and shown to have at least a 15 F margin over the anticipated nonentary peak LOCA tenperature, this provides reasonable assurance that the butyl rubber insulation will also operate satisfactorily under these conditions.
)
The tests were performed in an open stcan environment; whereas the cables are actually installed in steel conduits and junction boxes, which provide protection fro: the steam environnent. The threshold of rcdiation danage for butyl rubber 7 is 2 x 10 R 0 and for polyethylene and PVC, the threshold is 2 x 10 R. These cables are located outside the biclogical, shield wall, so the integrated dose after 17 years is only 2 x 10'R. The 120-day integrated LOCA dose outside the shield wall is less than 10 6R, so there is adequate targin for these cables { to perform their function before radiation Janage even begins to ' take effect. Operating experience for 17 years hcs shown these cables to be sctisfactory for their application. Cables with silicone rubber insulation and asbestos braid overall and cables with crosslinked polyethylene ( XL P ) insulation have been testcc in accordance with IEEE-333 to environmental conditions which far exceed the conditiens expected within the conttintent. Docutentation of test results is on file at YAEC. (Ref e rence B. 31. 2 )
Reference:
B.31.1 U.S. Departrent of Coarerce i.eport # APEX-251,
" Radiation Damage to Elasteners, Organic Liquids, and Plastics".
B.31.2 FIRL Test Report #F-C3798, " Qualification of Class IE Electric Cables fo r ':uclear Power Generating Stations per IEEE 3E3", 1974 B.31.3 Standard llandbook for Electrical Engineers, 1957. B.31.4 Collyer Technical Report 667-2, " Study of 1000V Control Cable in Steam Environ:ent", 1967. l 3.22 The !:osecount 1151GP transmitter is the saac basic unit as the 1152GP codel discussed in Section 3.23. Amplifier eper: tion is designed for a terperature range of 20 F to 200 ?, which far exceeds the l condltions in the PAD. The transmitter is rated for 100 psig and is calibrated to a span of 60 poig. This allows considerable margin l over the LOCA peak pressure of 32 psig. __-________7n_______. i
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,.. V ij,n j e . P ,
Reference:
B.32.1 Rosecount Product Data Sheet 2260 B.33- The Analogic PI2455 indicator has solid-state circuitry and as LED digital display. The operating temperature range is 14 F0 to 140 F, which exceeds the environmental conditions in the control room.
Reference:
B.33.1 Analogic Bulletin :o. 16-10005u Rev. 2 B.34 The solenoid relief valve is designed for a normal operating tenperature of 635 F as the inlet side of the valve is continually exposed to pressurizer saturated steam conditions. It has operated satisfactorily at this elevated ter.perature for 17 years. This valve is to be replaced at the next refueling. Environmental conditions will be considered in the specification of the replacement valve solenoid.
Reference:
B.34.1 Uestinghouse Specification, E-567128-A l l l l t l l l 21
A ~ 3/9M S < REGULATORY INFORMATION DfSTRIBUTION SYSTEM'(RIDS) ,
- . . .,, DISTRIBUTION FOR INCOMING MATERIAL 50-029 l l
REC; ORG: VANDENBURGH D E DOCD ATE: 02/28/78 ) NRC , YANKEE ATOMIC ELEC DATE RCVD: 03/07/78 NOTARIZED: NO DOCTYPE: _ ETTER COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 40 ' LIST IDENTIFYING EQUIPMENT ITS CLASS AND LOCATION AND ADDL INFO IN RESPONSE TO NRC LTR DTD 12/23/77. PLANT NAME: YANKEE ROWE REVIEWER INITIAL: XEF DISTRIBUTOR INITIAL:
***oo************ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE. (DISTRIBUTION CODE AOO1) FOR ACTION: ER CHIEF 'Z-IE N**W 6 f M INTERNAL: ( REG FILE **W/EN L ' NRC PDR**W/ ENCL I 6 E**W/2-ENCL OELD**LTR ONLY HANAUER**W/ ENCL CHECK **W/ ENCL EISENMUT**W/ ENCL SHAO**W/ ENCL BAER**W/ ENCL BUTLER **W/ ENCL GRIMES **W/ ENCL J COLLINS **W/ ENCL - J. MCGOUGH**W/ ENCL EXTERNAL: LPDR'S GREENFIELD, MA**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL i 1 A i t i 6 DISTRIBUTION: LTR 40 ENCL 39 700'700ve. SIZE: 1P+21P CONTROL /GR: _
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