ML19309H913
| ML19309H913 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/15/1980 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| TLL-224, NUDOCS 8005200651 | |
| Download: ML19309H913 (78) | |
Text
o-800520066/f Metropolitan Edison Company
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Post Office Box 480 t
Middletown,. Pennsylvania 17057 717 944-4041 Writer's Direct Dial Number May 15, 1980 TLL 224 Division of Operating Reactors Attn:
R. W. Reid, Chief Op trating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission bashington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Degraded Grid Voltage Enclosed please find Revision 1 to our submittal of October 16,1979 (GOL 1292), which also addresses Item 3 of your letter of August 14, 1979. This study was conducted to determine the adequacy of the Station Electric Distribution System Voltages under degraded grid voltage conditions. Further-more, this study evaluates the undervoltage protection of the safety related electrical equipment from loss of capability of redundant safety loads, their control circuits and associated electrical components, from perfcrming safety functions as a result of sustained degraded voltage from the of fsite electric grid system.
Analytical studies have determined that the offsite power system and the onsite distribution system of TMI Unit I are of sufficient capacity and capability to automatically start as well as operate all required safety loads at a minimum grid voltage of 225kv with either one or two Auxiliary Transformers connected provided certain minor changes are performed. These changes which will be performed by January 1981 are-a.
Designated loads per Exh. 1 be automatically tripped upon initiation of an ES signal.
b.
Installation of solid state undervoltage relays in place of existing electromagnetic type relays for both first and second level.
c.
Institute new procedures to preclude starting a condensate and/or condensate booster pump during the Engineered Safeguard block loading sequence.
Upon performance of these changes, the system design will adequately protect the safety related electric equipment from loss of capability of redundant cafety loads, their control circuitry and associated electrical components required for performing safety functions as a result of sustained degraded voltage from ff the off-site electric grid system. The system is designed to provide the Metrecchtan Ed. son Ccmcany 's a Memter of the General Pubhc Uttt es System
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R. W. Reid TLL 224 required protection without causing voltages to exceed the voltage ratings of the safety loads and without causing spurious separations of the safety buses from offsite power. The analysis indice' ad no event or conditions which could rervit in simultcneous or consequential loss of both required circuits to the offsite network and therefore presents no violation of GDC-17 in this regard.
This revision additionally provides a detailed explanatory analysis in justifying the safety and integrity of the 460 volt motors when operating at 887. of nominal voltage.
Sincerely, s
J. G. Herbein Vice President i
TMI-I JGH:LWH: hah Enclosure cc:
J. T. Collins B. J. Snyder 2
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ADEQUACY OF STATION 1
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ELECTRIC DISTRIBUTION SYSTEM VOLTAGES i
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Table of Contents 1.0 Conclusions and Recom:nendations 2.0 References Page 4
3.0 Methods Page 4
4.0 Comparison of Analytical Results and Ecuicment Rating Page 8
5.0 Computer Analysis Results Page 11 6.0 Taole of Exhioits Page 12 ;
1.0 Purpose The purpose of this TDR is to evaluate the effect of oegraded grid voltage within tne plant and to evolve suitaole operating conditions to maintain the integrity of engineered safeguard ouses and associated electrical eculpment under a degraded grid voltage of 225 kv.
2.0 Re ferences 1.
tRC letter dated May 2,1979 2.
NRC letter dated Aug. 8, 1979 3.
Met-Ed letter to GPU dated Sept. 10, 1979 No. GQM 3030 tute: All listed references are at end of curves - Exhioit 11.
3.0 Methods Basis of Analysis 1.
OFFSITE POWER SOURCES AND DISTRIBUTION (Floure 1)
The plant auxiliary systems are fed by two full size unit auxil-iary transformers which are connected to different 230 KV suosta-tion buses and provide the source of power for startuo, operation and shutdown recuirements. Each of tne unit auxiliary trans-formers has two isolated secondary windings, one at 6900 volts and one at 4160 volts.
The 230 KV suostation is connected to the Metropolitan Edison Company 230 KV grid by two lines to Middletown Junction Substation, one line to Jackson Substation, and one line to a 230 KV/500KV Autotransformer connection to the Metropolitan Edison Company 500 KV grid.
TMI Unit 1 generates electric power i ;
1 at 19 KV.
The main transformers step-up this voltage up to 230 KV and are connected to the TMI substation.
The available connections of TMI Unit 1 to the offsite power net-work that were considered by this study were:
a) Two unit auxiliary transformer connection o) One unit auxiliary transformer connection.
c) Both ES trains availaole s
The analysir considered, in eitner connection situation, tne largest plant load demand as oeing that initiated by an Engineered Safeguards (ES) actuation when the unit was operating at 100%
power output under a degraded grid voltage condition of 225KV.
2.
MULTI-UNIT STATION ANALYSIS Three Mile Island is the location of two nuclear power generating stations, TMI Unit 1 and TMI Unit 2.
Each unit is independently connected to offsite power sources and no common electrical power interconnection exists between units (see Exhibit 2).
Therefore, the analysis treated TMI Unit 1 as independent of tne operating status and electrical load demands of TMI Unit 2.
9 '
i 3.
AUTOMATIC LOADING ACTIONS An Engineered Safeguards Actuation initiates tne Automatic Engi-neered Safeguards block loading sequence (see Exnibit 3) and sim-ultaneously, automatically trips the loads on the ous designated as "lN" and other loads per Ref. 1.
4.
MANUAL LOAD SHEDDING The analysis assumed no manual load shedding to occur on the safety system or on the balance of plant (SOP) systems.
5.
MAXIMUM LOAD The maximum load considered oy the analysis was the Engineered Safeguards block loading in addition to the maximum 80P loao for the unit operation at 100% power output.
The analysis also con-sidered the above loading followed by a trip of a condensate pump
- condensate booster pump simultaneous trip and manual simulata-neous restart.
6.
MINIMUM CRID t 1 TAGE The minimum expected grid voltage used in the analysis was 225KV.
The voltage level was cased upon reliaoility studies (See Exhioit
- 4) that have determined that the probability of occurance for a multiple contingency in the TMI area resulting in a TMI suostation voltage level lower tnan 225 KV is 7 x 10~'.
A minimum grid voltage of 225 KV was tnerefore used as the lowest voltage at the connection of TMI Unit 1 to the offsite source anticipated to -
4
occur during the operating lifetime of the unit.
Tne normal TMI substation voltage level is 232 KV - 238 KV.
7.
VOLTAGE ANALYSIS PROGRAM The analysis employed the Metropolitan Edison Company computer program "TMI - VOLT B" for calculation of the voltage level at eacn of the safety buses for each condition and for each stage in the block loading sequence (See Exhibit 3).
The computer program was verified by actual measurements taken at various points in the plant electrical distribution e--(tem'during 100% power operation on June 7, 1978.
There was less tnan two percent variation between the calculated and measured values.
Exhibit 8.
8.
UNDERVOLTAGE RELAY INITIATION At present the 4160 volt safety buses have General Electric type IAV53K undervo.tage relays to detect a loss of offsite power con-ditions.
These relays are set at 3534 volts and callorated to produce a trip in 6.5 seconds at 2994 volts.
The inverse enarac-teristic of this relay also produces a trip in 16 seconds at 3456 volts and a trip in 2 seconds at zero volts. Operation of these relays will separate the safety bus from offsite network and con-nect it to the onsite emergency diesel generator.
The electro-magnetic relays will be replacea oy solid slate relays.
These relays will oe type ITE-27H as supplied oy Gould.
The setting of
s the solid state relays will oe 3610 volts with 10 second time I
delay and 2912 volts with 1-1/2 second time delay, te automatic transfer of safety loads is initiated oy these under-voltage relays. wnen electrical power is oeing supplied from off-site sources, automatic loadsnedding and automatic load secuencing is initiated only by an Engineerec Safeguards actuation.
9.
COMPARISON OF ANALYTICAL RESULTS AND EQUIPMENT RATINGS A.
Safety eoulpment voltage ratings:
(1) All safety equipment is capaole of continuous operation at 210% of the eculpment nominal rated voltage.
(2) All safety related motors rated 4000 volts nominal nave the capacility to start at 80% voltage or greater.
(3) All safety related valve motors rated 460 volts nominal have the capaoility to start at 75% voltage or greater.
(4) All safety circuit starters have tne capaoility to pickup at 75% voltage or greater and to d,opout at 55% voltage or less.
Exhioit 5. i
(5) Our voltage analysis verifies tnat minimum operating j
voltage conditions will satisfy the 4000 volt motor oper-ating reouirements as specified in MEMA-MGl ANSIC89.1-1977 and IEEE 141-1976. Voltage profile for 4.16KV buses 1D and lE are shown under Exhibit 10 and 11.
( 6 ',
Our voltage analysis indicates that, under the most ao-verse celow listed conditions *, the voltages on the 480 volt cuses will be 404 volts.
This is 87.8% of the ap-plied voltage to the 460 volt motors.
Although this voltage is 2.2% oelow tne 90% acceptacle value as speci-fled in the standards listed under item 5, tne following should oe noted.
1.
All of the 460 volt motors have a service factor of 1.15.
When the voltage and frequency are maintained at the value specified on the nameplate, NEMA stand-ards MGl-12.42 specify that the temperature rise of the motor shall not exceed tne value of the class of insulation system specified when the motor is tested at the service factor load.
On tnis oasis, tne stancard permits continuous operation of the motor when tne current is approximately 15% aoove tnat listed on the nameplate.
- The soverse conditions under whien the voltage will fall below the 90% level are tne simultaneous occurrence of: ;
1.
Lo;s of one Auxiliary transformer 2.
Degraded grid voltage at 225KV level 3.
ES signal 2.
All 460 volt motors connected to tne ES ouses operate at unity service factor.
3.
IEEE 141-1976 Taole 7 estaolishes that tne current to an induction motor will increase oy approximately 11%
when operating at 90% of nominal voltage.
This re-presents an 11% increase in current for a 10%
decrease in voltage wnicn indicates tnat, within limits, the current varies inversely witn the volt-age. Since we do not anticipate to operate oelow 87.8% or 12.2% of motor rated voltage, we ao not expect the current to increase by more than 13.5%.
This is witnin tne 15% allowaole limits indicated under 6.1.
4.
Immediately following an ES signal, tne calance of plant loads will decrease tnereoy helping to increase the voltage, i i l
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Based on the above, it is concluded that a postulated voltage of 87.8% of 460 volts for an indefinite time will not exceed the temperature rise of the value given for the specified class of insulation and will tnerefore not cause thermal damage to the ES motors.
B.
Cor.puter Analysis Results The results of the Computer analysis are presented in curve form in Exhioit 10-1 through Exhibit 10-8 for one (1) unit auxiliary transformer operation and Exhibit 11-1 tnrougn 11-8 for two (2) transformer operation. Re er to Exhioit 7 for listing of each case shown on curves.
The computer analysis has indicated maximum 480 volt safety bus voltage of 509 volts and maximum 4160 volt safety ous vc. age of 4410 volts, representing conditions within the safety equipment ratings.
This maximum voltage was snown to occur with the unit in a snutdown mode and the offsite power network at 242 KV, the maximum 230 KV grid voltage permitted by the PJM Interconnection System which is highly unlikely to occur.
No case was found where tnere was inadequate capacity or cap-ability to start and operate the required safety loads.
The acceptaollity of the voltage-conditions on tne TMI Unit 1 safety electric distrioution system has oeen confirmed analytically.,
TABLE OF EXHIBITS Exhibit 1 A list of loads that will trip automatically on ES signal.
Exhibit 2 TMI Unit 1 one line "Offsite Power Sources and Distribution System."
Exhioit 3 Engineered safeguards block loading secuence.
Exhibit 4 TMI Unit 1230 kv Bus voltage Rellaollity Study.
Exhibit 5 MCC line starter voltage coil design rating.
Exhibit 6 Engineered Safeguards Channel A & Channel B load study.
t Exhioit 7 Engineered Safeguards Bus Loading Stages - Computer run.
Exhibit 8 Computer program verification.
Exhibit 9 Notes to voltage profile curves.
Exhibit 10 Safety Bus Voltage Profiles for One Aux. Transf. Operation at 225 kv during block loading and running conditions.
Exhibit 11 Safety Bus Voltage Profiles for Two Aux. Transf. Opera-tion at 225 kv during blocw loading and running conditions. e
A List of Loads That Will Trio Automatically on ES Signal i
(i)
AH-E-8A, Spent Fuel Cooling Pump Air Unit 2
KW (ii)
AH-E-9A, Penetration Cooling Fan
- 43.4 KW j
(iii)
SF-P-1A, Spent Fuel Pit Cooling Pump 33 KW (iv)
Boric Acid Mix Tank Heater
- 17.5 KW (v)
Boric Acid Tank Mixer 1.4 KW BUS IN - All Loads 405 KW BUS 19 ES MCC 7 ads:
i (1)
AH-E-88, Spent Fuel Cooling Pump Air Unit 2
KW (ii)
AH-E-98, Penetration Cooling Faa
- 43.4 KW (iii)
SF-P-1B, Spent Fuel Pit Cooling Pump 33 KW (iv)
Boric Acid Mix Tank Heater 17.5 KW Totals
= 598.2 KW EXHIBIT 1
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1-Makeup Pump 700 700 0.93 561 1-Decay Heat Pump 350 340 0.92 275 3-Inverters 45 (KW) 35 (KW)* 0.78 45 2-Battery Chargers 37.5 (KW) 37.5 (KW)* 0.80 47 2
2-Reactor Building Ventilation Units 150 92 0.9 76 1-Reactor Bldg. Emerg. Cooling R. W. Pump 400 380 0.92 308 3
1-Nuc. Serv. Closed Cooling Pump 125 115 0.91 94 1-Nuc. Serv. River Water Pump 150 150 0.92 122 1-D3 cay Heat Closed Cooling Pump 100 91 0.91 75 1-Decay Heat River Water Pump 200 180 0.91 148 4
1-Reactor Building Spray Pump 250 240 0.91 197 5
1-Emergency Feedwater Pump 450 450
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No credit has been taken for the reduction in pumping power requirements that occur with time following an accident.
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TMI 230 KV BUS VOLTAGE RELIABILITY STUDY l
Calculations have been made to determine the procaoility of the TMI 230 KV bus voltage ceing equal to or less than 225 KV.
The calculated probability is 7 x 10-'.
The study concentrated on outage conditions in the TMI area tnat 4
could result in a TMI 230 KV bus voltage of 225 KV or less. Exnibits 4-1 through 4-27 indicate the various system conditions considered.
The calculations were based upon the results of several load flow cases representing 1979 summer peak conditions, intermediate and light load levels.
A prerecuisite for a multiple contingency condition recuired to yield a TMI 230 KV bus voltage of 225 KV or less is that tne TMI 500 KV/230 KV autotransformer is open.
Typical data for 500 KV transformers was used to determine an cutage rate of one percent for the transformer, including the effects of an outage due to a fault and scheduled or unscheduled maintenance.
The latest actual or predicted forced, maintenance and scheduled outage data for TMI and Brur.ner Island generating units was used.
Outage rates for single or double 230 KV line outages were based on typical data that was used for PJM studies.
The probaollity of being at peak load level (85% to 100% of peak),
intermediate load level'(60 to 85% of peak) or light load level (minimum load to 60% of peak) was determined from PJM load duration curves.
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Contetrc.orr., employed rcr cohtrollint; h60 volt lightinis, Pres:uri t r llenber: ur.d ht-at tn.r.: 3 ca;t nhedl be previded whcio notcd on thi: dr;uingp,,ul such card.nci era shall 1 e Iraquetier.1.]y held with i;hree pcver nuine.gi;., pol 3 si..c;.
c inaticc i.:!d.
Cireit!: brJakern uced in coalunction with 2
coate.ct.o:c chull h:.ve teribient c::cp.:non;.ed Lhelunl and uag netic trips.
!al co: ttteter:- uill.be arrane.ed for threi Viro cenLrol.
Ginca ther2 13 a po: ibility or r.cment,,:.:; voltece dipc, each u turL 3r and coni act >r chn11 bc ce. pubic cs' 'ti t;tutmiding; a l N;xentrey volte.p.e J. cp t., 5:V or r iled,olc p Iw; a perioi-cf 2 3 c:o::<ia withcrt'; d o;,pi;,3 cat, I
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Exhibit 5
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ENGIrJEERED SAFEGUARDS CHANNEL 0 LOAD STUDY, Eri 4EERED SAFEGUARDS CHAtar!ELS A Aro 8 ARE AVAILABLE t
LOAD DLRING LOAD DLRING '
LOAD OtRING LOAD DLRING 100% POWER AT 100% P0clER E.S. AT E.S. AT NOMINAL BUS AT DECRADED TO4IrlAL BUS DECRADED BUS VOLTAGE BUS VOLTAGE VOLTA &
VOLTAGE LOAD BY BUS K.W.
AMPS.
K.W.
AMPS K.W.
AMPS K.W.
AftPS A.
4160V IE 1919.5 302.7 1919.5 349.8 3631.]
572.7 3631.1 661.7 1.
EMERG. FEED WTR.
0 0
0 0
PLNP MOTOR EF-P2A 2.
8 EMERG. FEED WTR.
0 0
365.7 499.9 365.7 578.1 PLNP MOTOR EF-P2B 3.
1S 480V. Lt4IT 856 1125.3 856 1206 760.5 997.7 760.5 1064.5 Modified SUB. FOR BKR.
IS BUS 4.
8 DECAY lEAT 0
0 275 375.9 275 434.8 RD40 VAL PLNP MOTOR DH-P1B 5.
C MAKE-UP PUMP 561 766.8 561 886.9 561 766.8 561 886.9 MOTOR HU-Plc 6.
B MAKE-UP PUMP O
0 561 766.8 561 886.9 MOTOR MU-PIB 7.
B REACTOR BLDG. SPRAY 0
0 197 269.3 197 311.4 PLNP MOTOR BS-PIB 8.
B RB. EMERG. CLG.
0 0
308 421 308 486.9 R.W. PLNP MOTOR RR-PIB 9.
IT 480V. UNIT 502.5 677.4 502.5 763 602.9 814.8 602.9 921.9 SUB. FOR. BKR.
EMiIBIT 6-1 o
7 cm,: a, EtJCirJEEHED SAFECUARDS CHAR!rJEL B LOAD STUDY, Err'NEERED SAFECU/RDS CHA"r!ELS A Ar.0 B ARE AVAILfSLE g
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(
LOID DWING LOAD DWIfJG LOAD DURING L0a0 DWING 100". POWER AT 100% P0 DER E.S. AT E.S. AT PO11NAL BUS AT OECRADED falINAL BUS DECRADED SUS VOLIAGE BUS VOLTAGE VOLTAGE VOLTAGE LOAD BY BUS K.W.
MiPS.
K.W.
INPS K.W.
41PS K.W.
A'.:PS B.
480V SWCR. BUS 1T 502.5 677.4 502.5 763 602.9 814.8 602.9 921.0 1.
B SEC. SERV. RIVER 0
0 0
0 WTR. PLNP SR-PIB
'2.
C tJUC. SERV. RIVER 122 166.8 122 192.9 122 166.8 122 192.9 WTR. PLNP m-Plc 3.
B DECAY lEAT RIVER 0
0 144.4 197.4 144.4 228.3 WTR. PLMP OR-PIB 4
B NUC. SERV. RIVER 0
0 0
0 WIR. PLMP m-PIB-T 5.
C SEC. SERV. RIVER 179.8 245.8 179.8 284.2 179.8 245.8 179.8 284.2 WTR. PLNP SR-PIC 6.
18 SCREEN LOUSE 102.3 131 102.8 131.1 107.7 137.8 107.7 139 ES MCC 7.
B SCREEN WASli 97.9 133.8 97.9 154.8 49 67 49 77.5 PLMP SW-PIO C.
480V SWCR. BUS IS 856 1125.3 856 1206 760.5 997.7 760.5 1064.5 Modi fied 15 BUS 1.
IB E.S. M.C.C.
556.7 733.7 556.7 790.4 424.6 556.1 424.6 591 tbdified Bus 556.7 733.7 556.7 700.4 520.5 684.2 520.5 733.3 Bus As Is 2.
B DECAY IEAT CL.
0 0
74.6 102 74.6 117.9 COOLING WTR. PP DC-PIB E)0lIBIT 6-2
- o
Page.5 EtJGINEERED SAFECUMDS DIAtJNEL B LOAD STUOY, Er.C'NEERED SAFECUfRDS DWJ:ELS A Aro B ARE A'.' AIL ASI E 4
(
(
LOAD DLRING LOAD OtRING LOAD OURIrlG LOAD DLEIi;G 100% POWER AT 100% POWER E.S. AT E.S. AT t04INAL BUS AT DECRADEO iG11NAL BUS DECRADED SUS VOLTACE BUS VOLTAGE VOLTACE VOLTACE LOAD BY BUS K.W.
44PS.
K.W.
44PS K.W.
R1PS K.W.
4435 C.
480V SWCR BUS IBES (CONT.)
3.
NUC. SERV. CL.
94.3 128.9 94.3 149.1 91.3 128.9 94.3 149.1 COOLING WTR. PP NS-Plc 4
TOC. SERV. CL.
0 0
0 0
0 0
0 0
COOLING WTR. PP NS-PIB-S 5.
91.9 110.5 91.9 96.1 91.9 110.5 91.9 96.1 HTG. MCC 6.
113.1 152.2 113.1 170.4 75.1 100.2 75.1 110.4 HTG. MCC 7.
PRESS. HTRS.
0 0
0 0
CROUP 9 HOTE: IC ES VLV. & HTG. HCC has been included 10 both A & B channels.
EXHIBIT 6-3 m
Pa,p 4 I.
EtlGItJEERED SAFEGlWlDS CilAtJtJEL B LOAD STUDi It.'CINEERED SAFECUfRDS CHAttJELS A AND B TRE AVAILf' {
BUS JS, LOAD DLRitlG LOAD DlRING LOAD DURltJG LOAD DtHING 100% POWER AT 100% POWER E.S. AT E.S. AT totItJAL BUS AT DECRADED iD4It!AL BUS DEGlf0ED BUS VOLTAE BUS VOLTAE VOLTAE VOLTAE K.W.
44PS.
K.W.
RIPS K.W.
R4PS K.M.
4:PS BUS IS AS IS 856 1125.3 856 1206 856.4 1125.8 856.4 1206.8 Loads Automatically tripped off on ES 95.9 128.1 95.9 142.3 Optimum Modified 15 Bus 856 1125.3 856 1206 760.5 997.7 760.5 1064.5 Followilig loads will automatically trip off on ES signal.
1)
AH-E-88, Spent Fuel Cooling Pump Air thit - 2 KW 11)
AH-E-98, Penetration Cooling Fan
- 43.4 KW 111)
SF-P-18, Spent Fuel Pit Cooling Pump
- 33 KW iv)
'v ic Acid Mix Tank Heater
- 17. 5 KW EXHIBIT 6-4 O
3 Pacp 1 i
EtJGItJEERED SAFECUntDS CHAT 4tJEL A LOAD STUOY, Et."
JEERED SAFECUfflDS CHA::r:ELS A 40 0 PRE AVAILN3tE (
LOAD DURING LOAD OlflDIG '
LOAD DWING L0fD OtflItJG 100% POWER AT 100% POWER E.S. AT E.S. AT FO-IINAl. BUS AT DECRTOED TO4INAL BUS DECRfDED BUS VOLTAGE BUS VOLTACE VOLTAGE WLTAGE LOAD BY BUS K.W.
R4PS.
K.W.
R4PS.
K.W.
R-tPS K.W.
A PS A.
4160V 10 2249.4 354.8 2249.4 409.9 3704.4 584.2 3704.4 675.1 1.
A EMERG FEED WTR 0
0 365.7 499.9 365.7 578.1 PLNP M0TDR EF-P2A 2.
8 EMERG FEED WTR 0
0 0
0 PLNP fl0 TOR EF-P20 3.
IP 480V UNIT 836.7 1014.8 836.7 1082.7 886 1078.9 886 1165.7 stb FOR BKR
^
4 A DECAY lEAT 0
0 275 375.9 275 434.8 RD40 VAL PLNP MOTOR DH-PI A 5.
A MR<E-UP PUMP 561 766.8 561 886.9 561 766.8 561 886.9 MOTOR HU-P1A 6.
8 MAKE-UP PLNP 0
0 561 766.8 561 886.4 MOTOR MU-P18 7.
A REACTOR BLDC.
0 0
197 269.3 197 311.4 SFYlAY PLNP MOTOR BS-PIA 8.
A R.B. EMERG.
0 0
308 421 308 486.9
- ~
CLG. R.W. PLMP MOTOR RR-PIA 9.
IR 480V DNIT 446.7 610.2 446.7 704.2 550.7 752.5 550.7 868.8 SLB FOR BKR.
10.
IN 480V UNIT 405 405 0
0 SUB FOR BKR E)HIBIT.6-5 4
l
. ug:. r.
EtJGirJEERED SAFECUARDS CHANNEL A LOAD STUDY, EtrNEERED SAFECUARDS CHAT:NELS A AND 8 ARE AVAIL MLE L
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LOAD DtBING LOIO DURIfJG LOAD DtRING LOAD DLRING l
100% POWER AT 100% POWER E.S. AT E.S. AT FOtIrlAL BUS AT DEm/CED iG'I;4AL ut,5 DECni4>EU ouS VOLTACE BUS VOLTAGE VOLTACE VOLTACE LOAD BY BUS K.W.
/ttPS.
K.W.
4tPS K.W.
It1PS K.W.
A*4PS 8.
480V SWCR BUS IR 446.7 610.2 446.7 704.2 550.7 752.5 550.7 Bf8.8 1.
FIRE Pl#4P MOTOR 0
0 0
0 2.
A NUC. SERV. RIVER 122 166.8 122 192.9 122 166.8 122 192.9 WTR PUMP tR-P1A 3.
A DECAY IEAT RIVER 0
0 148 202.3 148 234 WTR PLf4P DR-P1A 4.
A SCREEN WASH 97.9 133.8 97.9 154.8 49 67 49 77.5 PLl4P SW-P1A 5.
B TOC. SERV. RIVER 0
0 0
0 WTR. plt 4P tR-PlB-R 6.
A SEC. Sm V. RIVER 179.8 245.8 179.8 284.2 179.8 245.8 179.8 284.2 WTR. PLf4P SR-P1 A 7.
l A SCREEN IOUSE ES. MCC 47 63.8 47 43.4 51.9 70.6 51.9 80.2 C.
480V SWCR. BUS IP 836.7 1014.8 836.7 1082.7 886 1078.9 886 1165.7 tbdifled Bus 1.
lA E.S. MCC 426.5 475.3 426.5 481.8 439.2 489.4 439.2 506.9 Fbdified Bus 426.5 475.3 426.5 481.8 536.5 619.4 536.5 651.3 As is Dos 2.
A DECAY TEAT CL.
0 0
74.6 102 74.6 117.9 COOLItjG WTR PLNP DC--PI A 3.
A CONT. BLDG.
130 177.7 130 205.5 130 177.7 130 205.5 WTR. CHILLER 4.
A NUC. SERV. CL.
94.3 128.9 94.3 149.1 94.3 128.9 94.3 149.1 COOLING WTR. PLf4P NS-PIA EXHIBIT 6-6
Pagc 3 EtCitJEERED SAECGtWIDS CHAT #JEL A LOAD STUDY, Etr"*EERED SAEEGUARDS CtWEELS A Ato fl EtE AVAllfBLE LOAD DlitING LOAD DlflING,
LOfo D W ItJG LOA 0 DWIrlG 100% POWER AT 100% POWER E.S. AT E.S. AT fD4INAL BUS AT DECRADED tatItJAL DUS DECRADED BLS VOLTAGE BUS V0t. TACE VOLTAGE VOLTACE LOAD BY BUS K.W.
R4PS.
K.W.
R4PS K.W.
R4PS K.W.
44PS C.
480V SWCR. BUS IP (CONT'0) 5.
B. NUC. SERV. CL.
0 0
0 0
~
COOLING WTR PLl4P NS-PIB-P 6.
72.8 80.7 72.8 75.9 72.8 80.7 72.8 75.9 HIG MCC 7.
113.1 152.2 113.1 170.4 75.1 100.2 75.1 110.4 HTG MCC 8.
PRESS. HTRS 0
0 0
0 CROUP 8 NOTE: IC ES VLV & HTG. MCC has been included in both A and B channels O
EXHIBIT 6-7 G
aoyn n
(
EtJGirJEERED SAFEGUARDS CHAtJt!EL A LOAD STUDY EtSI? JEERED SATECUPRDS CittfriELS A No B faE AVAILT
(
i BUS IP L0fD DulltJG LOAD DulltJG LOAD DulltJG LOAD DulIfC 100% POWER AT 100% PL7 DER E.S. AT E.S. AT Not4ItJAL BUS AT DECRADED IJCl41tJAL BUS DECRTOED BUS VOLTAT BUS VOLTAT VOLTAGE VOLTAGE K.W.
At4PS.
K.W.
- 4PS K.W.
R4FS K.W.
f#,PS BUS IP 836.7 1014.8 836.7 1082.7 983.3 1208.9 983.3 1310.1 AS IS Loads automatic-ally tripped off 97.3 130 97.3 144.4 on E. S.
Optimum Modified 836.7 1014.8 836.7 1082.7 886 1078.9 886 1165.7 IP BUS
.Following loads will automatically trip off on ES signal.
1)
AH-E-8A, Spent Fuel Cooling Pump Air Unit - 2 KW 11)
AH-E-9A, Penetration Cooling Fan
- 43.4 KW iii)
SF-P-1 A, Spent fuel Pit Cooling Pump
- 33 KW iv)
Boric Acid raix Tank Heater
- 17.5 KW v)
Boric Acid Tank Mixer 1.4 KW EXHIBIT 6-8
ENGINEERED SAFETY BUS LOADING STAGES (Refer to Exhibits 10-1 to 10-8 and 11-1 to 11-3)
One Transformer Operation with Grid 225 kv Case 1-1 100% power, no "ES" condition Case 1-2 100* powerr. starting ES Block 1 - 2 ES trains Case 1-3 100% power, running ES Block 1-2 ES trains Case 1-4 100% power, starting ES Block 2 - 2 ES trains Case.1-5 100* power, running ES 31ock 1 & 2 - 2 ES rrains
_ Case:-1. 100* power,2sent-%g_ES Block. 3
.2 ES ~ irs Case-1-7
.100% power running ES Blocks 1, 2 & 3 - 2 ES trains r
Case 1-8 100~ power, starting ES Block 4 - 2 ES trains Case 1-9
.100*. power, running ES Blocks 1, 2, 3 & 4 - 2 ES trains Case 1-10 100% power,. starting ES Block 5 - 2 ES trains Case 1-11.100%. power,_ running two full ES trains Case 1-12 100% power, running two full ES trains, starting condensate t
booster pump Case 1-13 1 Aux. Trae;I. Operation, 225kV, 100* power, running two full ES trains, starting condensate and condensate booster pumps Case 1-14 Aux. Transf. Operation, 225kV,100% power, run:t'.ng two full ES trains Two Transformer Oneration with Grid at 225kV (One ES Train on each Transformer)
Case 2-1 100% power, no "ES" condition Case 2-2 100* power, starting ES Block 1 Case 2-3 100* pswer, running ES Block 1 Case 2-4 100% power, starting ES Bleck 2 Case 2-5 100% power, running ES Blocks 1 & 2 Case 2-6 100% power, starting ES Block 3 Case 2-7 100% power, running ES Block 1, 2 & 3 Case 2-8 100% power, starting ES Block 4 Casr ?-9 100% power, running ES Blocks 1, 2, 3 & 4 Case 2-10 100% power, starting ES Bicek 5 Case 2-11_ 1001 power, running one full ES train Case 2-12 100% power, running one full ES train starting condensata boosts: punp Case 2-13 2 Aux. Transf. Operation, 225kV. 100% power, running one full ES train, starting and condensate booster punps Case 2-14 100% power, running i full ES train Exhibit 7 e
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THI UNIT 1 AUXBK.A VOLTAGE PROFILE
' - '... ~,.
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2 4160 BOP 16070 28.8 1,
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TMI UNIT 1 AUXBN A VOLTAGE PROFILE a...n..m..-
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.2BK OPEPATION 4
5 230 6900 BOP BUS BUS BUS 1A 1AES 1AES
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THI UNIT 1 AUXBK B VOLTAGE PROFILE
'2 2BK OPERATION a
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in LOADS USED IN THIS STUDY r..l n
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The following notes apply to curve exhibits Note 1: Simultaneous starting of the condensate and condesnate booster pumps can occur after the Engineered Safeguards block loading sequence has been completed.
The starting current to these BCP loads can cause the voltage on the 4160 volt safety Duses.to_ momentarily die below the undervoltage relay set point deoending u;on -the-offsite-network grid voltage.
The 4160 voit safety cus voltage will return to a value acove the undervoltage relay set point in a time less than that required for tne relay to trip.
Note 2: During one unit auxiliary transformer operation, the starting of some Engineered Safeguards load clocks can cause the voltage on the 4160 volt safety ous to momentarily dip Delow the undervoltage relay set point depending upon the offsite network grid boltage.
Tne 4160 volt safety bus voltage will return to a value above the undervoltage relay set point in a time less than that required for the relay to trip.
Note 3: Starting the condensate booster pump can occur after tne Engineered Safeguards olock loading secuence has been completed.
The starting current to that BOP load can cause tne volrage on tne 4160 volt safety ouses to momentarily dip Delow the uncer-voltage relay set point depending upon the offsite network grid Exhibit 9-1
voltage.
The 4160 volt safety ous voltage will return to a value acove tne undervoltage relay set point in a time for less than that recuired for the relay to trip.
EXHIEIT 9-2
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UNITED STATES
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7' h NUCLEAR REGULATORY COMMISSION RECEP/ED WASH NCTotJ,0. C. 20555
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f EIS AUG 13,UI 8-54
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August 8,1979 MET cD CO.
GEFEllATIO!l DIVIS!OH.
All Power neactor Licensees (Except Humboldt Bay) r esg
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81 M N RE: ADEQUACY OF STATION ELECTRIC DISTRIBUTION SYSTEMS VOLTAGES icc.*h'.D.p:.6 sc e~
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the-NRC_ generic-letter-of June 2,1977 regarding undervoltage protec /d, M@
We-are currently = reviewing the licensee's-submittal s in response to tion of--tne safety related electric equipment frcm 1 css of capability] I
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e of redundant safety loads, their control circuitry, and associated electrical components required for perfoming safety functions as a result of sustained degraded-voltage frcm the offsite electric grid system. This_ generic ~ action was based on the Millstone Event which occurred on July 5,1976.
The-recent event at the-Arkansas Nuclear One (ANO) station on September 16, 1978 brought into question the conformance of the station electric distribution system to GDC-17, in two sep'arate regards. Each of two units at the ANO station has a dedicated-startup transfomer powered through a single shared autotransfomer (conmon source of of fsite power) from the station switchyard. Opera-tion of an autotransfomer overcurrent relay caused the loss of the two dedicated startup transformers. The station electrical distribution systen thus automatically transferred the full auxiliary loads of both units to the backup startup transfomer exceeding its rated capacity and degrading the voltage level at the safety buses. Secondly, during our review of the electrical system at the AN0 station, the licensee's analysis indicated that the "immediate ac' cess,offsite power circuit" (dedicated startup transfomer) lacked "sufft'cient capacity and capability" to acconmedate the simultaneous starting demands of the emergency loads concurrent with the full ' house loads, in the event of a less of coolan't accident (LOCA). The condition would result in all safety loads remaining on the dedicated startup transfomer with unacceptably degraded voltage. A voltage degradation during the electrical starting condition beccmes a safety concern either if the degradation causes the starting condition to be prolonged so as to become a sustained undervoltage or if the voltage degradation causes frequent spurious sheeiding of the ESF loads from the preferred power source, Li:e oil It e e!ct ! is 3 11 II.h. rvent wa. dexcilovl in ?!RC's IE Infomation Notice No. 79-04.
Additional background infomation is provided in Enclosure 1.
The IE Infomation Motice No. 79-04 stated that NRC would follow with specific actions to be taken by licensees.
This letter identifies those actions.
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2 Based on the ANO event, the IRC has expanded its generic review of the adequacy of the electric power systems for all operating nuclear power facilities. Specifically, we must now confirm the acceptability of the voltage conditions.on the station electric distribution systems with regard to both (1) potential overloading due to transfers of
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either safety or non-safety loads, and (2) potential starting transient problems in addition to the concerns expressed in our June 2,1977 correspondence with regard to degraded voltage conditions due to conditions originating on the grid.
Based on the experienc'e at ANO, the fGC is requiring all licensees to review-the:clectric power systens at eath of their nuclear power plants to detemine analytically if, assuming all onsite sources of AC power are not available, the offsite power system and the onsite distribution system is of sufficient capacity!and capability to automatically start asiell as operate all required safety loads.
Within their required voltage ratings in the event of (1) an antici-pated transient (such as unit, trip) or (2) an accident (such as a LOCA) regardless of other actions the electi-ic power system is designed to automatically-initiate-and without the need for manual shedding of any electric loads. Protection of safety loads from undervolta'ge conditions must be designed to provide the required protection without causing voltages in excess of maximum voltage ratings of safety loads and without' causing spurious separations of safety buses frem offsite e
power.
t'P.C should be infomed of any required sequential loading of any portion of the offsite power system or the onsite distribution system which is needed to assure that power provided to all safety loads is within required voltage limits for these safety loads.
Guidance on evaluating the perfomance of electric power systems with regard to voltage drops is provided in Enclosure 2.
Th,e adequacy of the onsite distribution of power from the offsite circuits shall be verified by test to assure that at.?ysis results are valid. Please provide:
(1) a description of the method for perfaming this verification, and (2) the test results.
If previous tests verify the results of the analysis, then test results should be submitted aad addition 11 tests need not be perfor vd.
In addition, you are requested to review the electric power systems of your nuclear station to determine if there are any events or conditions which could result in the simultaneous or consequential loss of both required circuits to the offsite network to detemine if any pntential exists for violatinn nf GDC-17 in tbs regarci.
These reviews should be completed, and a copy of the analyses provided to IMC within 60 days of the date of this letter.
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In the event that any violation or potential violations of GDC-17 or voltage requirements of safety loads are discovered remedial action should be taken immediately. You should provide the Commission with Prompt Notification with Written Followup pursuant to the reporting requirenents of your Technical Specifications.
If the above required revio:s have been cor.yleted by you as part of your response-to our June 2,1977 request, MP.C should be infomed within 30 days of the date of this letter. Approved by GAO, B-180225 (R0072). cl earance-e*pires 7/31/80. Approval was given under a blanket clearance-specifircally-for-identified generic problems.
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Sincerely, s
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CL% v.s.w William Gammill, Acting Assistant' Director for Operating Reactors Projects Division of Operating Reactors
Enclosures:
1.
Background Infomation on AND Event 2.
Guidelines for Voltage Drop Calcuiations cc:
Service List t
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ENCLO5UP.E 1
,BACXGROUND INFORMTION ON AND EVENT The event that occurred at the Arkansas. Huclear One station on September'16, 1978, brought into question the conformance of the station electric
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distribution system design to GDC-17 with regard to the capacity and the capability of the ensite systems.
Each of two units at the ANO station has a dedicated startup transformer connected to a_sincle shared autotransformer (common source of offsite '.
power)-from-the station switchycrd. The incident was initiated by Unit--l reactor--trip concurrent with trip of the unit!s turbine-generator.
The-Unit I auxil-iary-loads-were automatically t-ans ferred o Startuo 2 dedicated startup power-being supplied to Startup Transformer 3 (Unit Transformer 1.
The transformer), which was feeding Unit 2, and being supplied-to Startup-Transformer-1 resulted in operation of an autotransformer
. overcurrent relay and consequen; tripping of the incoming circuit breaker of the autetransformer. The autotransformer has the capacity to provide power for both units,.but due to an error, the overturrent relay was still set for-the operation; of Unit 1 only. Loss of input power to the two Startup transformers auto =atically transferred the auxiliary loads for both units to the backup Startup Transformer, ST 2.
However, this trans-former is Jesigned as an alternate su ply for one unit and is not designed r
to carry f ull auxiliary loads for both units. This overload caused a voltage degradation at the safety buses. The event to this point demonstrated that the design of the offsite power system to the ANO station Units 1 and 2 did not fully meet GDC-17.
In the cirev= stances experienced at AND the failure of one of the two offsite electric power circuits resulted in failure of the other electric power circuit. GDC-17 requires, in part, that (1) electric power from the transmission network to the onsite distribution system shall be supplied by two physically independent circuits (not necessarily on s perate right of wn-) desi;ned and located so as to minimize to the extent practical the likelihood of their simultaneous failure under operating and environmental conditions and (2) provision shall be included to minimize the probability of losing electric power from any of the remaining supplies as a result of, or coincident with, the loss of power generated by the nuclear unit, or the loss of pcwer frem the transmission network.
The AMO tid not fully meet these requiresents.
Initially, the s quence of events on ' September 16,1978 did not indicate any problem with t..e electrical distribution systen of Unit 1.
However,
subsequent anclysis by the licensee indicated that in the event of a LOCA at Unit 1 during which time Startup Trans former No.1 would be required to provide power to both the non-safety auxiliary electrical e
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,.: -l loads and start the sa fety loads a voltage degradation would result..
2 The safety loads might not transfer to the Unit 1 diesel-generators but ~
could remain on the startup transfomer with unacceptably degraded voltage.
Although there is margin in the themal capability of equipment such a s.ituation could result in thermal damage in the safety equipment and/or blown fuses in control circuits for these safety loads.
Either event could result in disabling these loads during a LOCA. GDC-17 requires,,
in part. that. electric power supplies for r.uclear power plants provide-f sufficient capicity. and. capability to as,ure that certain limits are not' exceeded in the event of anticipated operational occurrences and
~ 'that the core is cooled and containment integrity and otner vital functions are maintained in the event of postulated failures.
The ANO.d,esign was not capable of pro iding the electric power of " sufficient ca pa city' a nd ' ca pabil ity. "
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- E!;CLOSUP.E 2 sGUIDElitlES FOR VOLTAGE DROP CAlcutATI0ftS 1.
Separate analyses should be performed assuming the' power source to safety buses is (a) the unit auxiliary transforcer; (b) the startup transformer; and (c) other available connections to the offsite networ!. one by one assuming the need for electric power is initiated by (1) an anticipated transient (e.g., unit trip) or (2) an accident, whichever presents the largest load demand situation.
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2.
For multi-unitatations a separate analysis should be perfomed for each-unir assuming (1) en accident in tne ur.it being anlayzed and simultaneous 1 shutdown of all _other units at that sta: ion;
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or-(2) an antietpated-transient in-the unit being analy:ed (e.g.,
unit trip,) and simultaneous shutdown of all other un'ts at that station, whichever presents the largest load decand situation.
3.
All actions the electric power system is desicned to aut matically initiate should be assumed to occur as designed (e.g., automatic buik or secuential loading or automatic transfers of bulk loads from one transformer-to another).
Included should be consideration of starting of large non-safety loads (e.g., condensate pumps).
4.
Ma'nual load shedding should not be assumed.
5.'
For each event ar.nlyzed, the maximum load necessitated by the event and the mode of operation of the plant at the time of the event should be assumed in addition to all loads ciused.by. expected automatic actions and manual actions permitted by ad7inistrative procedures.
6.
' The v'oltage at the terminals of each safety load should be calculated based on the above listed c'onsiderations and assumstions and based on the assumption that the grid v61tage is at the " minimum expected value".
The " minimum expected value" should be selected based on the least of the following:
a.
The minimum steady-state voltage experienced at the connection to -the of fsite circuit.
b.
ihe Tninimum-. voltage expected at the connection to the offsite circuit due 'to contingency plans' which ray resul: -in redated voltage from this grid., _
c.
"The minimum predicted grid voltace from cri: sta:ility ar.alysis.
(e.g., load flow studies).
j In the report to f1RC on this matter the licensee shc ld state planned actions, includirg any proposed " Limiting Conditicas for Operation"
, for Technical Specifications, in response to egerie cin; voltage at the connection to the offsite circuit whict. is leis tnan the'
" minimum expected value." A copy of the plant crocedure in this regard should be provided.
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The voltage analysis should include documentation fer each condition analyzed, of the voltage at the input and output of each transfcrmer and'at each intermediate bus between the connection to the offsite circuit and the terminals of each safety load.
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The analysis should document the voltage setpoint and any inherent or adjustable (with nominal setting) time delay for relays which (1) initiate _or execute automatic transfer of loads from one source to anothert (2) initiate or execute automatic load shedding; or.
(3) initiate or execute automatic load sequencing.
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9.
T.'+2 calculated: voltages at the terninals o' cac5 refety load should be compared witn-the required voltage range for normal cperation and starting of that load.
Any identified inadequacies of calculated voltage require immediate remedial action and notification of HRC.
10.
For each case. evaluated the calculated voltages on each safety _ bus should be compared with the voltage-time settings for the under-vol3 age' relays on these safety b,uses.
Any identified inadequacies f6 undervoltage relay settings require immediate re' iial action and notification of HRC.
To provide assurance.that act' ions taken to assure adequate voltagh 11.
levels for safety loads do not result in' excessive. voltage, assusing the maximum expected value of voltage at the ccnnection to the offsite circuit, a deerminatio1 should be made of-the maximum voltage expected at the terminais of each safety load and its starting circuit.
If this voltage exceeds the maximum voltage rating of any item of safety equipment immediate remedial action is required and NRC shall be notified.
12.
Voltage-time settings for undervoltage relays shall be selected so as to avoid spurious separation of safety buses from offsite power during plant startup, normal operation and shutdcwn.due to startup end/or operation of electric loads.
13.
Aralysis documentation should include e statement of the assumptions -
for each case. analyzed.
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/AETROPOUTAN EDISON C OM P A N Y s....a
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Subject TMI-l AUXILI;2.Y TRA'!SFCRMER Location n!I l
Date Septe=ber 10, 1979' To J. R. THORPE GQM 3030 J. J. COLITZ D.
SLEAR
References:
- 1) FRC letter to R. C. A nold
- August 12, 1976 2). Met-Ei letter to NRC Septe=ber 16,1976 (GO.L 1313) i
- 3) Met-Ei le::er to URO
- August 15, 197T (COL 11'.5) h) URC letter to Met-Ed May 2, 1979
- 5) NRC~latter-to Me:-Ed_
August 3, 1979
- 6) HRC letter to Met-Ed
- August ik, 1979 On May 7,_1979 Met-Id_ received.a request from NRC to undertake a voltage study (Ref. L).
The purpose of this stud, is to dete=ine that, under i
vors: case. conditions, adequate voltage is supplied to ES co=ponents to assure that those cc:ponents can start and run.
Met-Ed began vorhing to resolve the issue and a group vas formed to work in this area.
"be group was co= posed of the following individuals:
1 Re C. Noll C. E. Har'.can A. C. East r
R. A. Lengel Initially, !*et-Ed told URO that we vould respond to the above mentier.ed request prior to re-starting T:C-1. URC has, however, requested that ve respond prior to October 15, 1979 By letter dated August 21, 1973 Met-Ed agreed to this date.
Thus fer, the abote sentioned Eroup has:
- 1) Performed.co=puter studies to determine bus voltages for various load conditions.
- 2) Verified the accuracy of the computer analysis regarding voltage drops, by u:ini; previoucly collected voltages and current data.
- 3) Reviewed and reached acreement c'$ loa:iing dcta, including loads expected to be added by TMI-l re-start =odificatio:ts.
IfjTER-OFFICE t.1ET.10R ANDU.'.1 s
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(s J. R. Thorpe J. J. Colits D. Slear "2-k) Obtained NRC interpreta. ion of "vorst-case conditions" (NRC (via telephone) has indiciated that for this study, off-site grid voltages should be chosen as those which are the lowest voltages anticipated to occur during the operating lifetime of the unit).
- 5) Developed a strategy for presenting / defending our choice of "vorst-case" 230 KV system conditions.
The computnr studies show that for degraded grid conditions, the voltage levels on ES busses dip below the-specific starting voltage requirements for the IS cotors Also,..for single ** miarf transfor er operatien, the voltage dip goes belov.the specified_ star:ing voltages even at nor a1 system voltages.
In addition, the veltage-s udy preliminary results have shov:. that in a n;:=ber of cases, the undervoltage protection system (U7PS) setpoints have been chosen such that the UVPS does not protect certain co=ponents against the under-voltage condition.
In addition, results show-that in order to protect these particular components against the undervoltage condition it vill be necessary to have the U7FS setpoint at a level such that, for single auxiliary transformer operation, UVPS relays ill be activated as a result of fluctuations within the nor=aL.operr. tin.- range cf 'the off-site, rid.
e In order to resolve these problems, it appeart caat hardvare modifications are necessary.
Among the nodifications which may solve the problem, are the following:
- 1) Addition of capacitor banks for affected ES busses
- 2) Add additional auxiliary transfor ers
- 3) Automatic trip of 20? loads on ES signal L) Automatic tap setting chances on existing auxiliary transformers y 5) Change block leading to reduce voltage steps me 6) Re-apportioning of 1cais to the new transformer which is proposed for pressurizer heaters.
Because hardware changes are required to solve these proble=s, ve request that prior to TMI-1 restart, GPUSO
- 1) review our efforts (see attachment) 2)
confirm our findincs
- 3) prepare the subtit:11 to ERO (prior to October 15, 1979), and h) pursue the installation of the required modifications.
If additional information is required, please contact any of the above mentioned members of the Met-Ed group which had been formed to investigate this area.
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BAL:tas R. A. Lcncel Attach =cnts Ext.
cc:
R. Vilnen (CPU)
W. E. Potta i
R. C. Arnold J. F. H11bish C. W. Smyth J. L. Seelinger File: el.0000.7T03 J. Torcivia R. C. Holl
- 1. L. Slake A. C. Rast J. G. Herbein L. W. Unrding C. E. Murtr.an R. W. Dennel w-
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