ML19270H479
| ML19270H479 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/30/1978 |
| From: | Herbein J Metropolitan Edison Co |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| G-712-12-581, NUDOCS 7908270547 | |
| Download: ML19270H479 (20) | |
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Post cmcs sox 542 REAciNc. PENNSYLVANI A 19603 TELEPHOolE 215 - 929 3501 March 30,19T8 GC.L 0569 Director cf Nuclear Reactor Regulation A::n:
!'r. S. A. Varga, Chief
~ight 'Jater Reactors Branch
.. S. :Tuclear Regulatory Cc==ission Jr.shingten, D.C.
20555 2 ear Sir:
Three Mile Island Nuclear Station Unit 2 (.TMI-2)
Docket :To. 50-320 License No. DPR-T3 At ached please find a report which provides the docunentaticn and confirnation of ccrrect voltage tap settings required by Condition 3.1 er attachment 2 to Operating License DPR-73 Sincerely, S'cid 'J. G. :-:2. be;,,-
J. G. Herbein Vice President-Generation GF.: C'..'3 : t as Attachnent File:
62.0016.0001.0001.02 7908270[
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Three Mile Island Nuclear Power Plant Unit 2 Optimization and Verification of Bus Voltages On March 23, 1978 a bus voltage measurement test program was implemented for the Three Mile Island Unit 2 electrical dis-tribution system.
The purpose of these measurements was to gather sufficicnt field data which could then be ccmpared with the analytical results for similar conditions, and thus establish a level of confidence on the ability of the analytical program to predict bus voltage behavior during different plant load conditions.
Voltage measurements were taken on various buses while observing the operating loads en these buses.
Since the plant was essentially in a shutdown mode the various pumps which were allcwed to run on the different buses were not operating at full load, anf thus pump horse power nameplate rat-ing could not be used as an indication of the actual electrical load.
Bus voltage and current measurements were taken instead, on the various buses in order to arrive at a KVA load for each bus which would more closely resemble the actual load.
For the purpose of these tests and in order to confine the person-nel involved and the areas to be covered to a manageable number, the plant electrical distribution system was divided into four major areas, to coincide closely with the physical layout of the equipment.
Area 1:
Control Room and Control Building Elevation 351' (Bus 2-12E and Bus 2-22E)
Area 2:
Turbine Building Elevation 305' (Buses :
2-1, 2-3, and 2-4)
Elevation 331' (Control Panel 316) and Control Bldg.
Area Elevation 280' (Control Panel 317)
Area 3:
River Water Pump House (Buses:
2-3E, 2-42, 2-31E, and 2-41E)
Area 4:
Auxiliary Bldg. Elevation 32S' (Bus 2-lE and 2-2E) and Elevation 305' (Bus 2-11E and 2-21E)
Ir order to take readings on all buses at essentially the same time, one test group tas sent to each of these areas.
As part of the Tes: Procedure, data shcots for each area were prepared in advance, which outlined what measurements.ic re to be taken, t e re they neaix1 tobe taken, and h *.* to take them.
To reduce the amount of time required cc ccmpletc the entire test procedure, a number of meters.ecre set up in advance.
Page 2 Digital portable meters were used to measure valvues of currents and voltages.
Power factor meters were also used on some buses.
Coordination among the various crews was established via a common channel of the existing paging system.
At 8:00 p.m., March 23, 1978, the bus voltage measurement program started.
It concluded at 3:45 p.m.
The results of the tests are shown on Table 1 as well as on Figure 1.
In order to correlate the measured values with the analytical results, a computer program was prepared which recreated the plant conditions during the test.
The computer was then askcd to print out expected bus voltage values for these same con-ditions.
The results of the computer analysis are shown on Table 2 and on Figure 1.
Comparison of the actual measured valu'eh~ahd the ecmputer analysis, as shown on Figure 1, indicates that the analytical results are within 2% of the measured values in most cases.
The ability of the computer analysis to predict bus voltage values at different plant operating conditions can thus be established.
By using the same analytical approach, it has been determined that in order to optimise the voltages at the various buses, the transformer taps at all the Unit Substations buses must be set at -2.5%,
as currently exists.
Table 3 below shcus the expected voltages at the different buses during the normal operating grid voltage range of the plant.
Page 3 TABLE 3 (1)
VOLTAGES PROFILES AT THE SAFETY RELATED BUSES (2)
Full Load No Lead Bus Min. Normal Max. Normal Min. Normal Max. Normal 230KV GRID 232KV 238KV 232KV 238KV 4.16KV 2-lE 4.196KV 4.305KV 3.889KV 4.007KV 4.16KV 2-2E 4.196KV 4.305KV 3.871XV 3.989KV 4.16KV 2-3E 4.196KV 4.305KV 3.886KV 4.004KV 4.16KV 2-4E 4.196KV 4.305KV 3.871KV 3.989KV 480V 2-llE 496V 509V 452V 466V 480V 2-21E 496V 509V 449V 463V 480V 2-12E 496V 509V 460V 474V 480V 2-22E 496V 509V 454V 468V 480V 2-31E 496V 509V 460V 474V 480V 2-41E 496V 509V 453V 466V 120V 2-11E3 124V 127v 113V 117V (1)
Based on tap settings of -2.5% at USS Transformers and nominal tap at the Aux. Transformers.
(2)
No Load Condition is assumed when the unit is shutdown and only the essential services are fed from the corresponding buses.
VOLTAGE RANGE FOR SAFE EQUIPMENT OPERATION Safe Operating Range Design Minimum Maximum Device Value Voltage Voltage B:oters 4000V 4000V 3600V 4400V Motors 4 GOV 460V 414V 506V Magnetic Starters 480V 384V 52SV Solenoid Valves 120V 102V 140V Instruments ll8V 106V 130V It can thus be concluded that the equipment should operate nafelk scithin the normal operating grid voltage range.
TABLE 1
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Page 1 of 6 Area 1 Control Room and Control Buildinc Elevation 351' CONTROL ROOM Measured CT or Value at PT
= Actual Component Location CT/PT x
Ratio Value Grid Voltage System 238KV Dispatcher 2A Aux. Transf. Pri. Amps Panel 6A
.4 50 24 2B Aux. Transf. Pri. Amps Panel 6A
.7 60 42 Bus 2-5 Volts Panel 6A 68.6 13~
35 4158.5 Bus 2-6 Volts Panel 6A 69.5 -[3-35 4213.1 Bus 2-5 Amps Panel 6A
.7 400 280 Bus 2-6 Amps Panel 6A
.84 400 336 0
Bus 2-5 Power Factor Panel 6A 41
(.75)
Bus 2-6 Power Factor Panel 6A 39.5
(.77)
Bus 2-2 kw Meter Panel 6A 6.5 MW Bus 2-3 kw Meter Panel 6A 2.5 MW Bus 2-4 kw Meter Panel 6A 0
MW Bus 2-5 kw Meter Panel 6A 3.0 MW Bus 2-6 kw Meter Panel 6A 3.8 FM Bus 2-2E kw Meter Panel 6C
.7 MW Bus 2-1E kw Meter Panel 63 1.0 MW CONTECL SUILDING ELEVATICN 35I' Measured CT or Value at PT
= Actual Cen; nen:
Unit E CT/PT Ratio Value USS 2-125 Volts 33C 120.4 4
481.6 U55 2-12E Arps 323
.6 600 360 C5i 2-22E Volts 41C 122.6 4
488 C3F ;-22E 7.=ps 423
.3 600 150
TABLE l-Page 2 of 6 AREA 2 Turbine Bldg. Elev. 305 (Bus 2-1 and 2-2)
Measured PT or Value at CT Actual Equipment Unit No.
CT/PT Ratio value Bkr. 2A-12 Amps 1-5 NA 400 0
Bkr. 2B-12 Amps 1-2 2.5 400 1000 Bus Volts 1-1 116.7 60 7002 RC-P-1A Amps 1-3 1.9 240 456 RC-P-1B Amps 1-4 2.3 240 552 Bkr. 2A-22 Amps 2-2 1.4 400 560 Bkr. 2B-22 Amps 2-5 NA 400 0
'us Volts 2-1 118.2 60 7092 a
RC-P-2A Amps 2-4 NA 240 0
RC-P-23 Amps 2-3 2.3 240 552 Bus 2-3 Volts 120.2 35 4207 Bus 2-3 Amps
.8 600 480 Sus 2-4 Volts 121.2 35 4242 Sus 2-4 Amps
.2 600 120 Sus 2-3 Power Factor 34.50 (0.82) 33 2-4 Power Factor 32-350 (.84-52)
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TABLE 1 Page 3 of 6 l'
AREA 3 River Water Pump House Bus 2-3E Measured CT or Value at PT Actual Component Unit No.
CT/PT Ratio Value NR-P-1A Amps 3E-3 NA 20 NA NR-P-1B Amps 3r-4 2.3 20 46 Bus Volts 3E-5 118.65 35 4152.7 Bus 2-4E NR-P-lD Amps 4E-1 2.3 20 46 NR-P-1C Amps 4E-3 NA 20 NA Bus Volts 4E-5 120.55 35 4217.5 Bus 2-31E Bus Amps FTl 0.2 60 12 Bus Volts llc 123.08 4
492.3 Bus 2-41E Bus Amps 21C 0.3 60 18 Bus Volts 22C 124.25 4
497 Component Location On/Off SW-P-la Control Panel 326 CFF SM-P-1B Control Panel 326 OFF
Page 4 of 6 '
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AREA 4 Auxiliary Building 328 Measured CT or Value at PT Actual Ecuipment Unit No.
CT/PT Ratio Value Bus 2-lE Bkr. 2A-lE2 Amps lE-10 NA 400 0
.5 400 200 Bus Volts lE-1 118.6 35 4151 BS-P-1A Amps lE-4 NA 20 0
MU-P-1A Amps lE-5 NA 30 0
MU-P-1B Amps lE-6 2.1 30 63 Skr. TlE-3E
-2 Amps lE-7
.6 80 48 EF-P-2A Amps lE-8 NA 20 0
Bkr. lE-12E-2 Amps
.5 30 DH-P-1A Amps lE-9 NA 20 0
Power Factor 37
(.798)
Brk. lE-llE
-2 Amps
.9 60 54
TABLE 1 Page 5 of 6 AREA 4 Auxiliary Building 328 Measured CT or Value at PT Actual Equipment Unit No.
CT/PT Ratio Value Bus 2-2E Bkr. 2A-2E2 Amps 2E-15
.3 400 120 Bkr. 23-2E2 Amps 2E-12 NA 400 0
BS-P-1B Amps 2E-5 NA 20 0
MU-P-lC Amps 2E-6 NA 30 0
MU-P-1B Amps 2E-7 NA 30 0
.6 80 48 Bus Volts 2E-9 120.5 35 4217.5 EF-P-23 Amps 2E-10 NA 20 0
DH-P-1B Amps 2E-ll NA 20 0
Phase Angle 44"(.719) 2E-22E Amps
.4 24 2E-21E Amps
.9 54
TABLE 1 Page 6 of 6 AREA 4 Auxiliary Building 305 1.
Continued Bus 2-11E CT or Measured PT Actual Components Unit No.
Value Factor V;1ue Bus Volts 13C 119.6 4
4 E.4 A=ps 12B
.8 600 480 Bus 2-21E Bus Volts 21C 121.1 4
484.4 Bus Amps 22B
.7 600 420' e
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POST C:8CE EOX 542 REACING, PENNSYt. VAN! A 19503 TELEPHCNE 215 - 923 0601 March 29, 1978 G^.,L 05kT y e },
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Fr. S. A. Varga, Chief p si s S
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Three Mile Island nuclear Station Unit 2 (TMI-2)
Decke: Uc. 50-320 License No. DFR-73 Fover Operr.tien With Three Reacter Coolant Fune.s As a result of the failure of the anti-rctational device en reacte: ecclant pu.; 2A at TV.I-2s ve intend to operate the plant usin6 three reactor ecclant The affected pu=p is presently blocked in position so that it cannet
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re: ate in either the forward or reverse direction. At present, ve expect to
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..ci hree pu=p cperation for safety concerns an:i/cr potential unreviewed safety iss es.
Based upcn review of decketed naterial for plants of si=ilar desi6n s.:.i ;cver level, ve concluded t, hat three r.u=c. cr.eration within the cresent te:h.ical specifications presents neither safety concerns nor ans-viciation
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Director of ;uclear Reactor Regulation March 29, 1978 G^,.L 05LT Due to the operation of TMI-2 as a che:ical shim controlled plant (i.e. rods are nearly ec=pletely withdrawn frc the cere) and technical specification li=its en pcver level as a function of the nu=ber of opere. ting pumps, localiced A=-
ge is considered extremely unlikely.
- Tevertheless, ve agree that it is appropriate to operate the plant using the folleving limits :
?q < 2.35
=
P vhere Fq = the radial x axial peaking factor, e.nd p = ther=al rever Me ' - '-' allovable ther=al power for the existing pu=p cc=binatien as requested by the Staff.
3 Sincerely, Signed.'. G. liedd J. G. Herbein Vice President-Generation
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G. T. Ercughton (GPUSC) bec:
Mrs. Pat Higgins R. M. Klinga an Edison Electric Institute N.
Kucannis (G?USC) 90 Park Avenue New York, New York 10016 L. L. Lawyer R. A. Lengel*
G. P. Miller Kr.
1.'. R. Gibson D. G. Mitchell*
Er.becek & L.'ilecx C. A. I'ixdor f P.O. Sex 1260 Lyncht.:rg, 'la.
2h505 J. P. O'Ranlon R. U. Prabb=.kar*
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Please revie.t the attached proposed changes and recurn ycur co==ents to
?. A. T engel befere k/3/78.
These changes cancern Secti ns 2.2.1 and c.12.1.c cf Appendix A cf the Unit's Technical Specifica:icns, and have been requested
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Actachnents ec: Sec retar-/ T:C-2 ? CEC Secretar~/ T'C -2 GEC Secretary T:C-2 GC?3 J. 3. Stair File: 62.0050.0005.0003 If.T E R -O F F IC E f
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3 Freccsed Technical Scecificacion Chanze Recuest #10h IA)
The licensee requests that the attached changed page replace paga 2-3 cf the existing Technical Specifications.
F.eason for Proposed Chanze nur4.3..~ *.ke *e~4.d o.# '. ' =., e'"s*, s.4-. ' o 5 ^-.". 7 4 - a....- #.3, + k.. a.
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and allevable values for certain reae:cr protection systen functional units underwent a nu=ber of changes while Me:-Id was attenpting to resolve the dif-ference between allevable values and actual trip se: points.
h reviewing Fig.
2.2-2 in the License Edition of the Technical Specifications, it was realized through a clerical error, the max 1=u: power levels at imbalance li=its of -37.6%
to +3S.6% were not shewn ecrrectly.
The tax pcuer levels at the -=x imbalance limits were correctly shown en Figure 2.2-2 in the "Freef and Review" copy of the Technical Specifications dated August 2h,1977, a ecpy of vnich is attached for inecrporation.
Safety Anal:rsic Justi^ ting Change The requested change results in a =cre conservative limitation on the taximun ellevable nuclear overpever trip setpoint when an axial imbalance limit exiscs.
Therefore, operation in a core conservative " - er vill not produce an i= pact en safety a::alyses which have already been perforced.
.-Isti ated Cost of Change
$1,200.00 - per HEC's new rate schedules
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1 Three Mile Island Tuclear Station, Unit 2 Operating License ::0. :?2-73 Docket :fo. 50-320 Frencsed Technical Specification Change Recuest #10h (A)
The licensee requests that the attached changed page replace pagt 2-8 cf the existing Technical Specifications.
Feason for Froncsed Change During the period of time, just prior Oc Unit Licensing, the trip setpoints and allavable values for certain reacter protection systen functional units underwent a nu=ber of changes while Met-Ed was attempting to resolve the dif-ference between allovable values and actual trip setpoints.
In reviewing Fig.
2.2-2 in the License Edition of the Technical Specifications, it was realized through a clerical error, the maximum power levels at imbalance li=its of -37.65 to +33.6% were not sh0vn correctly. The tax power levels at the =ax i= balance li=its vere correctly shown en Figure 2.2-2 in the "?rcof and Review" copy of the Technical Specifications dated August 2h,1977, a copy of which is attached for incorporation.
Safety Analysis Justifying Chanze The requested change results in a : ore conservative limitatien en the naximun allevable nuclear overpower trip setpoint when an axial imbalance limit exists.
Therefore, cperation in a = ore conservative -- ner vill not produce an i= pact en safety analyses which have al: aady been perforced.
Esti ated Cost of Chance
$1,200.00 - per URC's new rate schedules
3ree :411e Island ::::les: Statien, Unit 2
- erating License '.
- o. DPR-73
- ket No. 50-320 Fre :esed Technical Steeification Chance The licensee requests that the attached changed page replace page' 6-20 of the e:.:isting TMI-2 Technical Specification.
Feasen for P-etesed Change Tne proposed change vould allev the ?.adiation Protection Forenan to have access and centrol of keys to high radiation areas, thus allowing 20re i==ediate ac-cess to tha areas if necessary, without appreciably decreasing the aMnistrative control for such areas.
Safety Analysis for Procesed Change The proposed change to the TMI-2 Technical Specifications is entirely ad=inistrative in nature, and therefore, has no impact en the safety analyses which have already been perforned.
Estinated Cost of Prorcsed Chance S1,200.00
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A radiation monitoring device which continuously integrates the
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radiation dose rate in the area and alarms when a preset inte-grated dose is reccived. Entry into such areas with this monitoring device may be made after the dose rate level in the
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An in.ifvidual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation 'Jork Permit.
5.12.2 The requirements of 6.12.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem /hr.
In addition, locked doors shall be provided to prevent unauthorized entry into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor or Shift Foreman on duty and/or the Radiation Protection Supervisor, of For-~,n.
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