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Supplemental Testimony on Ucs Contention 4 Re Connection of Pressurizer Heater to Diesel Generator,In Response to ASLB Request for Further Info.Prof Qualifications & Certificate of Svc Encl
	ML19350B845
Person / Time
Site:	Three Mile Island
Issue date:	03/12/1981
From:	Hartman C, Torcivia J; METROPOLITAN EDISON CO.
To:	;
References
	NUDOCS 8103230843
	Download: ML19350B845 (25)
	v • d • e

LIC 3/1.'/81 acuT2DCo?222M!"3C C UNITED STATES OF AMERICA NUCLEAR PIGULATORY COM11ISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

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METROPOLITAN EDISON COMPANY ) Docket No. 50-289 M'

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(Three Mile Island Nuclear )

Station, Unit No. 1) )

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LICENSEE'S TESTIMONY OF CHARLES HART M AND JOSEPH A. TORCIVIA l @ 05 ON DIESEL LOADING IN THE EVENT e-4 OF LOSS OF OFF-SITE POWER p

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OUTLINE Previous witnesses have testified that loading of the pressurizer heaters to the diesel generator may be desirable both in the case of a loss of off-site power condition and in the case of a loss of off-site power accompanied by a small break in the reactor coolant system. This testimony demonstrates that a single diesel generator has sufficient capacity to accommodate connection of the pressurizer heater load in addition to all safety-related loads required in each of the two cases.

This testimony also explains how the size of individual loads has been calculated.

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INTRODUCTION This testimony, by Mr. Charles Hartman, Lead Electrical Engineer, Plant Engineering, GPU, and Mr. Josepa A. Torcivia, Senior Project Engineer, GPU, supplements previous testimony on UCS Contention No. 4 (Connection of Pressurizer Heater to Diesel) and responds to the Board's request for further information on diesel loading in the event of a loss of off-site power.

Mr. Hartman's testimony covers the loading sequence and cumulative loads for two cases - loss of off-site power only and loss of off-site power combined with a small break LOCA.

Mr. Torcivia's testimony explains how the size of the individual loads enumerated by Mr. Hartman has been calculated.

TESTIMONY BY MR. HARTMAN:

Figure 1 attached to this testimony shows the size and timing of loads which would be connected to the diesel generator in the event of a loss of off-site power only.

Figure 2 provides similar information for the case of a loss of off-site power combined with a small break LOCA. For both cases B Diesel is assumed to be unavailable. Thus all loads are loaded on A Diesel. If both diesels are available the load would be divided between the two diesels and the load on either diesel would be less than the loading shown.

A Tables A and B, also attached to this testimony, prasent in tabular form the same information as Figures 1 and 2 and, in addition, supply a detailed listing of each of the loads connected to the diesel , generator.

Previous witnesses have testified that. loading of a pressurizer heater group to the diesel generator may be desirable both in the case of a loss of off-site power condition and in the case of a loss of off-site power accompanied by a smal]

break in the reactor coolant system. Figures 1 and 2 and their associated tables demonstrate that the diesel generator, rated at 3000 kw, has sufficient capacity to accommodate connection of the pressurizer heater load in addition to all safety-related loads required in each of the two cases. The pressurizer heaters are shown in Figures 1 and 2 to be added two hours after the loss of off-site power.

DISCUSSION OF FIGURE 1 The loading sequence shown for the case of a loss of off-site power only includes all safety-related loads required for that event. Note that Figure 1 also includes a number of non-safety related loads which, in the case of a LOCA, would be automatically disconnected upon receipt of an ES signal.

The loads in Figure 1 include valve loads which are required for two minutes or less before they complete their function and stop. For simplicity's sake all valves are shown as instantaneous loads and are discontinued after ten minutes.

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Safety-related loads are defined fo. ; ,oses of this testimony as those required to achieve and maintain the Unit in a safe shut-down condition or to support safety-related equipment. The major loads for those functions are:

a. Makeup Pump (HPI)

b. Motor Driven Emergency Feedwater Pump (although turbine driven Pump is sufficient)

c. Decay Heat River Pump

d. Nuclear Services River Water Pump

e. Nuclear Services Closed Cocling Water Pump

f. Decay Heat Closed Cooling Water Pump (LPI)

g. Control Building Ventilation

h. Reactor Building Ventilation

i. Inverters

j. Battery Chargers

~

k. Radiation Monitors

1. Area Lighting

m. Spent Fuel Cooling (required after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

Major loads which are not safety-related but which are desirable for equipment protection or ease of operations are:

a. Instrument Air Compressors

b. Pressurizer Heaters

c. Intermediate Closed Cooling Water Pump

d. Heat Trace

e. Main Turbine Turning Gear and Lift Oil Pumps

f. Substation Control Power

g. Screen Wash Pumps

.. ~ . .

h. Penetration Cooling Fan

i. Sump Pumps Not all of the safety-related loads would necessarily be required for the entire duration of the loss of off-site power. For example, assuming the availability of the Turbine Driven EFW Pump, the Motor Driven EFW Pump can be turned off.

Figure 1 shows this load change after 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months although switching to the Turbine Driven EFW Pump could be accomplished at any time after the loss of off-site power. Another load which could potentially be shed (but which is not shown to be turned off in Figure 1) is the Makeup Pump after the RCS has been cooled down to less than approximately 320 psig and 250'F. The operator could also reduce load on the diesel by realigning Nuclear Service Closed Cooling Water services to the Makeup Pump and then turning off Decay Heat Closed Cooling Water and Decay Heat River Water Pumps.

Actual loads for major pumps would probably be less than the maximum loads shown on Figure 1. For example, in the no LOCA scenario the Makeup Pump would be operating at about 120 gpm and would require 414 kw rather than 561 kw.

DISCUSSION OF FIGURE 2 Figure 2 loadings are based on small break sizes where the break is not sufficiently large ei.. ;h to depressurize the RCS within a two hour period to the Low Pressure Injection System operating range. In larger break sizes where the Reactor Coolant System depressurizes to Low Pressare Injection System operating range within the first two hours, the pressurizer heaters would not be of value.

The loading sequence shown in Figure 2 includes all safety-related loads required for a loss of off-site power coupled with a small break LOCA. The Reactor Building Spray Pump is assumed not to be operating since it starts when reactor building pressure is 30 psig. Small breaks which will not depressurize the Reactor Coolant System to the Low Pressure Injection range (and therefore possibly call for the use of the pressurizer heaters) would not result in reactor building pressures as great as 30 psig.

The safety-related loads for loss of off-site power with small break are automatically connected in a five block sequence by block loading timers and are similar to the loss of off-site power situation, except that the following two additional loads autcmatically start:

l a. Decay Heat Removal Pump (auto starts, but is ,

not required until RCS pressure is less than 300 psig.)

I b. A second Reactor Building Ventilation Unit Fan.

.The following loads are automatically tripped to reduce diesel loading:

a. Screen Wash Pump I b. Instrument Air Compressor

c. Main Turbine Lift Oil Pumps l

l d. Main Turbine Turning Gear l

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e. Reactor Coolant Pump Lift Oil Pump

f. Spent Fuel Cooling Pump

g. Intermediate Closed Cooling Water Pump

h. Borated Water Storage Tank Heater

1. Pressurizer Heaters (if connected to the class lE Bus)

Some of the loads that are automatically tripped may be manually started at a later time consistent with diesel loading. Examples of such loads are Instrument Air Compressor and Spent Fuel Cooling Pump, which are shown to be manually added in Figure 2 after tripping the Motor Driven EFW Pump.

BY MR. TORCIVIA CALCULATION OF LOADS This portion of our testimony explains how loads were calculated for the inaividual items of equipment listed in Tables A and B.

The majority of loads on the diesel generators are induction motors. The following formula has been used in calculating motor loads and converting Brake Horsepower (B.H.P.) ratings to Kilowatt (K.W.) ratings:

Load (K.W.) =

sfficiency For motors used to operate pumps, B.H.P. value is taken from the manufacturer's pump curve where available and from the name plate rating of the motor where pump curves are not available. Since motors are offered commercially in standard

w sizes, it is not uncommon to purchase motors with a higher rating than required to operate the pump and the full horsepower rating of the motor is not used at the design operating point. Service factor of the motors has been taken as 1.

The factor of 0.746 is a standard factor for converting horsepower to kilowatts. Motor efficiency data has been taken from Westinghouse and Reliance Applied Engineering Data for various size motors.

Following is an example calculation of the motor load for the Reactor Building Emergency Cooling River Water Pump, RR-PlA:

Motor Nameplate Rating = 400 H.P.

Pump Curve Rating = 380 H.P.

Efficiency = 0.92 80 = 08 Load (K.W.) =

09 Pure resistance loads, such as the pressurizer heater, are identified by their simple kilowatt rating. Corrections for efficiency are not required.

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TMt Unit 1 Engineered Safeguards Deesel Generator Loading Sequence on Loss of Offsite Power Only.1 A Diesel Generator Loading (18 Diesel Generator Not Available 1 A

p, i 3000 Manually Apphed Lo.eds 2004 "n

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+-SIop Emergency Feedwater Pump j '478 2499 y,

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2352 ,, @q P.ianually Applied Loads 2073 , i eate 126 K W.

7 2000 - -

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, Make-up Purnp 1512 @

1287-

) Decay Heat River Water Pump Discharge Strainer. Decay Heat River Water Pump Decay Heat Rever Water Pump Lube Pump. Decay Heat Closed Cooling Water Pump

Emergancy Feed Water Pump 1000 -

Notes 9210+@

1. @lohse2 table A fee the last ng of loads j 2. Pressurizer heaters ave not required

, g Directly Connected within twr> liours.

g and Auto Start Loads llowever diesel generator has enough a capacity to mclude theload j i t i I ,.ps e i e a a f .1 I I r a i T =0 10 20 30 40 50 60 0 10 20 30 40 50 60;'O i i o 77 1 2 3 4 5 12 20 i Bkr Close Seconds Minutes ttours I oad.ag Sequence

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TMl Unit 1 Engineered Safeguards Diesel Generator Loading Sequen::e on Loss of Of fsste Power wath Small Loca 1 A Diesel Generator Loading (IB Diesel Generator Not Available )

3000 Include" 2844 -

Psessunter I -

. Heaters L oad gpf@#7906

, : Stop Emergency Feedwater Pump

{7 2547 ll g II - @ 'p; s h ,,h 2624 2541

@- 2576

Auto Load Block 5

' i 2182 Manually Applied Loads Aut Load Block 4 2153 2000 -

1709_

Auto Load Block 2 1322_

b Notes:

1000 -

1 6)toOsee i ule a vor ihe asiino et .

so.wis

Directly conntected, Auto Start 2. Psessunzer heaters are not required and Autoload Block I w. thin Iwo hcurs liowever. dic3cl generator has enougt

- capJCaly to ar'clude it:e load E '

3 i I i I l t ul l L_ t I g y ,1 3 ,,,g ,, , , g 1=0 10 20 30 40 50 GO "O 10 to 30 40 50 60 "O I 2 " G " 12 " 24 " 48 Skr Close Seconds Minutes liour s ,

L o.Tdirdi S equertct-Ficure 2

TABLE A DIESEL CENERATOR LOADING ON LOSS OF OFFSITF POWER ONLY 1A Diesel Generator Loading -

(IB Diesel not available)

K.W.

Directly connected and auto start loads 1.

SW-Pin, Screen douse Vent Equipment Pump. 12.4 SW-P3A, Screen House Pumo Lube Pump 1.3 SW-P4A, Screen House Vent Pumn Lube Pune 1.1 1C-PIA, Intermediate Closed Cooling Pumo 62 NS-PIB, Nuclear Services Closed Cooling Dumn 94.3 NR-PIB,' Nucicar Services River t.'ater Purp 122 EC nlA, Eternancy Diesel Generator Stnrt Comnress.ir 3 IA-PlA, Instrument Ai r Comoressi.r 49

, DP-PIA, Diesel Generator A.C. Fuel Pump 0.5

RC-P2A, Reactor Coolant Pumo Hi Pressure Oil Lif t Pump 8.5

RC-P2C, Reactor Coolant Pump lli Pressure Oil Lift Pump A.9 AH-P8A/B, Cer. trol Tower Instrument Air Comoressor 0.5 SW-PIA, Screen Wash Pump 49 1

SW-SIA . Screen House Pump Discharge Strainer- 0.7 CO2 Pump. 1.4 WDL-PSA Auxiliary Building Sump Pump 4.6 SD-P3A & 4A, Emergency Feedwater Pump' Sump Pump 1.4 Valve Loads 01

Stop in 15 minutes 511.4 e

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TABLE A K.W.

2. Auto Applied Loads (immediate)

Panels'SH-1 4 Lighting Panal AB-1 1.1 Regulating Transic w.er TRA 10 Turbine Building Lightine Panel, TB1, 2 & 3 9.5 Control Building Lichtina Panel, CT-2 12.3 4RO-120/280V Feeder CT-5 26.5 Lighting Panel CT-1 13.4 Substation Control Power Transformer 19 Distribution Panel, AB-E 12 Emergency Lichting Panel, CVE 2.3 lleat trace, BS-TIB 7.3 Count Room MG Set 10 Heat Trace Panel, 3A-1 6.7 Heat Trace Panel, 3A-2 4.9 Borated Water Storage Tank !! cater. BKill 45.5 Heat Trace Panel, 4A 13.1 Heat Trace Panel, 3A 6.6 Heat Trace Panel 2A 14.4 Heat Trace Panel, 2A-1 4.6 Boric Acid Mix Tank Htr. 17.5 Inverters 45 Battery Chargers 47 Instrument Air Dryer 10 .

Radiation Monitor RMA4, 6 & 9 5.7 2 of 5 s

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TABLE A

2. '!U-P-3A, Make-up Pump - Main Oil Pumo n.5 MU-P-3D,ake-up Pu.p - Main Oil Pump 0.5 Diesel Generator Auxiliaries 21.

Fire System Jockey Pump Controller 1.4 Radiation Monitor, P24-Al 1.0 Radiation Monitor, R;4-L7 7.*

410.3 Dies ~el Loading 511.4 + 410.3 = 921.7

3. Auto Start in 5 seconds:

EF-P2A, Emergency Feedwater Punn 365.7 Diesel Loadine 921.7 + 365.7 = 1287.4

4. Manual started loads in 10 seconds:

DR-SIA, Decay Heat River Water Pump Discharge Strainer 1.3 DR-PIA, Decav Heat River Cater Pump 148.

DR-P2A, Decay liest River Water Pump Lube Pump 1.3 Dr-PIA, Decay IIcat Closed Cooline Water Pump ia.6 225.2 i Diesel Loading 1287.4 + 225.2 = 1512.6

5. Manual started loads in 15 seconds:

MU-PIA, Make-up Pump 561.

Diesel Loading 1512.6 + 561 = 2073.6 i

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TABLE A K .W .

6. Manual started loads in 10 minutes:

Valve Loads Removed -01 Control Building Chiller 136 AH-E24A, Air Cooll Fan for E7W Pump 12.5 AH-EISA, Air Cool Fan for DH & NSF 3.

AH-E27, Screen House Air Handline Unit 12.4 AH-E29A,. Diesel Cencrator North Fan 37 AH-P3A, Control Building Chilled Water Pump 37 AH-F19A, control Building Exhaust Fan 9 AH-E17A, Normal Vent Supply Fan 41 AH-E95A, Control Building Boost Tan 1,3 CA-PI A, Boric Acid Pu .o 1.4 AH-E9A, Penet ration Coolin Fan 62 219.S Diesel Loading 2073.6 + 219.A = 2203.4

7. Manual' started loads in 15 minutes:

~ RC-P2A, Reactor Coolant Pump Hi Pressure Oil Lif t Pump ( Stopped - 8.5 RC-P2C, Reactor Coolant Pump Pressure Oil Lif t Pump 0Ftopped ) - A.5 LOP-7C/D, Turbine Oil Lift Pump 8.7 LOP-7E/F, Turbine Oil Lift Pump 8.7 LOP-7A/B, Turbine Oil Lift Pump

_ 8.7 9.1 Diesel Loading 2293.4 + 9.1 = 2302.5 4'of 5

TABLE A ,

8. Manual started loads in 40 minutes K.W.

GN-Y1, Turbine Turning Gear 50 Diesel Loading 2302.5 + 50 = 2352.5

9. Manual started loads in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Pressurizer Heaters 126 Diese) Loading 2352.5 + 126 = 2478.5

10. Manual started loa'ds in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months AH-EIA, Reactor Building Vent Unit Fan 76 RR-P1A, Reactor Building Emer,qency Cooline River Water Pump 308 RR-P2A, Emergency Cooling Lube Pumn 1.3 RR-SIA, Reactor River Water Puen Discharte Strainer 1.

TOTAL 38A.3 h.v.

Diesel Loadinc 2478.5 + 386.3 = 2864.8 k.w.

11. Manual stopp.d load in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months EF-F2A, Emergency Feedwater Pump -365.7 k.w.

Disel Loading 2864.8 - 365.7 = 2499.1

12. Manual started loads in 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months SF-P1A, Spent Fuel Pump 33 AH-E8A, Spent Fuel Pump Air Unit 2 35 Diesel Loading 2499.1 + 35 = 2534.1 5 of 5

TABLE B DIESEL GENERATOR LOADING ON LOSS OF OFFSITE POVER WITH SMALL LOCA 1A Diesel Generator Loadine (1B Diesel - not available) l l Directly connected and auto start loads KR

Panel SH-1 4 Lichting Panel AE-1 1.1 Regulating Transformer. TRA in Turbine Building Lichting Panel T3-1. TB-2 and TB-3 9.5 Control Building Lighting Panel, CT-2 12.3 489-120/208V feeder, CT-5 26.5 Lightine Panel CT-1 13.4 Substation Control Power Transformer 49 Distribution Panel, AB-E 12 Emergency Lighting Panel, CVI-: 2.1 Pcat Trace, BS-TIB 7.3 Heat Trace Panel, 3A-1 6.7 Heat Trace Panel, 3A-2 4.9 Heat Trace Danel, 4A 13.1 Heat Trace Panel, 3A 6.6

. Heat Trace Panel, 2A 14.4 Heat Trace' Panel, 2A-1 4.7 Boric Acid Mix Tank Heater 17.5 Inverters 45 l

Battery Chargers 47

[ Instrument Air Dryer 10 Radiation Monitor RMA4, 6 & 9 5.7 MU-P3A, Make-up Pump Main Oil Pump 0.5 MU-P3B, Make-up Pump Main Oil Pump 0.5 Diesel Generator Auxiliaries 21 1 of 5

. ~. - - _ _ _ . . . _ . . - - . _ - _. . _ . . .

TABLE B Fire System .7ockey Tumn Controller 1.4 Sadiition Monitor,.u-Al 1.0 Radiation .ionitor, hr.-L7 7,5 Count Room MC Set 10 "alve Loads 91 TOTAL 455.9 k.w.

Auto 1.ond filock 1 MJ PIA, Make-up Pum 561 DH DIA, Decay lleat Pump 775 EG 81A, Emergency Diesel Cenerator Start Compressor 3 WDL-PSA, Auxiliary Building See Pump 4.A SD-P3A, E?crgcncy Feedwater Purp Sump Pump 0.7 SD-P4A, Emcrgency Feedwater Pump Sump Purp 0.7 AP-PSA, Control Tower Instru ent Air Comoressor 0 . '.

lic DIA Diesel Cencrator A. C. Fuci Pump 0.5 All-E29A, Diesel Generator North Fan 21 TOTAL 867 Diesel Loading 455.9 + P67 - 1322.9 k.w.

2. Auto Load Block 7 AII-EIA, Reactor Building Vent Unit Fan 38 AH-EIC, Reactor Building Vent Unit Fan 38 RR-P2A, Emergency Cooling 4,be Dumo 1.3 RR-SIA, Reactor River Water Pump Discharge Strainer 1 RR-PIA, Reactor Building Emergency Cooling River Water Pump 308 TOTAL 386.3 k.w.

Diesel Loading 1322.9 + 386.3 = 1709.2 k.w.

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TABLE B

3. Auto Load Riock 3 NR DIA, Nuclear Services River Water Pump 127 DR-PIA, Decay Heat River Water Pump 148 DC *1A, Decay Heat Closed Cooling Water Pump 74.6 NS-PIA, Nuclear Services Closed Coolins. Pump 94.3 NR-SIA, Nuclear River Water Discharge Strainer 1.0 DR-SIA, Decay Heat River Water Pump Discharge Strainer 1.3 NR-P2A, Nuclear River Water Pump Luhe Pump 1.3 DR-P2A, Decay Heat River Water Pumo Lube Pume 1.3

. TOTAL 441.0 Diesel Londinn 1709.2

441.8 a 2151. L.w.

4. Auto Load Block 4 SW-P2A. Screen House Vent Equipment Pump 12.4

. SW-P4A, Screen llouse Vent Pump Luhe Pump 1.1 A!!-E27A, Screen House f.ir Handling Unit 12.4 AH-EISA, Air Cool Fan for DH & NSP 3 TOTAL 20.1 Diesel Loading 2153 + 29.1 = 2182.1 k.w.

5. Auto Load Block 5 EF-P2A, Emergency Feedwater Pump 365.7 Diesel Loading 2182.1 + 365.7 = 2547.8 k.w.

3 of 5

TABLE B

6. Manual started loads in 10 minutes f

Valve Loads Stopped -91 control Building Chiller 130 l

AH-E95A, Control Building Boost Fan 1.5 AH-E19A, Control Building Exhaust van 9.

, AH-P3A, Control Building Chilled **ater Pump 17.

AH-E18A, Control Building Emergency Supply Fan 41.

AH-E24A, Air Cool Fan for Emercenev Feedvarer pump 12.5 Boric Acid Pump 2.

TOTAL 122 Diesel Loading 2547.8 + 122 = 2669.8 k.w.

7. Manual started inads in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months IA-PIA, Instrument Air Compressor 49 Pressurfrer Heaters 126 TOTAL 175 Diesel Loading 2669.8 + 175= 2844.8 k.w.

8. Manually started loads in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AH-E9A, Penetration Cooling Fan 52

-Diesel Loading 2844.8 + 62 = 2906.8 k.w.

9, Manual stopped load in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months EF-P2A, Emergency Feedwater Pump -365.7 Diesel Loading 2906.8 - 365.7 = 2541.1

10. Manually started load in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months AH-E8A, Spent Fuel l' ump Air Unit 2 SF-PIA, Spent Fuel Pump 33 TOTAL 35 Diesel Loading 2541.1 + 35 = 2576.1 k.w.

4 of 5

TACLC B

11. Manually started load in 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months 11 Recombiner 48 Diasel Loading 2576.1 + 48 = 2624.1 k.w.

t b

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PROFESSIONAL QUALIFICATIONS OF CHARLES HARTMAN EDUCATION: Bachelor of Engineering Technology in Electircal Engineering 1970, Capitol Campus of the Pennsylvania State University EXPERIENCE : Lead Electrical Engineer, Metropolitan Edison Company TMI-1, 1973 to present. Responsible for the support of plant operations and maintenance activities relating to electrical systems and components, including review of safety related procedures.

Member of the Plant Operations Review Committee.

Licensed Senior Reactor Operator for one year (1979)

Project Engineer, TMI-1, Metropolitan Edison Company 1970 to 1973. Duties included review of procurement specifications and vendor proposals, and preparation and/or review of operating test and maintenance procedures for TMI-1.

Engineering Assistant, TMI-1, Metropolitan Edistn Company 1969, review of drawings and preparation of procedures.

Technician Bell Telephone Laboratories 1967 to 1968 United States Army Military Police 1965 to 1967 PROFESSIONAL AFFILIATIONS: Member of IEEE, Registered Professional Engineer in the Commonwealth of Pennsylvania l

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u.w :c f,l MAR 161981 >

, CfEc3 cf tha kretary /

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION @YN BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITKd EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

CERTIFICATE OF SERVICE I hereby certify that copies of " Licensee's Testimony of Charles Hartman ind Joseph A. Turcivia on Diesel Loading in the Event of Loss of Off-site Power," were served upon the parties identified on the attached Service List by deposit in the United States mail, first class, postage prepaid, this 12 th day of March,1981.

] N

. /fAf4d ' /

eorge F.~ Trowbridg Dated: March 12, 1981

UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

. BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of )

)

METROPOLITAN EDISON COMPANY ) Docket No. 50-289

) (Restart)

(Three Mile Island Nuclear )

Station, Unit No. 1) )

CERVICE LIST Ivan W. Smith, Esquire John A. Levin, Esquire Chairman Assistant Counsel Atomic Safety and Licensing Pennsylvania Public Utility Com'n 4 Board Panel Post Office Box 3265 U. S. Nuclear Rcquiatory Commission Harrisburg, Pennsylvania 17120 Washington, D. C. 20555 Karin W. Carter, Esquire Dr. Walter H. Jordan Assistant Attorney General Atomic Safety and Licensing 505 Executive House Board Panel Post Office Box 2357 881 West Outer Drive Harrisburg, Pennsylvania 17120 Oak Ridge, Tennessee 37830 John E. Minnich Dr. Linda W. Little Chairman, Dauphin County Board Atomic Safety and Licensing of Comissioners Board Panel Dauphin County Courthouse 5000 Hermitage Drive Front and Market Streets Raleigh, North Carolina 27612 Harrisburg, Pennsylvania 17101 James R. Tourtellotte, Esquire (4) Walter 'J. Cohen, Esquire Office of the Executive Legal Director Consumer Advocate U. S. Nuclear Regulatory Commission Office of Consumer Advocate Washington, D. C. 20555 14th Floor, Strawberry Square Harrisburg, Pennsylvania 17127 Docketing and Service Section (3) 4 Office of the Secretary U. S. Nuclear Regulatory Commission

. Washington, D.'C. 20555 f

9

-;--e . _ . . r , , .-y . , , , - -

Jordan D. Cunningham, Esquire William S. Jordan, III, Esquire Fox, Farr & Cunningham Harmon & Weiss 2320 North Second Street 1725 Eye Street, N. W., Suite 506 Harrisbu g, Pennsylvania 17110 Washington, D. C. 20006 Ms. Louise Bradford ' Robert Q. Pollard TMI ALERT 509 Montpelier Street 315 Peffer Street Baltimore, Maryland 21218 Harrisburg, Pennsylvania 17102 Chauncey Kepford Ellyn R. Weiss, Esquire Judith Johnsrud Harmon & Weiss Environmental Coalition on Nuclear 1725 Eye Street, N. W., Suite 506 Power Washington, D. C. 20006 433 Orlando Avenue State College, Pennsylvania 16801 Steven C. Sholly Union of Concerned Scientists Marvin I. Lewis 1725 Eye Street, N. W., Suite 601 6504 Bradford Terrace Washington, D. C. 20006 Philadelphia, Pennsylvania 19149 Gail Bradford Marjorie M. Aamodt ANGRY R. D. 5 245 West Philadelphia Street Coatesville, Pennsylvania 19320 York, Pennsylvania 17404 Attorney General of New Jersey Attention: Thomas C. Germine, Esquire Deputy Attorney General Division of Law - Room 316 1100 Raymond Boulevard Newark, New Jersey 07102 v -

ML19350B845

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