Text

Monthly Operating Repts for Apr 1995 for Limerick Generating Station
	ML20083L369
Person / Time
Site:	Limerick
Issue date:	04/30/1995
From:	Henricks D, Muntz J; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9505180301
	Download: ML20083L369 (12)
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Sanatoga. PA 19464 0920 T.S.6.9.1.6 May 15, 1995 7'

Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U.

S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555 i

Subject:

Limerick Generating Station Monthly Operating I

f Report For Units 1 and 2 Enclosed are the monthly operating reports for Limerick Units 1 and 2 for the month of April 1995 forwarded pursuant to Technical Specification 6.9.1.6.

j Very truly yours, ANV.

J es A. Muntz i

Director - Site Engineering I

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Enclosures i

cc:

T. T. Martin, Administrator, Region I, USNRC l

N.

S.

Perry, USNRC Senior Resident Inspector LGS W. G. MacFarland, Vice President, LGS 8

9505190301 950430 PDR ADOCK 05000352 R

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Docket No. 50-352 Attachment to MontNy Operating Report for 1

~

Apr51995 Limerick Generating Station Unit 1 AprN 1 through AprE 30,1995 1.

Narrative Summary of Operating Exoorlences J

Unit 1 began the month of AprH at a nominal 100% of rated thermal power (RTP).

On AprH 4,1995, at 1223 hours0.0142 days 0.34 hours 0.00202 weeks 4.653515e-4 months , power was reduced to 97.5% RTP due to high turbine backpressure. Power was restored to 100% RTP at 1850 hours0.0214 days 0.514 hours 0.00306 weeks 7.03925e-4 months .

On AprH 9,1995, at 0244 hours0.00282 days 0.0678 hours 4.034392e-4 weeks 9.2842e-5 months , power was reduced to 92% RTP 'or main turbine valve testing.

Power was restored to 100% RTP at 0420 hours0.00486 days 0.117 hours 6.944444e-4 weeks 1.5981e-4 months .

On AprH 9,1005, beginning at 1525 hours0.0177 days 0.424 hours 0.00252 weeks 5.802625e-4 months , power was reduced a number of times due to high turbine backpressure, to a minimum of 96% RTP, Power was restored to 100% RTP at 2200 hours0.0255 days 0.611 hours 0.00364 weeks 8.371e-4 months .

On AprH 11,1995, at 2105 hours0.0244 days 0.585 hours 0.00348 weeks 8.009525e-4 months , power was reduced to 90% RTP in order to remove the 'C' low pressure feedwater hester string from service due to a drain cooler tube leak. Power was restored to 100% RTP at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months on AprH 12,1995.

On AprN 12,1995, beginning at 1700 hours0.0197 days 0.472 hours 0.00281 weeks 6.4685e-4 months , power was reduced a number of times due to high j

turbine backpressure, to a minimum of 90% RTP. Power was restored to 100% RTP at 2235 hours0.0259 days 0.621 hours 0.0037 weeks 8.504175e-4 months .

On AprH 19,1995, beginning at 1130 hours0.0131 days 0.314 hours 0.00187 weeks 4.29965e-4 months , power was reduced a number of times due to high j

turbine backpressure, to a minimum of 88% RTP. Power was restored to 100% RTP at 0117 hours0.00135 days 0.0325 hours 1.934524e-4 weeks 4.45185e-5 months on April 20,1995.

On Apri 22,1995, at 1220 hours0.0141 days 0.339 hours 0.00202 weeks 4.6421e-4 months , power was reduced to 88% RTP due to high turbine backpressure. Power was restored to 100% RTP at 1535 hours0.0178 days 0.426 hours 0.00254 weeks 5.840675e-4 months .

1 On AprR 24,1995, at 1935 hours0.0224 days 0.538 hours 0.0032 weeks 7.362675e-4 months , the 'A' reactor feedpump tripped due to a faulty suction

- I pressure switch. Both reactor recirculation pumps ranback por design, reactor pressure vessel level increased to 40 inches and retumed its normal 35 inches, and power stabitzed at 77%

RTP. The faulty pressure switch was replaced and power was restored to 100% RTP at 0750 1

hours on AprH 25,1995.

On AprN 27,1995, at 1447 hours0.0167 days 0.402 hours 0.00239 weeks 5.505835e-4 months , power was reduced to 95% RTP due to high turbine i

backpressure. Power was restored to 100% RTP at 0017 hours1.967593e-4 days 0.00472 hours 2.810847e-5 weeks 6.4685e-6 months on AprH 28,1995.

Unit 1 ended this operating period at 100% of RTP.

11.

Challenoes to Main Steam Safety Relief Valves l:

There were no challenges to the Main Steam Safety Relief Valves during the month of Apri.

j l

.1 QVEROGE DOILV UNIT POWER LEUEL

~

' -e DOCKET NO. 50 - 352 UNIT LIMERICK UNIT 1 DATE MAY 11 1995 COMPANY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 MONTH APRIL 1995 DAY AVERAGE OAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MwE-NET) 1 1061 17 1036 2

1013 18 1024 3

1058 19 975 4

1044 20 1024 5

1066 21 1025 6

1062 22 1017 7

1054 23 1033 8

1062 24 992 9

1037 25 985 10 1054 26 1025 11 1042 27 1005 12 1008 28 1026 13 1029 29 1029 14 1037 30 1030 s

15 1033 16 1033 i

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OPEROTING DOVQ REPORT DOCKET NO. 50 - 352 DATE MAY 11, 1995 COMPLETED BY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 OPERATING STATUS 1

UNIT NAME: LIMERICK UNIT 1

( NOTES: THERE WAS 1 LOAD DROP 2.

REPORTING PERIOD:

APRIL. 1995

' GREATER THAN 20% THIS MONTH

3. LICENSED THERMAL POWER (MwT):

3293 DUE TO A REACTOR FEEDPUMP TRIP 4 NAMEPLATE RATING (GROSS MwE):

1092

5. DESIGN ELECTRICAL RATING (NET MWE):

1055 6.

MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): lb92 7.

MAXIMUM DEPENDABLE CAPACITY (NET MWE):

Ib5b 8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:

9.

POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MWE):

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH VR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 719 2.879 81.023

12. NUMBER OF HOURS REACTOR WAS CRITICAL 719.0 2.859.5 66 967

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 14 HOURS GENERATOR ON-LINE 719.b 2.841.2 65.866.7

15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (MWH) 2.349.718 9.305.436 203.621.974

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 766.2bb 3.b42.bbb bkI226.78b-

18. NET ELECTRICAL ENERGY GENERATED (MWH) 741.991 2.942.605 63.586.611

-=

PAGE 1 OF 2

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OPERQTING DATO REPORT (CONTINUED)

DOCKEY NO. 30 - 352 DATE MAY 11 1995 THIS MONTH VR-TO-DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 98.7 81.3

20. UNIT AVAILABILITY FACTOR 100.0 98.7 Rt.3

21. UNIT CAPACITY FACTOR (USING MDC NET) 97.8 96.9 74.4

22. UNIT CAPACITY FACTOR (USING DER NET) 97.8 96.9 74.4

23. UNIT FORCED OUTAGE RATE O.0 1.3 4.1 24 5HUTDOWNS SCHEDULED OVER NEXT 6 MONTMS (TYPE. DATE. AND DURATION OF EACH):

A 4 DAY PLANNED OUTAGE IS SCHEDULED fos; May 7 1995 FOR BOP ISSUES: DRAIN COOLER HEPAIR AND CONDENSER CLEANING.

25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITV 12/19/84 12/22/84 INITIAL ELECTRICITY MID APRIL 85 4/13/85 COMMERCIAL OPERATION IST QTR 86 2/01/86 PAGE 2 OF 2

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UNIT SNUTDOWNS CWD POWER REDUCTIONS DOCCIET NO. 50 - 3S2 UNIT NAME LIMERICK UNIT 1 DATE MAY 11 1995 REPORT MONTH APRIL, 1995 COMPLETED BY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.

DATE (1)L (HOURS)

(2)

REACTOR (3)

REPORT *

(4)

(5)

PREVENT RECURRENCE 55 950404 S

000.0 B

4 N/A HC HTEXCH REACTOR POWER WAS eZDUCED TO 97.5% DUE 4

TO HIGH TURBINE BACK PRESSURE.

4 56 950409 S

000.0 B

4 N/A HA VALVEX REACTOR POWER WAS REDUCED TC 92% FOR 4

MAIN TURBINE VALVE TESTING.

4 57 950409 5

000.0 B

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 96% DUE 4

TO HIGH TURBINE BACK PRESSURE.

4-58 950411 F

000.0 A

4 N/A HH HTEXCH REACTOR POWER WAS REDUCED TO 90% DUE TO 4

DRAIN COOLER TUBE LEAK.

4 59 950412 S

000.0 B

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 90% DUE TO 4

HIGH TURBINE BACK PRESSURE.

4 60 950419 S

000.0 B

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 88% DUE TO 4

HIGH TURBINE BACK PRESSURE.

4 61 950422 S

000.0 B

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 88% DUE TO 4

HIGH TURBINE BACK PRESSRE.

4 1

62 l 950424 F

000.0 A

4 N/A CM PUMPXX l REACTOR POWER WAS REDUCED TO 77% DUE TO 4

t t

(1)

(2)

(3)

(4)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

' FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE i

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x UNIT SHUTDOWNS AND POWER REDUCTIONS DOCCET NO. 50 - 352 UNIT NAME LIMERICK.

UNIT-1 g

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DATE MAY 11 1995 7

REPORT MONTH APRIL. 1995 COMPLETED BY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) T18-3TT2 METHOD OF LICENSEE SYSTEM : COMPONENT CAUSE AND CORRECTIVE

'I -

TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO.

DATE (1).

(HOURS)!

(2)

REACTOR (3)

REPORT #

(4)

(5)

PREVENT RECURRENCE REACTOR FEEDPUMP TRIP.

4 63 950427 5

000.0 8

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 95% DUE TO 4

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i HIGH TURBINE BACM PRESSURE.

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(2)

(3)

(4)

F = FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A - EOUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0181)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE

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G - OPERATIONAL ERROR (EXPLAIN)

H-OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE i

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~t' Docket No. 50-353 Attachment to Monthly.

Operating Report for Apr51995 Limerick Generating Station Unit 2 April 1 through AprH 30,1995 1.

Narrative Summary of Operating Experiences Unit 2 began the month of AprH at a nominal 100% of rated thermal power (RTP).

On AprH 2,1995, at 0100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months , power was reduced to 75% RTP for a control rod pattom adjustment and main turbine valve testing. Power was restored to 100% RTP at 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months .

On AprH 4,1995, beginning at 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months , power was reduced a number of times due to high turbine backpressure, to a minimum of 88% RTP. Power was restored to 100% RTP at 0040 hours4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months on Apru 5,1995.

On AprH 9,1995, beginning at 1550 hours0.0179 days 0.431 hours 0.00256 weeks 5.89775e-4 months , power was reduced a number of times due to high turbine backpressure, to a minimum of 95% RTP. Power was restored to 100% RTP at 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months .

On April 19,1995, beginning at 1635 hours0.0189 days 0.454 hours 0.0027 weeks 6.221175e-4 months , power was reduced a number of times due to high turbine backpressure, to a minimum of 95% RTP. Power was restored to 100% RTP at 2237 hours0.0259 days 0.621 hours 0.0037 weeks 8.511785e-4 months .

9 On AprH 22,1995, at 1310 hours0.0152 days 0.364 hours 0.00217 weeks 4.98455e-4 months , power was reduced to 95% RTP due to high turbine backpressure. Power was restored to 100% RTP at 1443 hours0.0167 days 0.401 hours 0.00239 weeks 5.490615e-4 months .

On AprH 29,1995, at 0455 hours0.00527 days 0.126 hours 7.523148e-4 weeks 1.731275e-4 months , the 'B' motor-generator drrse motor breaker opened, resulting in the trip of the 'B' reactor recirculation pump. The cause of this trip was due to a low lube ou pressure trip. Power was reduced, per procedure, and power was stabuized at 27% RTP. Lube oH pressure was increased and the motor generator set was started. Power was restored to 100% RTP at 0026 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months on AprH 30,1995.

On AprH 30,1995, at 2011 hours0.0233 days 0.559 hours 0.00333 weeks 7.651855e-4 months , power was reduced to 91% for a control rod pattem adjustment. Power was restored to 100% RTP at 2355 hours0.0273 days 0.654 hours 0.00389 weeks 8.960775e-4 months .

Unit 2 ended this operating period at 100% of RTP.

11.

Challenges to Main Steam Safety Relief Valves There were no challenges to the Main Steam Safety Relief Valves during the month of Aprl.

i

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1 AVERACE DOILY UNIT PODER LEVEL DOCKET NO. 50 - 353 UNIT LIMERICK UNIT 2 DATE MAY 11, 1995 COMPANY PECO ENERGY COMPANY

.-~~-.

DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 MONTH APRIL 1995 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)

(MWE-NET) 1 1133 17 1126 2

1031 18 1114 3

1129 19 1106 4

1080 20 1131 5

1133 21 1102 6

1132 22 1114 7

1120 23 1123 8

1128 24 1122 9

1112 25 1122 10 1130 26 1118 11 1130 27 1110 12 1118 28 1118 13 1126 29 617 14 1122 30 1113 15 1126 16 1122

wu 3

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I OPERATING DQVO REPORT 6

i DOCKET NO. 50 - 353 DATE MAY 11 1995 COMPLETED BY PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION.

TELEPHONE (610) 718-3772 OPERATING STATUS

1. UNIT NAME: LIMERICK UNIT 2 NOTES: THERE WERE 2 LOAD DROPS 4

2.

REPORTING PERIOD:

APRIL. 1995 GREATER THAN 20% THIS MONTH'

3. LICENSED THERMAL POWER (MwT):

3458 DUE TO ROD PATTERN ADJUSTMENT 4 NAMEPLATE RATING (GROSS MWE):

1163 AND REACTOR RECIRCULATION 1

5.

DESIGN ELECTRICAL RATING (NET MWE):

11

-PUMP TRIP.

t "f

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MwE): 1155

7. MAXIMUM DEPENDABLE CAPACITY (NET MwE):

1115 i

8.

IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS -

9.

POWER LEVEL TO wHICH RESTRICTED, IF ANY (NET MWE):

{

10. REASONS FOR RESTRICTIONS. IF ANY:

THIS MONTH YR-TO-DATE CUMULATIVE

'i

11. HOURS IN REPORTING PERIOD 719

-2.879 46.535

12. NUMBER OF HOURS REACTOR WAS CRITICAL 719.0-2.359.4 41.722.4

13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0

-r

14. HOURS GENERATOR ON-LINE 719.b 2 h51.8 '

40.856.7

15. UNIT RESERVE SHUTDOWN HOURS OO OO O.0

--- =

i

16. GROSS THERMAL ENERGY GENERATED (MwH) 2.446.284 6.508.539 128.738,122

17. GROSS ELECTRICAL ENERGY GENERATED (MwH) 817.700

- 2.159.900 42.543.480-

18. NET ELECTRICAL ENERGY GENERATED (MwH) 792.169 2.081.386 40.983.586.

PAGE 1 OF 2 a

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b OPERATING DATA REPORT (CONTINUED)

DOCKEV NO. 50 - 333 T

.eee_--

DATE MAY 11, 1995

_ - =

THIS MONTH YR-TO-DATE CUMULATIVE

{

19. UNIT SERVICE FACTOR 100.0 78.2 87.8 l

20. UNIT AVAILABILITY FACTOR 100.0 78.2 87.8

21. UNIT CAPACITY FACTOR (USING MDC NET) 98.8 65.5 83.3

22. UNIT CAPACITY FACTOR (USING DER NET) 98.8 65.5 83.3

23. UNIT FORCED OUTAGE RATE O.0 3.4 3.5 24 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):

25. IF SHUTDOWN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP:

26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 08/12/89 08/12/89 INITIAL ELECTRICITY 09/01/89 09/01/89 COMMERCIAL OPERATION 02/01/90 01/08/90 PAGE 2 OF 2

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UNIT SHUTDOWNS sMD POWER REDUCTIONS DOCKET NO. 50 - 353 i

UNIT NAME LIMERICK UNIT 2 DATE MAY 11 1995 REPORT WONTH APRIL. 1995 COMPLETED BV PECO ENERGY COMPANY DAVID R.

HENRICKS REPORTS ENGINEER SITE ENGINEERING LIMERICK GENERATING STATION TELEPHONE (610) 718-3772 METHOD OF LICENSEE SYSTEM COMPONENT ' CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE COOE ACTION TO NO.

DATE (1)!

(HOURS)

(2)

REACTOR (3)

REPORT *

(4)

(5)

PREVENT RECURRENCE j

42 950402 S

000.0 B

4 N/A RB CONROD REACTOR POWER WAS REDUCED TO 75% DUE TO 4

CONTROL ROD PATTERN ADJUSTMENT AND MAIN 4

TURBINE VALVE TESTING.

4 i

43 950404 S

000.0 B

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 88% DUE TO 4

HIGH TURBINE BACK PRESSURE.

4 44 950409 5

000.0 B-4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 95% DUE TO 4

HIGH TURBINE BACK PRESSURE.

4 45 950419 5

000.0 8

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 95% DUE TO 4

HIGH TURBINE BACK PRESSURE.

4 43 950422 S

000.0 B

4 N/A HC HTEXCH REACTOR POWER WAS REDUCED TO 95% DUE TO 4

HIGH TURBINE BACK PRESSURE.

4 47 950429 F

000.0 A

4 N/A CB PUMPXX REACTOR POWER WAS REDUCED TO 27% DUE TO 4

REACTOR RECIRC PUMP TRIP.

4 48 950430 S

000.0 B

4 N/A RB CONROD P ".* CTOR POWER WAS REDUCED TO 91% OUE TO 4

CONTROL ROD PATTERN ADJUSTMENT.

4 1

4 t

(1)

(2)

(3)

(4)

F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)

G - OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN)

EXHIBIT I - SAME SOURCE m-4 wt

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ML20083L369

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