ML20059L012

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Monthly Operating Repts for Aug 1990 for Peach Bottom Units 2 & 3
ML20059L012
Person / Time
Site: Peach Bottom  
Issue date: 08/31/1990
From: Baron M, Miller D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9009260049
Download: ML20059L012 (14)


Text

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PHILADELPHLA ELECTRIC COMPANY PT.ACil BUI"IDM ATOMIC PO4TR STATION R. D.1. Ikis 208 Iktta, Itnnsylvania 17314 poum mornus.4sa nma or turuswe C17) 4W7014 D. B. Whr, Jr. N Preiktent September 14, 1990 Docket Nos. 50 ^77 50 278

U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

SUBJECT:

Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen: Enclosed are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of August 1990 forwarded pursuant to Techmcal Specification 6 9.1.d.ander the guidance of Regulatory Guide 10.1, Revision 4. Sincerely,' 1 A DBM/ A / M/ cme Enclosure-cc: R.A. Burricch;, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania - JJ. Lyash, USNRC Senior Resident inspector R. McLean, State of Maryland T,T. Martin, Administrator, Repion 1, USNRC II.C, Schwemm. Atlantic Electric / J. Urban, Delmarva Power if i INPO Records Center j (XIE90.NRC p,am. t.-> 9009260049 900831 PDR ADOCK C5000277 Pu R PDC a:,

5 y, 3 + S. e :. =.. m NRC Monthly Operations Summary Peach llottom Atomic Power Station August 1990 - UNIT 2 Unit 2 began the month at 10J% power. Power was reduced on August 14 for a control rod pattern adjustment and returned to 100% power by the evening (,f the same day. Power was again reduced on August 22 to perform h second rod pattern adjustment. At this time, scram time testing of selected rods, MSIV full closure timing and maintenance on the *2C" condensate pump and "2A* cire

water pump was performed. Testing and maintenance were completed the same day and power increases were started but held at 52% power because of a packing leak on the "B" outboard MSIV. Power increases were started after the leak was repaired and the vaht was stroked satisfactorily. Power was held at 73% pending _

engineering evaluation of the repair. On August 25 the *2A" recirc pump tripped while swapping tube oil pumps. Cause of the trh was determined to be a faulty pressure switch on the lube oil system. The "2A" recire pump tripped again on August 25 and this - time the cause was found to be a defective Agastat relay in the tube oil pressure logic. The relay was replaced and power was increased to 70%. The engineering evaluation for the MSIV repair was received on August 28, the block was cleared and the inboard MSIV was opened. Power was then increased to 80% and held at that level because of feedwater copper at greater than 0.3 ppb. The unit was shut down on August 30 because of inoperable reactc; head chamber level transmitters, and the' unit ended the month shut down with investigation of the problem in progress. UNIT 3 The unit started the month recovering from the manual scram last month which was inserted because of low condenser vacuum. The unit reached 100% power by August 6.

Power was reduced to 55% on August 7 for a control rod pattern adjustment which was completed that same

' day, and a gradual power increase to 100% was completed on August 9.

A load drop to 760 MWe was taken on August 11 for maintenance to the "3C" reactor feed pump. Maintenance was completed that same afternoon and the unit was returned to 100% power on August 12.

~ ' Power was reduced to 65% on August 17 to facilitate waterbox inspection and repair Repairs were completed . and the unit returned to 100% power by the afternoon of Aumst 20.The unit remained at 100% power for tla rest of the month. i tw s CCXt%7.NRC 1 i 1-l -u. ma

w r 3 ,q e fu< -1 f. q, l- .[ i m i, ; ,l i Docket No. 50-277 : i Attachment to i p" ., Monthly Operating. .l J . Report for August 1990 : ~[ ~~ l UNIT 2 REFUFLING INFORMATION r .-s d 1. . Name of facility: Peach Bottom Unit 2 2. Scheduled date for next refueling shutdown: I

i. '

January 5,1991

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3. Scheduled date for restart following refueling: 1 .i April 5,1991 + , 4. . Will refueling or resumption of operation therefore require a technical specification change or other ~ license amendment? t Yes. 3 if answer is yes, what, in general, will these be? Safety limit MCPR for cycle 9 fuel. ' 5. Scheduled date(s) for submitting proposed licensing action and r.upporting information: A , January 1991 t 6. Important licensing considerations associates with refueling, e.g., new or different fuel design or supplier, unretiewed design or performance analysis methods, significant changes in fuel design, new operating. ,g procedures: ' ~~

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?The number of fue; assemblics (a) in the core and (b) in the spe it fuel storage pool: i (a) Core 764 Fuel Assemblies ( (b) Fuel Pool 1734 Fuel Assemblies,58 Fuel Rods J ~ l f CC0890.NRC l: !,h

l , ;;,, 9 ~ %V. re - 3 4,t;( p, y.., __, . * : t fg. l :f e. l F Docket No. 50-277 ' = Attachment to Monthly Operating - . Report for August 1990 : .y. > i' Page 2, ? UNIT 2 REFUELING INFORMATION (Continued) m i 1 - 8. ; The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage i , capacity that has been requested or is planned, in number of fuel assemblies: The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies. ,u.. 9. .The projected, date of the last refueling that can be discharged 'to the spent fuel pool assuming the - -[ present capacity:., September 2003 without full core offload capability, 'i' September 1997 with full core offload capability. ? i i i n. l , i;-. r 3 -t 3 .')\\ i [, If i,l 1 1

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N i .. :l ...) ' Docket No. 50-278 p" A ! Attachment to -- i C,. Monthly Operating. l' Report for August 1990c (; .p i e UNIT 3 REFUELING INFORMATION - 1. Name of facility:- Peach Bottom Unit 3 2. ~ Scheduled date for next refueling shutdown: q Reload 8 scheduled for August 31,1991 ' 3. . f Scheduled date for restart following refueling

Restart following refueling scheduled for November 29,1991 4.

Will refueling or resumption of operation thereafter require a technical specification change or other - t we ' license amendment? Yes. If answer is yes, what, in general, will these be? 3 Safety limit MCPR for cycle 9 fuel. u 5.1 Scheduled date(s) for submitting proposed licensing action and supporting information: io August 1991 n 5. Important licensing co'nsiderations associated with refueling, e.g., new or different fuel design or supplier, N _ unreviewed design or performance analysis methods, significant changes in fuel design, new operating. procedures: } .i 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pooli-r T (a) Core 764 Fuel Assemblies (b) Fuel Pool 14% Fuel Assemblies,6 Fuel Rods CC0890.NRC s

f ' y: m y An, u cg, .s y a :y p o. gl -l 7l [..'; L. f. 'j yB. s9 Docket No. 50-278 Attachment to' -l e 1 Monthly Operating Report for August 1990 g. Page 2 m UNIT 3 REFUELING INFORM ATION (Continued). - 8. The present licensed spent fuel pool sto:oge capacity and the size of any increase in licensed storage capacity that has been requested or is planned, m number of fuel assemblies: The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblics. Modification - = of the fuel pool is expected to be complete in the fourth quarter of 1990. J - 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the'- present capacity:- - With the current fuel pool capacity (prior to the completion of the fuel pool reracking modification): September 19(X) without full core offload capability. . End of next cycle with full core offload capability (est. January 1991). With increased fuel pool capacity (subsequent to the completion of the fuel pool reracking modification):

September 2004 without full core offload capability.

September 1998 with full core offload capability. d f b t t a r 7 ) E k N -f 4 t CC0890.NRC m m

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Y OPERAilNG DATA REPORT' DOCKET NO. 50 - 277-DATE SEPTEMBER 15.-1990-COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M.'J. BARON SUPERVISOR REPORTS GROUP PEACH BOTTOM ATOMIC POWER STATION - TELEPHONE (717) 456-7014 EXT. 3321-- OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 2.-

NOTES: IV

2. REPORTING PERIOD:

AUGUST, 1990

3. LICENSED THERMAL POVER(MVT):

3293

4. NAMEPLATE RATING (GROSS MWE):

1152 5.DESIGNELECTRICALRATING(NETMWE): 1065 6.HAXIMUMDEPENDABLECAPACITY(GROSSMWE): 1098 7

7. MAXIMUM DEPENDABLE CAPACITY (N.. MWE):

1055 J 8.1F-CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) $1NCE LAST REPORT, GIVE REASONS: 9'. POWER LEVEL.TO WHICH RESTRICTED,,IF ANT (NET MWE): p.

10. RCASONS FOR RESTRICTIONS, IF ANY:

1 1 THIS MONTH YR-TO-DATE CUMULATIVE 11, HOURS IN REPORTING PERIOD - 744 5,831 141,647 -12. NUMBER OF HOURS ~ REACTOR WAS CRITICAL 717.9 4,481.3 -84,008.6:

13. REACTOR RESERVE' SHUTDOWN'HOURt 0.0
0.0 '

O.0-n c.- 14,' HOURS GENERATOR btH.TNE 717.9 4,371.4 80,976.7-1 s' 15.* l'd!T RESERVE SHUT 00VN HOURS ' O.0 0.0 'O.0' 16, GROSS THERMAL' ENERGY GENERATED (MWH) 2,147,064 13,227.840. 238.524,033 17.' GROSS ELECTRICAL ENERGY GENERATED (HWH) 698,300 4,3S4,100 78,413,990 i < d' .18/ NET ELECTRICAL ENERGY. GENERATED (MWH) 669,556 4.'190,300 75.045,149 2 W-PAGE 1 0F 2 f L / i.- -j-a }

-h, OPERAT]NGDATAREPORT(CONTINUED) _-DOCKET N0'. 50 - 277 DATE SEPTEMBER 15. 1990 THl$ MONTH -

YR-TD-DATE CUMULATIVE

'19. UNIT SERVICE FACT 0k-96.5 '75.0 ~57.2

20. UNIT AVAILABILITY FACTOR-96.5; 75.0 57.2

--21. UNIT CAPACITY FACTOR (USING MDC NET)- 85.3-68.1 - 50.2 22.'UNITCAPACITYFACTOR(USINGDERNET) 84.5 67.5 49.7' 23, UNIT FORCED OUTAGE RATE 3.5 14.8 14.5 g

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH):

REFUEL, BEGINNING JANUARY 5, 1991. ENDING APRIL 5, 1991. 91 DAYS,

25. IF 5HUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:

SEPTEMBER 2. 1990

26. UNITS IN TL5T STATUS (PRIOR 10 COMMERCIAL OPERATION):

FORECAST' ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 ' COMMERCIAL OPERATION 07/05/74 PAGE 2 0F 2 m

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h[i-q.- y 39. " h..; i[ ' i OPERAT'ING DATA REPORT' DOCKET NO. 50 - 278 .0 ATE SEPTEMBER 15,' 1990 ' COMPLETED BY PHILADELPHIA ELECTRIC COMPANY'- ' N. Ji BARON' SUPERVISOR REPORTS GROUP- ,,G = PEACH BOTTOM ATOMIC POVER STATION TELEPHONE (717) 456-7014 EXT, 3321-OPERAT]NG STATUS y .1. UNIT NAME: PEACH BOTTOM UN]T 3 -- NOTES:

2. REPORTING PERIOD:

AUGUST, 1990 t 1

3. LICENSED.THERMALPOWER(MWT):

3293 o 4.NAMEPLATERATING(GROSSMWE): 1152 U 5.DESIGNELECTRICALRATING(NETMWE): 1065 9 g 6.MAXIMUMDEPENI,ABLECAPACITY(GROSSMWE):'1098 i+ '7..MAXIMUMDEPENDABIECAPACITY'(NETMWE)t.1035

8. IF CHANGES OCCUR IN CAPACITY RATINGS:(ITEMS NUMBER 3 THROUGH 7) SINCE L AST REPORT, GIVE. REASONS:

9,-POWER LEVEL TO VHICH RESTRICTED,'IF ANY (NET MWE): 10.' REASONS FOR' RESTRICTIONS,'IF ANY: l THIS MONTHL 'YR-TO-DATEL ' CUMULATIVE '11. HOURS:IN REPORTING PERIOD : 744 5,831 '.137,543 J =12T NUMBER OF HOURS REACTOR WAS CRITICAL -737.5-5.540.0-82,698.8 '^., 113.- REACTOR RESERVE SHUT 00WN HOURS-0.0. ! 0.0 - 0. 0 - 14, HOURS GENERATOR ON-LINE 697.9 5,427.4 -79,829.6 /. 15.' UNIT RECERVE SHUTDOWN HOUR $ 0.0 0,0. 0.0 16,'GROSSTHERMALENERGYGENERATED(MWH) 2,169,600 16,774,421 232,937,290 3 17.GROSSELECTRICALENERGYGENERATE0'(MWH). 69';,100 5,519,400 76,391,532 ll 18.~ NET ELECTRICAL ENERGY GENERATED (MWH) 666,178 5,328,312 73,170,880. t PAGE 1 0F 2 - -3 i 4 i 'k ] I W,. j 3/ i h, iQ j ~ 3 a l I N. 3 -l

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OPERATING DATA REPORT (CONTINUED).

1 -DOCKET NO. 50 - 278-s 2 Qh:, + + -DATE SEPTEMBER 15, 1990-- l f Y.Y /\\.,; 1His MONTH YR-TO-DATE CUMULATIVE 7 - 19J' UNIT SERVICE. FACTOR-93.8 '- - 93.1

- 56.0 J i

'20,. UNIT AVAILABILITY FACTOR: 93.8 93.1. 58.0

21. UNIT CAPACITY FACTOR (USING MDC NET) 86.5.

- 88.3: 151.4= --3 : ' m .22. UNIT CAPACITY FACTOR (USING DER NET) 84.1 85.8 50.0- ~ O 23.: UNIT' FORCED OUTAGE-. RATE 1 6.2 . 6.9 ^ 12.9: J24.SHLITDOWNSSCHEDULEDOVERNEXT6 MONTHS (TYPE,DATElANDDURATIONOFEACH): -MID-CYCLE MAINTENANCE OUTAGE STARTING OCTOBER 27, - SCHEDULED FOR 21 DAYS. p 25i-IF SHUTDOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP: 26, UN'ITS IN TEST STATUS (PRIOR TO. COMMERCIAL OPERATION): FORECAST . ACHIEVED. INITIAL CRITICALITY 08/07/74. 4 INITIAL ELECTRICITY 09/01/74 v,. 3 COMMERCIAL OFtRATION' -12/23/74 --4 3c e k, j !!i 1 ,_j r 1 i PAGE 2 0F'2 a v i; I 4 L i'

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y, s i g, ,,e a ,f u-. ~ AVERAGE DAILY UNIT POWER LEVEL x DOCKET No. 50 - 277-. UNIT PEACH BOTTOM UNIT 2 ' i - ~ '. DATE $[P' >BER 15. 1990 COMPANY PHILADELPHIA ELECTRIC COMPANY M."J. BARON $UPERVISOR . REPORTS GROUP PEACH BOTTOM AT0 Hic POWER STATIUN.-

ti TELEPHONE (717)456-7014 EXT,3321 MONTH AUGUST 1990

~ 'DAf AVERAGE DA!LY POWER LEVEL' DAY AVERAGE DAILY POWER LEVEL-(MWE-NET)- .(MWE-NET)- ~i -1033 17 1038 2~ 1039_ 18 1C13 - .3

1035

.19 1043-4 -1036 20 1037 5 1035 21 1038 6 ~1035-22 -910 7 1036 23 660 8-1040 24 -498- .9 1036 25 . 651 10 - M8 26 586 ' - 11 ' 1036 27-590 . 1, s 12 1045- ~ 28 -750 13 1035 29 '782 14 1017 30 701 15 1032 31. 0 16 1041 3.; '.; i - i m_ _._..__.___.____._.________._...m._._____

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s k DOCKET NO, 50 J 278.- '?! I b . UNIT PEACH BOTTOM UNIT 3-n 1, 0 ; DATE SEPTEMBER 15.L 1990: j u. y ..;-D, lCOMPANYPHILADELPHIAELECTRICCOMPANYi h -i j M g" / i M.-J. BARON ~ i f*. SUPERVISOR ii r h G(? ' ' REPORTS GROUP. = ?j p@%g f V, .c

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.l PEACH BOTTOM ATOMIC POWER STATION 6 = TELEPHONE (717)'456-7014 EXT.3321 ,-s z j f*) . _., AUGUST 1990 ; l 1 J MONTH l --1 n1 ;r .j lDAYe AVERAGE DAILY POWER LEVEL p,

(MWE-NE1 ) ---

DAY, AVERAGE DAILY POWER LEVELE ,? j s (MWE-NET) y Is 0: 17 9632

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11 ~ 3. g i. i t ^h i UNIT SHUTDOWNS AND POVER REDUCTIONS DOCKET NO.-S0 - 277 - UNIT NAME PEACH BOTTOM UNIT 2-DATE $EPTEMBER is 1990 1 I REPORT MONTH' AUGUST,-1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY - M. J. BARON e SUPERVISOR REPORTS GROUP ' PEACH BOTTOM ATOMIC POVER STATION M TELEPHONE (717) 456-7014 EXT. 3321 METHOD OF . LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE CODE ACTION TO NO. DATE' (1) (HOURS) (2) REACTOR (3) REPORT # (4) (5): PREVENT RECURRENCE ' ll-900822' F. ' 0.0 H 4 N/A HH PUMPXX. CONDENSATE PUMP MAINTENANCE. CIRCULATION PUMP MAINTENANCE. .e y C0hfROL ROD ADJUSTMENT. i. REACTOR WAS NOT SHUT DOWN. '12 900823 F ' O.0 H~ 4 N/A CD VALVEX-MSIV 86B REPAIR. '13 900826 !F 0.0 ,H' 4 N/A CB PUMPXX "A" REClRC PUMP REPA!R. -'14 900827 F 0.0 H 4 N/A CB PUMPXX:. "A" RECIRC PUMP REPAIRJ '15. 900830 'F 26.1 A ~ 2' 2-90-21. 10 ~ INSTRU' REACTOR LEVEL INSTRUMENTATION .THAT USES 2B REFERENCE LEG DETERMINED TO BE INOP. NOTE: LER WAS IN REFERENCE T0 INADVERTENT SAFETY SYSTEM ACTUATION' i DURING INSERTION OF THE MANUAL SCRAM: GROUP ll/lil-ISOLAT!ONS. ' 26.1 ' ,. (1) (2) (3)- (4) 4 ' F - FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S.,5CHEDULED = 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 (S) G-OPERATIONAL' ERROR (EXPLAIN) H - OTHER(EXPLAIN) EXHIBIT I - SAME SOURCE

1.- ' 9.j (1 . UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 - 27B' UNIT NAME PEACH BOTTOM UNIT 3 - i DATE SEPTEMBER 15; 1990 COMPLETEDBYbl5ADELPHIAELECTRICCOMPANY- . REPORT MONTH AUGUST. 1990-M. J.' BARON- ' SUPERVISOR REPORTS GROUP" PEACH BOTTOM ATOMIC POWER STATION TELEPHONE (717) 4$6-7014 EXT. 3321 - METHOD OF : LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE-TYPE DURAtl)N REASON SHUTTING DOWN . EVENT CODE CODE ACTION TD- -' NO. .DATE (1) (HOURI) (2)- REACTOR (3) . REPORT # (4) (5) - PREVENT RECURRENCE 10 900801 F 46.1 A: 2 .3-90-08 HH HTEXCH CONDENSER LOW VACUUM. REACTOR MANUALLY SCRAMED. 11 900807 5 0.0 H i4 N/A RB CONROD'- .TO' SET FULL' POWER ROD PATTERN. - 12 -900811 F 0.0 H 4 N/A CH. PUMPXX' C RFP HIGH VIBRATION READING-DUE TO A BROKEN PROBE. 13 900817 'F "0.0-H 4 N/A HC HTEXCH VATERBOX INSPECTION. ~ s .h -46.1 y '(1)' .(2) (3) (4) -v F'- FORCED:.. -A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA' REASON. METHOD . EXHIBIT G - INSTRUCTIONS 4' 'S - SCHEDULED-- B - MAINTENANCE OR TEST ' 2 - MANUAL SCRAM. ENTRY SHEETS FOR LICENSEE-C - REFUELING... 3 - AUTOMATIC SCRAM. EVENT REPORT (LER), - j*=. ' D.- REGULATORY RESTRICTION 4-OTHER(EXPLAIN) FILE-(NUREG-0161). E'- OPERATOR TRAINING + LICENSE EXAMINATION 'F - ADMINISTRATIVE (5) G OPERATIONAL-ERROR (EXPLAIN). ~H - OTHER(EAPLAIN) EXHISIT I - SAME SOURCE al. -3.. .}}