ML20203F420
| ML20203F420 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/31/1986 |
| From: | Alden W, Logue R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8604250153 | |
| Download: ML20203F420 (16) | |
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- Dockst Nom. 50-277/50-278 t Attachment to Monthly Operating Report for Ma r ch , 1986 Page 1 Peach Bottom Atomic Power Station Narrative Summary of Operating Experience March, 1986 .
UNIT 2 Unit 2 began the report period operating at a reduced powerThe level of 900 MWe to accommodate control rod pattern adjustment.
unit was returned to full power on March 1. .
load was reduced to 700 MWe for the inspection and On March 4, The unit returned to full power repair of condenser tube leaks.
on March 5.
g On March 16, load was reducedcaused to 200 by MWe due clogging debris to the loss theofouter 4 condenser circulating water,The unit was manually scrammed on intake structure screens.
March 17 after Circulating water unsuccessful efforts and was reestablished to clear the screens.
the reactor was started on March 19. The turbine-generator was synchronized to the bus 2 later the same day. Full power was achieved on March 21.
On March 21, load was reduced to 660 MWe for control rod pattern Load recovery began on March 23. A load reduction adjustment.to 700 MWe was taken again on March 25 to perform condenser tube leak inspections. Leaks were discovered in the A2 and B1 water boxes. Repairs were made and the unit was returned to full power on March 26.
Unit 2 ended the report period operating at 100% power.
Unit 3 Unit 3 began the report period in the processThe of starting reactor was upat held j following its sixth refueling outage.
t 300 degrees F and 60 psig to repair the High Pressure Coolant (MO-5244-
] Injection (HPCI) system turbine exhaust vacuum breaker A) valve, and to leak check condenser tubes.
-! The 150 psig reactor pressure startup test was conducted on March Pressure was then increased to 500 psig for continued 4-5.
startup testing.
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Attachment to Monthly l
Operating Report for March, 1986 Page 2 i
Main On March 6, the reactor scrammed due to low water level.
condenser vacuum was decreasing because of maintenance beingIn an performed on the 'C' condensate pump drive packing gland.
attempt to increase vacuum, the steam jet air ejector (SJAE) was placed into service; however, vacuumthe continued to decrease. To avoid a reactor scram on low vacuum, operator lowered the electrohydraulic control (EHC) pressure setpoint to open two turbine bypass valves, to reduce pressure below the 600 psig low vacuum scram bypass setpoint. As pressure decreased, To avoid a wa te r a turbine
" swell" occurred causing level to increase.
trip, the operator partially closed a bypass valve and reduced t
reactor feedwater pump turbine (RFPT) speed to stabilize level.
Because of a RFPT speed control alignment problem, feedwater flow decreased to zero. The operator attempted to increase the flow, but the increase was not fast enough to avoid the low level reactor scram.
Level was restored, and startup was resumed on March 7.
On March 9, reactor pressure was reduced to 570 psig for turbine warmup. On March 10, the turbine tripped due to bearing low oil pressure. Investigation revealed that two of three pressure switches for the shaft driven oil pump discharge pressure too low, were causing set too high and the 1300 rpm bypass switch set the turbine trip. The two pressure switches were recalibrated, the bypass switch was reset, and the turbine was placed on line March 12.
due to high The unit operated below 25% power until March 14, reactor water conductivity. Condenser tube leak repairs were made and reactor power was increased to perform the 30% reactor power portion of the startup test program.
On March 16, the unit was shutdown due to the loss of condenser circulating water, caused by debris clogging the outer intake structure screens.
Circulating water was reestablished and reactor was started on March 17.
On March 18, the reactor was manually scrammed from 5% power The when two control rods were found withdrawn out of sequence.
l reactor was restarted the same day, and the turbine-generator was ii synchronized on March 20.
Power ascension continued until March 25, when it waswhich halted at j
940 MWe due to increased reactor water conductivity, was
'F' condensate caused by a resin injection while placing the filter domineralizer into service.
set On March 27, th e ' B ' recirculation pump motor-generator (M-G) tripped due.to a ground fault in one of three pump motor leads L
Attachment to Monthly Operating Report for March, 1986 Page 3 outside the drywell. The unit was limited to single-loop while the problem was operation-with investigated.
load reduced to 32%,Since the two remaining pump motor leads are sufficient to carry the electrical load, it has been determi_ted that the cable can be replaced during a later outage.
Unit 3 er 'ad the report period in power ascension from 300 MWe after the restoration of the 3B recirculation pump M-G set to service.
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Docket No. 50-277
.[ Attcchment to Monthly Operating Report for March, 1986 REFUELING _INFORMATION
- 1. Name of_ facility:
Peach Bottom Unit 2
- 2. Scheduled'date for next refueling shutdown:
January 31, 1987
- 3. Scheduled date for restart following refueling:
May 1, 1987
- 4. Will- refueling or resumption of operation thereaf ter require a ,
technical specification change or other license amendment?
Yes' If answer is yes, what, in general, will these be? ,
Technical Specifications to accommodate reload fuel.
Modifications to reactor core operating limits.
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
Reload 7 license amendment to be submitted December 12, 1986.
(
- 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
None expected.
- 7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1462 Fuel Assemblies, 58 Fuel Rods
- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been l
requested or is planned, in number of fuel assemblies:
l The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblies. Replacement higher density fuel racks l
were approved by the NRC on February 19, 1986 which increases the licensed fuel pool capacity to a total of 3819 l.
fuel bundles in each fuel pool. This modification is scheduled for completion by January 31, 1987.
l Docket No. 50-277 Atttchment to Monthly Operating Report for March, 1986 Page 2 REFUELING INFORMATION (Continued)
- 9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity, prior to the completion of the new fuel racks installation:
March, 1992 (February, 1987, with reserve full core discharge)
- 10. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, subsequent to the completion of the new fuel racks installation:
March, 1995 (March, 1998, with reserve full core discharge)
, Docket No. 50-278 Attachment to Monthly Operating Report for March, 1986 REFUELING INFORMATION
- 1. Name of facility:
Peach Bottom Unit 3 !
- 2. Scheduled date for next refueling shutdown: I May 16, 1987
- 3. Scheduled date for restart following refueling:
May 14, 1988
- 4. Will refueling or resumption of operation thereaf ter require a technical specification change or other license amendment?
Yes.
If answer is yes, what, in general, will these be?
Technical Specifications to accommodate reload fuel.
Modifications to reactor core operating limits.
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information:
Reload 7 License Amendment to be submitted January 7, 1988
- 6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures None expected.
- 7. The number of fuel assemblies (a) in the core and (b) in the I spent fuel storage pools (a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1496 Fuel Assemblies, 6 Fuel Rods i
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Docket No. 50-278 F :. .
Attcchment to Monthly Operating .
Report for March, 1986 Page 2 REFUELING INFORMATION (Continued)
- 8. The present' licensed spent fuel pool storage capacity and the size of any increase in licensed storage 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. Replacement higher density fuel racks
- were approved by the NRC on February 19, 1986 which increases the licensed fuel pool capacity to a total of 3819 fuel bundles in each fuel pool. This modification will be implemented following completion of a similar change for Unit 2.
- 9. The projected date of the last refueling that .can be discharged to the spent fuel pool assuming the present capacity, prior to the completion of the new fuel racks installation:
March, 1993 (September, 1987, with reserve full j core discharge) ,
- 10. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, subsequent to the completion of the new fuel racks installation:
March, 1999 ( Ma rch , 1996, with reserve full i core discharge) i f
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.' ' AVERAGE DAILY WIT POWE2 LEVEL DOCKET NO. 50 - 277 WIT PEACH BOTTOM WIT 2 DATE APRIL 15.1906 COMPANY PHILADELPHIA ELECTRIC COMPANY l .. ................... ....
W.M.ALDEN ENGINEER-1H-CHARGE -
LICENSING SECTION
! NUCLEAR GENERATIDH DIVISION TELEPHONE (2151841-5022 MONTH MARCH 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
( MWE-NET ) (MWE-NETI l
1 960 17 51
't 1073 18 0 3 1872 19 14 l
4 1030 20 409 i
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5 746 21 847 6 1955 22 989 -
7 1978 23 973 8 1062 24 1975 9 1072 25 1015 le 1971 26 958 11 1973 27 1074 ,
12 1980 to 1972 i
13 1978 29 1978 14 1978 30 1876 15 1981 31 1978 16 709 i
. AVERAGE DAILY WIT POWER LEVEL DOCKET M). 50 - 278 WIT PEACH 80TTOM UNIT 3 Ot.TE AMIIL 15.1986 COMPANY PHILADELPHIA ELECTRIC COMPANY -
W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTIDH P0JCLEAR GENERATION DIVISION g TELEPHONZ t215) 841-5022 MONTN MARCH 1966
. DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL t FedE-NET I IPWE-NETI i
1 0 17 0 2 0 18 0 3 0 19 0 0 0- to 175 5 0 21 171 6 0 22 401 7 0 23 616 8 0 26 . 781 9 0 25 922 10 0 26 930 11 0 27 460 It 139 to 303 13 163 29 301 14 219 30 277 15 200 31 344 a l'a 169
. - - - - ,-- ,nn,---. - - , . , - - . , , , . - . - , . , - . - - - - . - . , - , , . _ . - - . , - , - - - . . . - , - . . -----,e-. - - - - , - - - - -, --- . - - - - - - - - - -- , *
. OPERATING OATA REPORT l
DOCKET No. 50 - 277 DATE APRIL 15,1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN -
ENGINEER.IN-CHARGE I7 CENSING SECTION N 4 LEAR GENEkATIDH OIVISIDH TELEPHONE (215) 8415022 OPERATING STATUS
- 1. UNIT NAMER PEACH ROTTOM UNIT 2 l NOTESt UNIT 2 EXPERIENCED ONE MANUAL l
............................... . l l
- 2. REPORTING PERIDO MARCH. 1986 l SCRAM. THREE SCHEDULED LDAD l
........................... l l
- 3. LICENSED THERMAL POWERiftiTit 3293 l REDUCTIONS Ate TWO FORCED l
..... ........ l l
- 4. NAMEPLATE RATING (GROSS PG4Elt 1152 l LOAD REDUCTIONS. l
............... l l
- 5. DESIGN ELECTRICAL RATING (HET PG4 Elf 1065 l l l l
- 6. MAXIMLM DEPDCABLE CAPACITY (GROSS feetil 1998 l l
.... l l
- 7. MAXIMLM DEPE> CABLE CAPACITY INET tt4Elt 1051 l l
- 8. IF CHANGES OCCUR IN CAPACITY DATINGS (ITEMS NLMBER 3 THROUGH 71 SINCE LAST REPORT, GIVE REASONSt
- 9. POWER LEVEL TO MtICH RESTRICTED. IF ANY INET pliElt
- 10. REASONS FOR RESTRICTIONS IF ANTt THIS MONTH YR.TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 2,160 102.912
- 12. PRRSER OF HOURS REACTOR WAS CRITICAL 699.4 1,685.1 66.879.3
- 13. REACTOR RESERVE SHLITD0lel HOURS 0.0 0.0 0.0
- 13. HOLRS GENERATOR CH-LINE 684.7 1.629.5 64.758.3
- 15. IMIT RESERVE SHUTD06#4 HOLNIS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (Ptoll 2.087.870 4,758,182 191,024.697
- 17. OROSS ELECTRICAL ENERGY GENERATED (tteil 693.030 1.562,180 62.775.140 18, NET ELECTRICAL ENERGY GENERATED (ft#O 672.426 1.509.493 60.101,788
- 19. LMIT SERVICE FACTOR 92.0 75.4 62.9
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+' 20. tR4IT AVAILABILI1'Y FACTOR 92.0 75.4 62.9 I l
- 21. tR41T CAPACITY FACTOR (USING W C NET) 66.0 66.5 55.6
- 22. UNIT CAPACITY FACTOR (USING DER NET) 64.9 65.6 54.8
- 23. UNIT FORCED OUTAGE RATE 8.0 20.1 13.2
- 24. SHUTDOW45 SCHEDULE 0 OVER NEXT 6 MONTHS ITYPE DATE. AW DURATION OF EACHit i
- 25. IF SHUTD0let AT Etm 0F REPORT PERIDO ESTIMATED DATE OF STARTUPt d
- 26. UNITS IN TEST STATUS (PRIOR TO COPMERCIAL OPERATION)* FORECAST ACHIEVE 0 INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 ComtRCIAL OPERATION 07/05/74 e
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OPE ~ATING DATA REPORT DOCKET No. 50 - 278 DATE APRIL 15.1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTIDH NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 OPERATING STATUS
- 1. UNIT NAMEt PEACH BOTTOM UNIT 3 l HOTES UNIT 3 STARTED UP l
.. ....... ....... ..... .. l l
- 2. REPORTING PERICOI MARCH 1986 l FOLLOWING OUTAGE FOR I
- 3. LICENSED THERMAL POWERitSITit 3293 l MAINTENANCE Ate REFUEL. l l
C. HAMEPLATE RATING (GROSS PSiElt 1152 l THEN EXPERIENCED ONE MANUAL l
.... ......... i 1
- 5. DESION ELECTRICAL RATING INET MWElt 1965 l SCRAM. Ate ONE F0#CED LOAO l
......... l l
- 6. MAXIMUM DEPEPEA8LE CAPACITY (GROSS MWEli 1998 l REDUCTION. l l l
- 7. MAXItut nEPEteABLE CAPACITT INET PedElt 1035 l l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORTe GIVE REASONS *
- 9. POWER LEVEL TO letICH RESTRICTED IF ANY INET PedElf
- 10. REASONS FOR RESTRICTIONS. IF ANYI i
THIS MONTH YR-TO-DATE CLMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 2,160 98.808
- 12. PU WER OF HOURS REACTOR WAS CRITICAL 621.8 621.8 69.235.0
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 1$. H0tRS SENERATOR ON-LINE 394.6 394.6 67.249.0
- 15. LMIT RESERVE SHUTD0bH HOURS 0.0 0.0 0.0
- 13. SROSS THERMAL ENERGY SENERATED (PeM) 592.829 592.829 195.589.493
- 17. GROSS ELECTRICAL ENERGY GENERATED (PGM) 165.230 165.230 64.158.900
- 18. HET ELECTRICAL ENERGT GENERATED (PSet) 155.032 145.548 61.538.289
- 17. IMIT SERVICE FACTOR 53.0 18.3 68.1
.[ 20. 124IT AVAI'LABILITT FACTOR 53.0 18.3 68.1 E1. UNIT CAPACITT FACTOR (USING f9C NET) 20.1 6.5 60.2
- 22. WIT CAPACITT F ACTOR (USING DER NETI 19.6 6.3 58.5
- 23. WIT FORCED OUTAGE RATE 17.3 17.3 7.2 "24. SHUTDOWHS SCHEDULED OVER NEXT 4 MONTHS ETYPE DATE. AND DURATION OF EACHit
- 25. IF SHUTDon#4 AT Ele OF REPORT PERIDO ESTIMATED DATE OF STARTUPI
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATIONlt FORECAST ACHIEVED INITIAL CRITICALITT 08/07 4
....__./.7 INITIAL ELECTRICITT 09
......... .../.01/.74 COMMERCIAL OPERATION 12
......... .../.23 /.74 l
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l UNIT SHUTDo m S Ate POWER REDUCTIONS DOCKET HO. 50 - 277 LHIT HANE PEACH BOTTON UNIT 2 DATE APRIL 15.1986 REPORT MONTH MARCH. 1986 COMPLETED BT PHILADELPHIA ELECTRIC COMPANY W.H. ALDEN ENGINEER-IN-CHARGE LICERSING SECTIDH HUCLEAR GENERATI0H DIVISICH TELEPHONE (2151841-5022 l l l l l NETHOD OF l LICENSEE ISYSTENICOMPONENTI CAUSE AHO CORRECTIVE I lTTPElDURATIOHIREASOHISHUTTING DOWHI EVENT l CODE I CODE I ACTION TO 0.1 UATE I (111 (HOURSil (2) l REACTOR 831 1 REPORT 8 l t4l I (5) l PREVENT RECURRENCE 1 1 1 1 I I I I I 1 l F40301 i Sl 0.0 i H l 4 l H/A l RC l COHROD l LOAD REDUCTION TO 760MW FOR CONTROL ROD l l 1 l l l l l l PATTERN ADJUSTHENT.
I I i 1 1 I i 1 I
.2 l 860304 i Sl 0.0 l A I 4 l N/A l HF l HTEXCH l LOAD REDUCTION TO 74EHW FOR WATERBOX l l 1 l l l l l l IHSPECTIDH.
I i 1 1 1 I I I I 3 I 860316 l Fl 0.0 l A1 4 l N/A I HF l FILTER I LOAD REDUCTIDH TO 200 MW DUE TO LOSS OF l l l l l l l l l CIRCULATING WATER CAUSED BY LEAVES AHD DEBRIS l l l l l l l l l CLOGGIHG DUTER IHTAKE STRUCTURE SCREENS.
I I I I I I I I I L4 1 660317 l Fl 59.3 l A I 2 l H/A l HF l FILTER I SHUTDOWN DUE TO LOSS OF CIRCULATItG WATER l l l 1 l l l l l CAU$[D BY LEAVES AND DEBRIS CLOGGING OUTER I l l l l l l l l INTAKE STRUCTURE SCREENS.
I i 1 1 I I I l I L5 l 660323 1 S1 0.0 l H l 4 I N/A l RC l CONR00 l LOAD REDUCTIDH TO 650 MW FOR COHTROL R00 l l l l l l l l l PATTERN ADJUSTMENT.
I I I I I I I I I
L6 l 66032) l Fl 0.0 l A I 4 l N/A I HF l HTEXCH I LOAD REDUCTIDH TO 700MW TO REPAIR CONDENSER I I I l 1 l l l l TUBE LEAKS IN A2 AND B1 WATERP0XES.
l l .-.-- 1 I I I I I I
l l l 59.3 l l l l l l (1) (t) (3) (4)
METH00 EXHIBIT G IHSTRUCTIDHS F - FORCED REASON 1 - MANUAL FOR PREPARATION OF DATA 5 . SCHEDULED A - EQUIPMENT FAILURE (EXPLA!HI . . _
5 - MAINTENANCE OR TEST 2 - MAtAJAL SCRAM. ENTRY SHEETS FOR LICENSEf.
C . REFUELING 3 - AUTOMATIC SCRAN. EVENT REPORT ILERI O - REGULATORT RESTRICTIDH 4 - OTHER (EXPLAINI FILE (HUREG-0161)
E . OPERATOR TRAINING + LICENSE EXAMINATION F - ADNIHIST"ATIVE (5)
G - OPERATIDHAL ERROR IEXPLAINI u _ nturarrvatatut FYHYnff f m SAMr SOURCE
e e.
LR4IT SNUTD0l#45 Ate POWER REDUCTIONS DOCKET NO. 50 - 276 '
UNIT NAME PEACN BOTTOM UNIT 3 3
DATE APRIL 15.1966 l REPORT MONTH MARCH. 1966 COMPLETED BT PHILADELPNIA ELECTRIC COMPANT W.M.ALDEN ENGINEER.IN-CNARGE LICENSING SECTION MJCLEAR GENERATION OIVISION TELEPHONE 1215) 841-5022
- e. .... .. ....... .... ....... ........... ..................................................................
l l l l l METHOD OF l LICENSEE ISTSTEMICOMPONENTl CAUSE Ate CORRECTIVE l lTTPElDURATIONINEASONISNUTTINC 006641 EVENT l CODE l CODE I ACTION TO I DATE l (111 (HOURSil (2) l REACTOR 433 l REPORT 8 l 141 l (5) l PREVENT RECURRENCE 1 I I I I I I I I
)l860301i S l 267.1 l C l 4 l N/A l RC l FUELXX l SNUTD0644 FOR SIXTN REFUELING Ate MAINTENANCE
'l l l l 1 l l l l DUTAGE.
I I I I I I I I I
) 1 860316 i Fl 82.3 l A l 2 l M/A l HF l FILTER l SNUT006et DUE TO 1055 0F CIRCULATING WATER I l l l l l l l l CAUSED ST LEAVES AND DEBRIS CLOGGING OUTER l l l l l l l l l INTAKE STRUCTURE SCREENS.
I I I I I I I I I
)I660327l Fl 0.0 l A l 4 l N/A I CB l ELECON l LOAD REDUCTIDN TO 374MW FOR SINGLE LD0P l I l l l l l l l UPERATION INEG.5) IN ACCopDANCE WITH T.S. 3.6.5 l l l l l l l l 1 DUE TO RECIRCLLATION PUMP M-G SET TRIP CAUSED l l l l 1 l l l l BT A CABLE FAILURE.
I I I -.--- 1 I i 1 1 1 1 I I 549.4 I I i 1 I I (Il III (3) (4)
- FORCED REASON METHOD EXHIBIT G = INSTRUCTIONS
- SCHEDULED A - EQUIPMENT FAILURE (EXPLAINI I . MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 . MANUAL SCRAM. EN1RT SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LERI D - REGULATORT RESTRICTION 4 - OTHER (EXPLAINI FILE (NUREG-0161)
E - OPERATOR TRAINING
- LICENSE EXAMINATION F - AOMINISTRATIVE 15) 8 - OPERATIONAL ERROR (EXPLAINI N - OTHERIEXPLAINI EXHIBIT I - SAME SOURCE
4 PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101 April 15, 1986 (2151841-4000 Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement US Nuclear Regulatory Commission Washington, DC 20555 Attention: Document Control Desk
SUBJECT:
Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen Attached are twelve copies of the monthly operating report for Peach Bottom Units 2 and 3 for the month of March, 1986 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
Very trul yours,
,,..o R. H. Logue Supe rintendent Nuclear Services Attachment cc Dr. T. E. Murley, NRC Mr. T. P. Johnson, Resident Inspector Mr. Stan P. Mangi, Dept. of Envir. Resources Mr. P. A. Ross, NRC~(2 copies)
Mr. Thomas Magette, Maryland Power Plant Siting INPO~ Records Center r6Li (II