ML20137P418
ML20137P418 | |
Person / Time | |
---|---|
Site: | Peach Bottom |
Issue date: | 08/31/1985 |
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 8509190639 | |
Download: ML20137P418 (14) | |
Text
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OPERATING DATA REPORT l
DOCKET No. 50 - 277 DATE SEPTENBER 13 1985 t
CONPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-HUCLEAR TELEPHONE (2153 841 50ER 4
OPERATING STATUS
- 1. tA4IT HAMER PEACH BOTTOM UNIT 2 l NOTES: UNIT 2 INCURRED TWO l
.. ......... ........... l l
- 2. REPORTING PERIODI AUGUSTe 1985 l SCHEDULED LOAD REDUCTIONS, l I i
- 3. LICENSED THERMAL POWER (ItiTit 3293 l THREE FORCED LDAD l i
! 4. HAMEPLATE RATING (GROSS telElt 1152 l REDUCTIONS TWO MANUAL l t
- 5. DESIGN ELECTRICAL RATING (HET telEll 1065 l SHUTDOW4Se AMI FIVE AUTO. l
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- 6. MAXIMLRt DEPEM3ABLE CAPACITY (GROSS IteE18 1998 l SCRAMS. l 4 ....
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- 7. MAXIMLRt DEPEM3ABLE CAPACITY (HET F54El* 1951 l l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NureER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS 8 t
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- 9. POWER LEVEL To letICH RESTRICTED, IF ANY (HET IS4Elt
- 10. REASONS FOR RESTRICTIONSe IF ANY THIS MONTH YR-TO-DATE CtN1ULATIVE w
- 11. HOURS IN REPORTING PERIOD 744 5,831 97.823
- 12. MJMBER OF HOURS REACTOR WAS CRITICAL 4%.9 1.031.3 63.314.9
- 13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR CH-LINE 451.6 775.7 61.332.3
- 15. UNIT RESERVE SHUTD0684 HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (ftell 1.300.920 2,076.144 180.4% e145
- 17. GROSS ELECTRICAL ENERGY GENERATED (fleil 404.380 618.530 59.337,190
- 18. HET ELECTRICAL ENERGY GENERATED (Ptail 386.919 532.699 56,795.037
- 19. UNIT SERVICE FACTOR 6
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- 20. UNIT AVAILABILITT FACTOR 60.7 13.3 62.7 '
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- 21. UNIT CAPACITT FACTOR (USING f10C HET) 49.5 8.7 55.2 l
- 22. (MIT CAPACITY FACTOR (USING DER HET) 48.8 8.6 54.5
- 23. UNIT FORCID OUTAGE RATE 39.3 27.4 12.7 2*e. SHUTD06elS SCHEDULED OVER NEXT 6 MONTHS ITYPEe DATE. AHO DURATIDH OF EACHis
- 25. IF SHUTD06M AT Em DF REPORT PERIOD ESTIMATED DATE OF STARTUP8
- 26. UNITS IN TEST STATUS (PRIOR TO CONMERCIAL OPERATIDHit FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY Cott1ERCIAL OPERATIDH 1
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I OPERATING DATA REPORT DOCKET No. 50 - 278 .
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+ ' i DATE SEPTEMBER 13.1985/., ','[j ; [> >, , . ) -
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W.M.ALDEN ENGINEER-IN-CHARGE
. LICENSING SECTION l GENERATIDH DIVISION-NUCLEAR TELEPHDHE (215) 641-5022 OPERATING STATUS
- 1. UNIT HAME8 PEACH BOTTOM UNIT 3 i NOTES: UNIT 3 CONTINUE 0 ITS SIXTH l
.. . . ...... ................ l l
- 2. REPORTING PERIOD AUGUST, 1985 l REFUELING ADS MAINTENANCE l l l
- 3. LICENSED THERMAL POWER (MWT): 3293 1 OUTAGE. l
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- 4. NAMEPLATE RATING (GROSS MWE)* 1152 l l
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- 5. DESIGN ELECTRICAL RATING (HET MWElt 1065 l l I i
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWEss 1098 l l
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- 7. MAXIMUM DEPENDA8LE CAPACITY (HET MWEli 1035 l I
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUleER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONSI
- 9. POWER LEVEL TO letICH RESTRICTEDs IF ANY (HET 694Els
- 10. REASONS FOR RESTRICTIONS IF ANY8 THIS MONTH YR-TO-DATE , CUMULATIVE
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- 11. HOURS IN REPORTING PERIOD ,
744 5.831 93,719
- 12. HUMBER OF HOURS REACTOR WAS CRITICAL 0 4:055.7 68.613.E ,
- 13. REACTOR RESERVE SNUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR OH-LINE 0.0 3,989.3 66.454.4
- 15. IMIT RESERVE SHUTD06M HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWN) 0 10.796.856 194.996.664
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWN) 0 3.466,130 63,993.670
- 18. NET ELECTRICAL ENERGY GENERATED (MMN) # -8.113 3,312,728 61.422:030
- 19. UNIT SERVICE FACTOR 0.0 68.4 71.3
- 10. UNIT AVAILABILITY FACTOR 0.0 68.4 71.3
- 21. UNIT CAPACITY FACTOR (USIHG NOC HET) 0.0 54.9 63.3
- 22. UNIT CAPACITY FACTOR (USING DER HET) 0.0 53.3 61.5
- 23. UNIT FORCED OUTAGE RATE 0.0 0.8 7.1
- 24. SHUTDOWHS SCHEDULED OVER HEXT 6 NOHTHS (TTPEe DATE AND DURATION OF EACH38 SCHEDULED SHUTDOWH FOR REFUELING AM MAINTENANCE OUTAGE, STARTED 7/14/85
- 25. IF SHUTDO W AT Em 0F REPORT PERIODe ESTIMATED DATE OF STARTUP8 12/I/85
- 26. UNITS IN TEST STATUS (PRIOR TO CotetERCIAL OPERATIDHit FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY Cott1ERCIAL OPERATIDH e - HEGATIVE VALUE REPORTED FOR CONSISTENCY WITH FEDERAL ENERGY REGULATORY COPMISSIGH REPORTS.
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. UNIT NAME PEAOl DOTTOM (A6IT t DATE SEPTErste 13.19e5 REPORT MONTH AUGUST. 19e5 COMPLETED ST PHILADELPHIA ELECTRIC COMPANY N.M.4LDEN ENGINEER IN-CHARGE LICENSING SECT 10N SIMRATION O!VIS10N-64JCLEAR TELEPHONE 18153 841-Sett * *
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- LICENSE EXAMINATION F - ADMINISTRATIVE 151 8 = OPERATIONAL ERROR IEXPLAINI
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I UNIT SHUTDOWHS AND POWER REDUCTICHS DOCKET NO. 50 - 277 UNIT HAME PEACH BOTTOM UNIT 2 DATE SEPTENBER 13,1985 REPORT MONTH AUGUSTe 1985 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.H.ALDEN ENGINEER-IN-CHARGE LICENSING SECTIDH GENERATI0H DIVISIGH-HUCLEAR TELEPHONE (215) 841-5022 l l l l l METHOD OF l LICENSEE ISYSTEMICOMP0HENTI CAUSE A}c CORRECTIVE l lTTPElDURATIOHlREASOHlSHUTTING DOWHI EVENT l CODE l CODE l ACTION TO No.1 DATE I (lli (HOURSil (2) l REACTOR (3) l REPORT S l (4) l (5) l PREVENi RECURRDCE I I I I I I I I i 15 1 850826 l F l 026.5 l A I 3 l 2-85-16 l CB l INSTRU l FALSE LOW-LEVEL WILE VALVING PT 53 B BLOCK l l l l l 1 l l l VALVE PUT IN SERVIch FOLLOWING MAINTENANCE.
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(1) (2) (3) (4) l F - FORCED REASCH METHOD EXHIBIT G . IHSTRUCTIONS
- l. 5 - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIH) 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) l l- D - RECULATORY RESTRICTIOH 4 - OTHER (EXPLAIH) FILE (HUREG-0161)
- l. E - CPERATOR TRAINING + LICENSE EXAMINATIDH
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G - CPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIH) EXHIBIT I - SAME SOURCE a
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LAIIT SHUTDOWHS AM) POWER REDUCTIDHS DOCKET NO. 50 178 UNIT HAME PEACH BOTTOM UNIT 3 ,
DATE SEPTEMBER 13.1985 REPORT MONTH AUGUST, 1985 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY
- H.M. A LDEN ENGINEER-IN-CHARGE LICEHSING SECTIDH GENERATI0H OIVISIDH-HUCLEAR TELEPHONE (215) 841-50Et l l l l l METHOD OF l LICENSEE ISYSTEMICOMPONENTl CAUSE AM) CORRECTIVE I ITTPElDURATIONIREASONISHUTTING DOWl EVENT l CODE I CODE 1 ACTION TO
@.l DATE I (1)l (HOURS)l (2) l REACTOR (3) l REPORT 8 l (4) l (5) l PREVENT HECURRENCE L... _. ... ... ...... ..... ........................._........... . .. .....-. ........ ....
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>3 I C50801 1 S l 744.0 l C l 1 i H/A I RC l REF'JEL i SHUTDO W FOR SIXTH REFUELING / MAINTENANCE OUTAGE' l I I ---- 1 I i i i I I I I 744.0 I l l l l l s
(1) (2) (3) (4)
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- EXHIBIT G - INSTRUCTIDHS
- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIH) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 . MANUAL SCRAM. ENTRT SHEETS FOR LICENSEE C . RETUELING 3 - AUTOMATIC SCRAM. EVENT REPORT (LER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN) FILE (MJREG-0161)
E - CPERATOR TRAINING + LICENSE EXAMINATIDH F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIH)
H - OTHER(EXPLAIH) EXHIBIT I . SAME SOURCE a
AVERAGE DAILY UNIT POWER LEVEL ,
DOCKET No. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE SEPTEMBER 13.1945 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH AUGUST 1965 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (te4E-NET 3 (MWE-NETI 1 904 17 843 2 1003 18 953 3 579 19 930 4 837 to 0 5 911 21 0 6 0 22 0 7 0 23 0 8 544 24 0 9 909 ., 25 0 10 806 26 0 11 902 27 573 It 905 to 931 13 0 29 822 1% 0 30 915 15 104 31 1933 16 819 I
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4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTON UNIT 3 DATE SEPTEMBER 13.1985 COMPANY PHILADELPHIA ELECTRIC COMPANY W.H.ALDEN ENGINEER-IN-CHARGE LICENSING SECTION GENERATI0H DIVISION-HUCLEAR TELEPHONE (2153 841-5022 MONTH AUGUST 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL it#4E-NETI (MWE-NETI 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 0 5 0 21 0
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I Dockst No. 50-278
- Attcchmsnt to Monthly Operating Report for August, 1985 REFUELING INFORMATION
- 1. Name of facility:
Peach Bottom Unit 3
- 2. Scheduled date for next refueling shutdown:
July 14, 1985
- 3. Scheduled date for restart following refueling:
December 1, 1985
- 4. Will refueling or resumption of operation thereafter 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:
MAPLHGR Limits Submitted January 7, 1985 Additional Core Limit Information - April 12, 1985
- 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 i fuel stordge pool:
(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1212 Fuel Assemblies, 6 Fuel Rods
- 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 2816 fuel assemblies. A request to increase fuel pool storage capacity was submitted to the NRC on Augunt 1.
i 9. The projected date of the last refueling that can be discharged to the spent fuel. pool. assuming the present licensed capacity.
l March, 1992 (January, 1987 with reserve for full core discharge)
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- - Dockot No. 50-277 Attcchtsnt to Monthly Operating Report for August, 1985 REFUELING INFORMATION
- 1. .Name of facility:
Peach Bottom Unit 2
- 2. Scheduled date for next refueling shutdown:
October 11, 1986
- 3. Scheduled date for restart following refueling:
December 27, 1986
- 4. Will refueling or resumption of operation thereafter 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 September 26, 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 numben of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1464 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 requested or is planned, in number of fuel assemblies:
The spent fuel pool storage capacity has been relicensed for 2816 fuel assemblies. A request to increase fuel pool i storage capacity was submitted to the NRC on August 1. j i 9. The projected date of the last refueling that can be discharged to I the spent fuel pool assuming the present licensed capacity. I
! September, 1990 (March, 1986, with reserve full ,
l core discharge) l l
- Docket Noc. 50-277/50-278 Attachment to Monthly Operating Report for August, 1985 Peach Bottom Atomic Power Station Narrative Summary of Operating Experiences August, 1985 UNIT 2 Unit 2 began the period at 96% power. Load was reduced on August 3 to accommodate the testing of newly installed recirculation system piping.
On August 5, the reactor scrammed from full power during turbine valve testing as a result of a turbine stop valve pressure switch setting being higher that the recommended value. The "A" reactor feed pump turbine exhaust rupture disk was repaired following the scram to remedy a vacuum leak.
During startup on August 7, the reactor scrammed as a result of high intermediate range neutron flux while maneuvering control rods to maintain reactor pressure. The generator was resynchronized on August 8.
On August 8, a load reduction was initiated after an increase in the main steam line radiation level, while placing a condensate filter demineralizer in service. On August 10, load was again reduced for a Control Rod Drive (CRD) accumulator diaphram replacement. Full load was achieved on August 12.
On August 12, the unit was shutdown from full power to comply with license requirements due to an inoperable Residual Heat Removal (RHR) system injection valve, coincident with the E-3 diesel generator being out-of-service for yearly maintenance.
The reactor was restarted on August 15, after repairs to the injection valve and the restoration of the diesel generator to service.
On August 17,'a load reduction was initiated for control rod pattern adjustment. Full power was achieved on August 18.
On August 19, the unit was again shutdown to comply with license requirements due to the E-2 diesel generator being out-of-service, coincident with another failure of the Residual Heat Removal (RHR) system injection valve. Repairs to the RHR system injection valve were completed and the diesel generator was restored to service on August 25. The reactor was restarted that same day.
During startup on August 26, the reactor scrammed again from l false low water level signals while the reactor pressure l
transmitter was being returned to service. Following l
maintenance, the reactor was restarted and the turbine-generator was synchronized on August 27. Full load was achieved on August 28.
I _ __
AttcchmLnt to Monthly
's Oparating Rsport for August, 1985 Page 2 On August 29, a trip of one recirculation pump was performed to test the dynamic loads on the new recirculation system piping.
On August 31, the unit was operating at 100% power.
UNIT 3 The sixth refueling outage continued through the month of August. !
As of August 30, inspections of 88 welds, in accordance with-Generic Letter 84-11, have been completed. Seventeen of the 88 welds have crack indications, with nine of the seventeen welds requiring weld overlay.
Nine of ten recirculation safe ends examined have crack indications in the thermal sleeve to safe end crevice area. GE does not recommend safe end repairs based on a crack growth analysis justifying continued operation through the next operating cycle. NRC approval of plans for addressing the pipe i crack problem is required prior to startup.
Visual inspection and bubble testing of the core spray spargers for Inter Granular Stress Cracking Corrosion (IGSCC) have verified thru wall cracks in one of the two piping tees. At this time, a repair procedure is being developed by GE.
Inspection of the Source Range Monitor and Intermediate Range Monitor dry tubes indicated cracking on 10 of the 12 tubes. One of these dry tubes has broken in the upper region near the pressure spring loading. However, this does not affect the boundary of dry tube integrity. It is planned to replace all 12 dry tubes.
Fuel sipping and inspection have been completed, indicating corrosion on 101 fuel assemblies. Reconstitution of fuel assemblies is'being performed to replace defective pins.
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PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 (21538414000 September 13, 1985 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 August, 1985 forwarded pursuant to Technical Specification 6.9.1.C under the guidance of Regulatory Guide 10.1, Revision 4.
Very trul yours,
%- v-R. H. Logue Superintendent 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 IEat IlI