ML20101S990

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for June 1992 for Peach Bottom Atomic Power Station,Units 2 & 3
ML20101S990
Person / Time
Site: Peach Bottom  
Issue date: 06/30/1992
From: Baron M, Miller D
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CCN-92-14083, NUDOCS 9207200184
Download: ML20101S990 (14)
v • d • e


Text

--

[

. ccN 95-)4083 PillLADELPIIIA ELECTRIC COMPANY N

Pf.ACllIKJilDN1 ATOhtlC POwlR S1ATION R. D. I, ikix 208 in ] #

ik;lta, Penm)lvania 17314

~ etut annnwins euw e a op iu tita va (717)15470H D. B. Miller, Jr, vice PresMent July 14, 1992 Docket Nos. 50-277 50-278 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUBJECli Peach Bottom Atomic Power Station Monthly Operating Report Gentlemen:

Enclosed are twelve copies of the monthly operating report for Peach 110ttom Units 2 and 3 for the month of June 1992 forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.

Sincerely, m

n

/w76 DBht//AF/T

/DRM/MJB: cmc

~

Enclosure cc:

R.A. Burricelli, Public Service Electric & Gas T.M. Gerusky, Commonwealth of Pennsylvania J.J. Lyash, USNP.C Senior Resident inspector R.I. McLean, State of Maryland T.T. Martin, Administrator, Region I, USNRC li C. Schwemm, Atlantic Electric C.D. Schaefer, Delmarva Power INPO Records Center CC0692.NRC 9207200184 920630 gDR-ADOCK 05000277 i

PDR

4 9

[

Docket No. 50-277 f

Attachment to

(

Monthly Operating Report for June 1992 UNIT 2 REFUELING INFORM ATION 1.

Name of facility:

Peach Bottom Unit 2 2.

Scheduled date for next refueling shutdown:

Reload 9 scheduled for September 12,1W2.

3.

Scheduled date for restart following refueling:

Restart following refueling forecast for November 30,1W2.

4.

Will refueling or resume:lon of operation therefore require a technical specification change or other license amendment?

No.

- If answer is yes, what, in general, will these be?

5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A

~

Important licensing comiderations associated with refueling, e.g., new or different fuel design or supplier; 6.

unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

N/A s

L CCD692.NRC

1 NRC Monthly Operations Summary Peach llottom Atomic Power Station June 1992 UNIT 2 Unit 2 began the month at nominal l')0% power. Load was dropped on June 15 to clean the *B* main transformer coolce and condenser waterboxes. Unit 2 returned to full power following rnaintenance activities and remained a; that level until June 20. Power was reduced to 95% due to possible feedwater flow inaccuracies.

A sodium injection test was performed on the reactor feed pump flow chments. The preliminary results are being evaluated and a final determination is expected by mid-July. Power was reduced to 37% on June 27 because of a trip of the recirc motor generator set. Unit 2 returned to 95% power on June 29 and remained there for the rest of the month.

UNIT 3 Unit 3 began the month at nominal 100%. Power was reduced to 71% on June 3 to remove the *C" reactor feed pump from service to repair an inner cavity llange drain leak. Following repairs and return to full power, the leak repairs were found to be unsuccessful. Power was reduced again on June 5 and successful repairs were completed followed by return to full power. Power remained at nominal 100% until June 20 when power was reduced to 95% because of pm.sible feedwater flow inaccuracies. A transient occurred in the offgas system on June 26 causing recombination in the air ejector aftercondenser. Power was reduced to /41% on June 27 to re-establish offgas recombination in the recombiner vessel. Following these activities power was returned to 95%

and remamed there for the rest of the month.

CCWB2.NRC h--.___m__'.d__.__.______________________.___._______.__._._______.__________.__._.___.___._____._____.____.____._______._._____...____________

n Dockct No,50-277 l

Attachment to Monthly Operating Report for June 1992 Page 2 UNIT 2 REFUEL LNG INFORM ATION (Continucd) 7.

The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

(a)

Core - 764 Fuci Atsemblics (b)

Fuel Pool 1896 Fuct Assemblics,58 Fuct 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 3319 fuel assemblics.

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,

l. -

[.

September 1997 with full core offload capability.

CC0602.NRC

[_' _

Docket No,50-278 f

Attachment to hionthly Operating Report ;or June 1912 UNIT 3 REFUEL.1NG INFOR51 ATION 1.

Name of facility:

Peach 'lottom Unit 3 2.

Scheduled date for next refueling shutdown:

Reload 9 scheduled for September 4,1933 3.

Scheduled date for restart following refueling Restart following refuc'ing scheduled for October 29,1993 4,

Will refueling or resumption of operation thercafter require a technical specification change or other license amendment?

No if answer is yes, whv., in general, will these be?

c

~

N/A 5.

Schtfu!cd date(s) for submitting proposed licensing action and supporting information:

N/A 6.

Important licentiag 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:

N/A CC0691NRC

i; Docket No. 50-278 Attachment to Monthly Operating Report for June 1992 Page 2 UNIT 3 REFUELING INFORh! ATION (Continued) j;

- 7.

The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

(a)

Core 764 Fuel Assemblics f-(b)

Fuct Pool 1945 Fuel Assemblics,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 assemblics:

The spent fuel pool storage capacity has been relicensed for 3819 fuel assemblics.

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present capacity:

September 20(14 without full core offload capability.

September 1998 with full core ofiload capabili y.

t g-CCD692.NRC

7, Vi' e

AVERAGE DAILY UNIT POWER LEVEL i-DOCKET No. 50 - 2TT UNIT PEACH B0fiON UNIT 2

'i DATE JULY 15,1992 COMPANY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORi$ GROUP PEACH Boff 0M ATONIC POWER STATION TELEPHONE (717) 456 7014 EXT. 3321 MONTH JUNE 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE* NET)

(MWE NET) 1 1049 17 1006 2

1D64 18 925

.3 1064 19 1043 4

1063 20 994 5

1047 21 997 6

1059-22 995 7

1063 23 992 8

1051 24 1004 9

1057 25 999 10 1D40 26 994 11.

1053 27 B41 12 1053 28 4D4 13 1044-20 9 78 14 1052 30 988 15 1043 16 1048

a AVfRAGE DAILY UNIT POWER LEVEL DOCKET No. 50

  • 278 UW!f PEACM BOTTnM UNif 3 DATE JULY 15, 1992 COMPANY PN!LADELPHI A ELECTRIC COMPANT M. J. BARDN CUPERVISOR REPORTS CROUP PEACH BOTTOM ATOMIC POWER $1Afl0N TELEPHOWE (717) 456 7014 Ext. 3321 MONTH JUNE 1992 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE NET)

(MJE NET)

.1 1056 -

17 1047 2

1056.

18 1035 3

982 19 1039 4

1054 20 986 5

965 21 9A9 1055 22 988 7

1058 23 9 84 8

1054 24 996 9

1053 25 995 to 1048 26 990 11 1D49 27 970 12 1056 28 780 13 1040 29 9 77 14 1D48 30

-989 15 1039 16 1039

l i

i l

- OPERAflWG DATA REPORT i

COCKET Wo. 50 277 DATE JULY 15, 1972 00MPLETED BY PHILADELPHlA ELECTRIC COMPANY M. J. BARON i

SUPERVISOR i

REPORTL GROUP PEACH 60Tf0M ATOMIC POWER STAT 10N

-TELEPHONE (717) 456 7014 EXT. 3321 OPERATING STAVOS 1

1. UN!T NAME: PEACH BOTTOM UNIT 2 NOTES:
2. REPORTlWG PERIOD:-

JUNE, 1992

~

3. LICENSED THERMAL POWER (MWT):

3293

4. NAMEPLATE RAflWG (GROS $ MWE):

1152

5. DE$lon ELECTRICAL. RATING (WET MWE):

1D65 i

6. MAXIMUM DEPENDABLE CAPACITY (GROS $ MWE): 1098
7. MAXlMUM DEPENDABLE CAPACITY (NET MWE):

1055

8. If CHANGES DCCUR IN CAPACITY RATINGS (lTEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:

-r

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (WET MWE):

+

.10. REASONS FOR RESTRICTIONS, IF ANY: -

THIS MONTH YR*TO DATE CUMULATIVE

.11.'N00R$ IN REPORTING PERIOD 720

-4,367 157,703 12.~ NUMBER OF HOURS REACTOR WAS CRITICAL' 720.0 3,907.2 96,161.2

.13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 r

14. HOURS GENERATOR DN LINE-720.0 3,890.3 92,727.8
15. UNIT RESERVE $NUTDOWN HOURS

- 0.0 0.0 0.0 16.~ GROSS THERMAL ENERGY GENERATED (MWH).

2,252,832 12,451,008-

. 274,990,737 x17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 748,000 4,152,700 90,441,290

$18. NET ELECTRICAL ENERGY. GENERATED (MWH) 720,206 4,019,799' 86,637,032 PAGE 1 of 2-L l 'd l

p

y

.\\

ij s

OPERATlWG DATA kEPORT (CONTINUED)

DOCKCT NO. 50 277 DATE L

2

,j

',y 7415 MONTH

'1 10 DATE CUMULATIVE

19. UNIT SERVICE FACTOR 100.0 89.1 58.8
20. UNB:

'41 LABILITY FACTOR 10f J A9.;

$8.8 y

21. UNI) GPAClTY FACTM (U$1NG MDC NET) 2
22. UNIT CAPALITY FACTOR ;J$ LNG dew NET) 93.9 E6.4 51.6
23. UNIT FORCED OUTA*.E RATE 0.0 10.9 14.5 2,

' g,,

24. SHUTDOWS SCHEDULED OVER NE.I 6 MONTHS (TYFE, DATE. AND DURATIO ur EACH):

Refuel, 9/12/93 start, 80 days

{

.5.

IF $HUTDOWh AT END OF REPORT PEkluD, ESTIMATED DATE OF ST AR7UA: N/A

\\

i

.h

26. UNITS IM TC)T STATU$ (PRIOR TO COMMERCI AL OPERATION.'s FPRECAST ACHIEVED INITIAL CRITICALITT 09/16/73 IEITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 PAGE 2 0F 2

v 1

OPERATlWG DATt REPORT DOCKET NO. 50 278 DATE JULT 15,1992 COMPLETED BT PHILADELPHIA ELECTRIC COMPANT M. J. BARON TUPERVISOR TEPORTS GROUP PEACH BOTTOM ATOMIC POWER STAil0N TELEPHONE (717) 456 7014 ext. 332i OPERATING STATUS

1. UNIT NAME: PEACH BOTTOM UNIT 3 NOTES:
2. REPORTING PERIOD:

JUNE, 1992 l

3. LICENSED THERMAL POWER (MWT):

3293

4. NAMEPLATE RATING (GROSS MWE):

1152

5. DE3IGN ELECTRICAL RATING (NET MWE):

1065

6. MAxlMUM DEPENDARLE CAPACITY (CROS$ M'd): 1098
7. MAy!ML7t DEPENDABLE CAPACITY (NET MWE):

1035

8. IF CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
9. Po6ER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWE):
10. REASONS FOR REST'd!CTIONS, IF ANY:

THIS MOWTH YR TO-DATE CUMULATIVS

11. HOURS IN REPORTING PERIOD 720 4,367 153,59)
12. NUMSER OF HOURS REACTOR WAS CRITICAL 720.0 4,211.1 04,573.2
13. REACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0 -
14. HOURS GENERATOR ON LINE 720.0 4,008.4 91,313.4

~

15. UNIT RESERVE SHUiDOWN HOURS 0.0 0.0 0.0

' 16. GE0Ji-THERMAL ENERGY GENERATED (MWH) 2,292,216 12,167,136 268,261,066

17. GROSS ELECTRICAL ENERGY GENERATED (MWH) 758,000 4,052,900 83,055,432
18. NET ELECTRICAL ENERGY GENERATED (MwH, 730,115 3,922,716 84,405,733 PAGE 1 OF 2

u

. e.

s l

OPERATING DATA REPORT (CDNTINUED)

,Ai'KET NO. 50 - 278 DATE JULY 15,- 1992 THis MONTN TR TO-DATE CUMULATIVE

19. UWlf SERVICE FACTOR 1D0.0 91.8 59.4
20. UNIT AVAILABILITT FACTOR 100.0 VI.8 59.4
21. UNIT CAPACITY FACTOR (USING MDr WIT)

CA.0 B6.8 53.1

22. UNIT CAPACITY FAC1UR (USING DER NEii s,

B4.3 51.6

23. UNIT FORCED OUTAGE RATE 0.0 0.3 12.2
24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONitts (TYPE, DATE, AND DURATION OF EACN):
25. IF SHUTDOWN AT ENb 0F 4tecni PERIOD, ESilMATED DATE OF STARTUP: N/A
26. UNITS IN TEST STATUS (PR13R TO COMMERCIAL OPERATION):

FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 1

I

. INITIAL ELECTRICITY D9/01/74 COMMERCIAL OPERATIDN 12/23/74

'k PAGE 2 0F 2

)

g4 H.a t

__4 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50 277 UNIT NAME PEACH BOTf0M UNIT 2 DATE JULY 15,1992

'EPORT MONTH JUNE, 1990 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J, BARON SUPERVISOR REPORTS GROUP

  • EACH ROTVON ATOMIC POWER STATION TELEPNGef. (717) 456-7014 EXT. 3321

{

METHOD OF LICENSEE SYSTEM COMPONENT CAUSE AND CORRECTIVE TYPE DURATION REASON SHUTTING DOWN EVENT CODE ACTION TO CODE l No.)DATE (1)

(HOURS)

-(2)

REACTOR (3)

REPORT #

(4)

(5)

PkEVENT RECURRENCE 10 92061T 0.0 H

4 NA EB TRANSF POWER REQUCED FOR "B" hAIN TRANSFORMER CLEANING REAC10R NOT SHUT 00VW

- 11 920627 F

0.0 H

NA CB MOTORX RECIRC MOTOR GENERATOR TRIP REACTOR WAS NOT SHUTDOWN (1)

(2)

(3)

(4)

F FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS S - SCHEDULED-A - EQUIPMENT FAILURE (EXPLAIN) 1

  • MANUAL FOR PRLPARATION OF DATA B - MA!WTENANCE C* TEST 2 MANUAL SCRAM.

ENTRY SHEETS FOR LICENSEE C - REFUELING 3 AUTOKATIC SCR AM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4 OTHER (EXPLAIN)

FILE (NUREG-0161)

E - OPERATOR TRAINING + LICENSE EXAMINATION'

,F - ADMINISTRATIVE (5)

G - OPERAil0NAL ERROR (EX? LAIN)

H - OTHER(EXPLAIN)'

EXHIBIT I - SAME SOURCE

S UNIT SHUTDOWNS add POWER REDUCil0NS DOCKET NO. 50 278 UNIT KAME PEACH BOTTOM UNIT 3 DATE JULY 15, 1992 REPORT MONTH JUNE, 1992 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY M. J. BARON SUPERVISOR REPORTS GROJP PEACH BOTTOM ATOMIC POWER STAfl0N TELEPHONE (717) 456 7014 EXT 3321 METH00 0F 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 14 920603 0.0 A

4 NA CH PUMPXX REPAIR $ TO "C" RFP CASING DdAIN FLANGE REACTOE WAS NOT SHUT DOWN 15 920605 F

0.0 A

4 NA CB PUMPXX REPAIRS TO "C" RFP CASING DRAIN FLANGE REACTOR WAS NOT SHUT DOWN 16 920627 5

0.0 A

4 NA MB RECOMB RESTOR'c RECOMBINATION PROCESS REACTOR WAS NOT SHUTDOWN (1)

(2)

(3)

(4)

F FORCED REASON MET:10D EXHISIT G - INSTRUCTIONS S - SCHEDULED A - EQUIDMENT FAILURE (EXPLAl'N) 1 - MANUAL FOR PREPARATION OF DATA 8 - MAINTENANCE OR TEST 2 - MANUAL SCRut.

ENTRY SHEETS FOR LICENSEE C REFUELING 3 - AUTOMATIC SCRAM.

EVENT REPORT (LER)

D - REGULATORY RESTRICTION 4

OTh't (EXPLAIN)

FILE (NUREG-0161)

E. OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRAllVE (5)

G OPERATIONAL ERROR (EXPLAIN)

H - OTHER(EXPLAIN)

EXHIBli ! - SAME SCURCE l

l

__

Retrieved from "https://kanterella.com/w/index.php?title=ML20101S990&oldid=4304398"