ML20236C419

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Rev 2 to Monthly Operating Repts for Aug 1987
ML20236C419
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 08/31/1987
From: Middleton L
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20236C417 List:
References
NUDOCS 8710270166
Download: ML20236C419 (13)
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~ NRC ' Monthly ;0perations Sumary.

J Peach Bottom Atomic Power Station

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. August, 1987

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' UNIT 21 Unit 2 remained shut'own throughout the' report period.

d On' August 16, a half scram'and Group !! and Ill inboard isolations,

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._. including Shutdown Cooling' System and Reactor Water Cleanup System isolations

' occurred as a resuit of a.-loss of.offsite power due to a trip of the startup-j

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- feed ' breaker caused -by. a, tree ' contacting a.high voltage line. 'All of the j

~isolations were reset within 15 minutes and.all equipment responded as expected.

On August 20,=a Group II:and.III inboard:isolations occurred as a

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resultlof. maintenance workers-operating a. crane too close to the-220 kV supply, 1

linei causing.an electrical arc which tripped the startup feed breaker.

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. Essential. systems'were' restored to service-as needed after the isolations.

cStationL electrical power via the f 2 Startup feed was restored within five hours'.

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I On August 28,"ShutdownJCuoling isolated when Residual Heats Removal.

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.(RHR) fuses were removed for a maintenance permit. Shutdown Cooling was

< restored within eight minutes.

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L Unit 3 j

Unit 3 remained shutdown throughout the report period.

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-On August 16, a Group II outboard isolation occurred as a result of a i'

loss of.offsite power due to the startup feed breaker trip caused by'a tree

-touching a high voltage line (previously discussed for Unit 2) 1 On August 20, a Group 11 outocard isolation occurred when the startup feed breaker tripped due to a crane. coming too close to the_220 kV supply line, causing an' electrical arc (previously discussed for Unit 2).

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i g0270166871015 ADOCK 05000277 R

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1 Docket No. 50-277 Attachment to.

Monthly Operating.

Report for. August,1987 UNIT 2 REFUELING INFORMATION 1

O 1.

Name of facility:

Peach Bottom Unit 2 q

2.

Scheduled date for. next refueling shutdown:

Reload 7. in progress 3.

Scheduled date for restart following refueling:

Indeterminate due to Shutdown Order 4.

'Will refueling or resumption ~of operation thereafter require a technical specification change or other license amendment?

1 Yes If ~ answer is yes, what, in general, will these be?

Technical Specifications to accomodate reload fuel. Modifications to reactor core operating linits.

5.

Scheduled date(s) for submitting proposed licensing action and supp'orting information:

Reload 8 license amendment to be submitted January 1989.

'6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perfomance 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. pool:

1 (a) Core - 764 Fuel Assemblies, Core Offloaded During Outage (b) Fuel Pool - 1462 Fuel Assemblies, 58 Fuel Rods

'8.

The present licensed spent fuel pool storage capacity and the size of any C

increase in licensed storage capacity that has been requested or is

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-planned,.in number of fuel assemblies:

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

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,7 Docket No. 50-277-'

1 Attachment to Monthly Operating Report for August,-1987 Page 2 UNIT 2 REFUELING INFORMATION (Continued)-

'The projected date of the last refueling that can be discharged to'the -

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. spent ' fuel; pool: assuming -the present capacity, subsequent to the completion of. the new fuel racks' installation:

March,1998.(March 1995,withreservefull core dir')arge)'

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Docket-Wo. 50-278 l

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Attachment to Monthly Operating Report-for August, 1987

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UNIT 3 REFUELING INFORMATION

- 1.

Name.of facility:

= Peach Bottom. Unit 3 2.

. Scheduled date for. next refueling shutdown:

0ctober, 1987 (Major Pipe Replacement Outage)

3. -

Scheduled date for restart following refueling:

. July.9, 1988-

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'4.

Will"refuelingror= resumption-of~ operation thereafter require a technical

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. specification change or other license _ amendment?

Yes.

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

I Technical Specifications to accommodate reload fuel. Modifications to i

reactor core operating limits.

- 5.

Scheduled.date(s) for submitting' proposed licensing action and supporting

..inf ormation:

1 Reload 7 License Amendment to be submitted March'11, 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:

1 None expected.

7..

The number of. fuel assemblies (a) in the core and (b) in the spent fuel

-l storage' pool:

(a) Core - 764 Fuel Assemblies (b) Fuel Pool - 1496 Fuel Assemblies, 6 Fuel Rods L

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Docket No. 50-278 i.'

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Attachment to-

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Monthly Operating

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Report for August,,1987 l..

Page 2

' ONIT 3 REFUELING INFORMATION (Continued) r-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 fuci pool storage capacity has been-relicensed for 3819 fuel assemblies. This modification began on february;20 -1987. The completion date: for this modification has. been rescheduled for

' February,1989 to accommodate the Unit 3 pipe. replacement _ outage.

~

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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 -(reserve. full core discharge' following restart after 1987-88 pipe' replacement and refueling)

10. :The projected.date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, subsequent to_ the l

completion of:the new fuel racks installation:

March, 1999 (March, 1996, with reserve full coredischarge)

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AVERAGE DAILY UNIT P0HER LEVEL DOCKET NO. 50 - 277 UNIT PEACH BOTTON UNIT 2 DATE SEPTEMBER 15:1987 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR EUPPORT DEPARTHENT TELEPHONE I215) 841-6374 1

HONTH AUGUGT 1987 I

DAY AVERAGE DAILY P0HER LEVEL DAY AVFRAGE DAILY P0HER LEVEL iIME-NETI

    • HE-NETI 1

0 17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

C9 0

14 0

30 0

15 0

31 0

16 0

AVERAGE DAILY UNIT P0HER LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE SEPTEMBER 15,1987 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE ( 215) 841-6374 MONTH AUGUST 1987 DAY AVERAGE DAILY POHER LEVEL DAY AVERAGE DAILY P0HER LEVEL

( tt4E-NET I (HHE-NET) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

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J OPERATING DATA REPORTT t

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DOCKET Ho. 50 - 277 (s-c

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DATE SEPTEMBER 15,1987 s

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COMPLETED BY PHILADELPHIA' ELECTRIC COMPANY ~

H L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION di m NUCLEAR SUPPORT DEPARTHENT TELEPHONE ( 215) 841-6374 i

' OPERATING STATUS'

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1. UNIT NAMEl' PEACH'BOTT0H UNIT'2.

I NOTESI UNIT 2 REHAINED SHUTDOPN l

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.q 2.: REPORTING PERIDDt.

AUGUST, 1987 l

FOR ITS SEVENTH REFUELING.-

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. 3. LICENSED THERHAL PONER(PMT1 3293

-l OUTAGE. THE UNIT REMAINED

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6.. NAMEPLATE RATING (GROSS P94E).

1152 l

SHUTDotN IN COMPLIANCE HITH l

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- 5. ' DESIGN ELECTRICAL RATING (HET HHE ):

1065 l

'THE NRC MARCH 31, 1987 l-a a

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6. HAXIHUN DEPENDABLE CAPACITY (GROSS 994E )t'-1098 l-

-SHUTDOWN ORDER.

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' 7. HAXIMUM DEPENDABLE CAPACITY (NET HME )*

1051 l

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8.' IF-CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUPSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI

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PONER -LEVEL TO NHICH RESTRICTED, IF ANY (NET HME )I a.

9.10. REASONS FOR RESTRICTIONS IF ' ANY:

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THIS HONTH

.YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD 744' 5,831 115,343 i
12. NUMBER OF HOURS REACTOR.HAS CRITICAL-0 1,729.8 74,196.8 l
13. REACTOR RESERVE SHUTDOHN HOURS

' O.0 0.0 0.0

14. HOURS GENERATOR ON-LINE 0.0 1,724.0.

71,866.8 15.-UNIT. RESERVE SHUTDO>N HOURS.

0.0 0.0 0.0

16. GROSS THERMAL ENERGY GENERATED (HHH) 0 4,979,376 212,810,745 1

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17. GROSS ELECTRICAL ENERGY GENERATED (HHH) 0 1,648,230 70,019,230 1

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18. NET ELECTRICAL ENERGY GENERATED (HHH1 5,862 1,570,835 67,059,695 I

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j DPERATING DATA REPORT (CONTINUED)

DOCKET No. 50 - 277 l

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-l DATE SEPTEMBER 15,1987 i

THIS HONTH YR-TO-DATE CUHULATIVE

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194 UNIT SERVICE FACTOR.

- 0.0 29.6 62.3 1

< 20.' LAi!T AVAILABILITY FACTOR '

O.0 29.6 62.3'

- 21/ UNIT. CAPACITY FACTOR (USING HDC NET) 0.0 25.6-55.3 1

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22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 25.3 54.6 i
23. UNIT FORCED OUTAGE RATE 100.0 27.3-

'14.0 L 2). SHUTDOHNS SCHEDULED DVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION OF EACH18 s

REFUELING OUTAGE i 255 IF FNJTPA41 AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPt.

26. UNITS iN TEST STATUS (PRIOR TO COHHERCIAL OPERATION):

FORECAST ACHIEVED

. INITIAL CRITICALITY 09/16/73 l

INITIAL ELECTRICITY 02/18/74 COHHERCIAL OPERATION 07/05/74 i

PAGE 2 0F 2

  1. = NE0ATIVE VALUE REPORTED FOR CONSISTENCY HITH FEDERAL ENERGY REGULATORY COHHISSION REPORTS.

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' OPERATING DATA REPORT i

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C DOCKET NO. 50 - 278 DATE, SEPTEMBER'15,1987 j

gi' COMPLETED BY PHILADELPHIA ELECTRIC COMPANY l

L. L.'HIDDLETON TECHNICAL ASSISTANT si o

LICENSING SECTION;

. NUCLEAR SUPPORT DEPARTMENT ~

' TELEPHONE (215) 841-6374

.DPERATING STATUS-1 UNIT NAME " PEACH' BOTTOM UNIT.3 ~

l NOTES: 'LNIT 3 REHAINED SHUTDONN l

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2. REPORTING PERIODI-AUGUST, 1987..

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IN ACCORDANCE HITH THE-l l

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.J 3F LICENSED THERMAL' P0HER(MNT)4 i 3293 l

MARCH 31,.1987 NUCLEAR

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' 4. NAMEPLATE RATING IGROSS P94E )8

- 1152 l

REQULATORY CortfISSION ORDER.

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. 5[ DESIGN ELECTRICAL RATING (HET MHE):

. 1065-l l

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1098.-l

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6. MAXIMUM DEPENDABLE CAPACITY IGROSS #94E11 l

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' 7.' HAXIMUM DEPENDABLE CAPACITY (NET HME ls 1035 l

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8. IF. CHANGES DCCUR IN CAPACITY RATINGS (ITEMS NUPBER 3 -THROUGH 7) SINCE LAST REPORT, GIVE REASONSI
9. P0HER ' EVEL TO HHICH RESTRICTED, IF 'ANY (NET PME)I L

--10.' REASONS'FOR RESTRICTIONS, IF ANY 4

l THIS HONTH-YR-TO-DATE CUMULATIVE

11. HOURS IN REPORTING PERIOD ~

744

-5,831 111,239

'12. NUMBER OF HOURS REACTOR NAS CRITICAL 0

1,824.9 76,357.4 i

'13. REACTOR RESERYE SHVTDOHN HOURS-0.0 0.0 0.0

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~ 14. HOURS GENERATDR DN-LINE 0.0 1,659.6 73,929.3 l

152 UNIT RESERVE SHUTDOHN HOURS 0.0 0.0' O.0'

16. GROSS THERHAL ENERGY GENERATED IMHH) 0 4,759,248 215,278,901 I
17. CROSS ELECTRICAL ENERGY GENERATED (HHHI O

1,555,560 70,611,432 l

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13.. NET ELECTRICAL ENERGY GENERATED (MHH)

-5,862 1,478,641 67,720,734 t

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. OPERATING DATA REPORT (CONTINUED)

DOCKET No. 50 - 278' f"

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DATE SEPTEMBER 15,1987-l THIS HONTH

.YR-TO-DATE CUHULATIVE.

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119.' UNIT SERVICE FACTOR

' 0. 0 -

28.5 66.5

"-20. UNIT 4 AVAILABILITY FACTOR' 0.0.

23.5 66.5 l

)21.~ UNIT LADACITY FACTOR (USING HDC NET) 0.0 24.5-58.8 "22! UNIT CAPACITY FACTOR (U' ING DER NET) 0.0 23.8 57.2 S

~23.' UNIT FORCED DUTAGE RATE 100.0 71.5 12.6

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- 20'. SHUTDOWNS SCHEDULED OVER NEXT 6 HONTHS (TYPE, DATE, AND DURATION OF EACH)

. INDETERMINATE UNTIL HRC ORDER IS SATISFIED.

25i IF SHUTDOWN' AT END OF REPORT PERIDO, ESTIHATED DATE OF STARTUPI

' 20. UNITS IN TEST.. STATUS (PRIOR 'TO COHHERCIAL ' OPERATION):

. FORECAST

' ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COHHERCIAL OPERATION 12/23/74 p

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l k-t UNIT SHUTDOHKS AND P0HER REDUCTIONS DOCKET No. 50 - 277 1

UNIT NAME PEACH BOTTOH UNIT 2 1

DATE SEPTEMBER 15,1987 REPORT HONTH AUGdST, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE ( 215) 841-6374 l

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l l HETHOD OF l LICENSEE ISYSTEHlC0HPONENTl CAUSE AND CORRECTIVE l

l TYP E l DURATIOH l RE ASON I SHUTTING DO&N I EVENT l CODE l CODE I ACTION TO CE.1 DATE-l (1)] (HOURS){ (2) l REACTOR 13) l REPORT # l (4) l (5) l PREVENT RECURRENCE I

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5 l 870801 i S l 096.0 1 C l 1

1 N/A l RC l FUELXX l SHUTDOHN FOR ITS SEVENTH REFUELING OUTAGE.

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l N/A l ZZ l 777777 i CONTINUATION OF SHUTDOHN IN COMPLIANCE HITH I

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

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

EVENT REPORT (LER) 0 - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)

FILE (NUREG-0161)

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

C - OPERATIONAL ERROR (EXPLAIN)

H - OTHERI EXPLAIN)

EXHIBIT I - SAHE SOURCE

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UNIT SHUTDoletS AND P0HER REDUCTIONS DOCKET No. 278-UNIT NAME PEACH BOTTON UNIT 3 DATE SEPTEMBER 15,1987 REPORT MONTH AUGUST, 1987 COMPLETED BY PHILADELPHIA-ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT

. TELEPHONE (215) B41-6374.

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l CODE l. CODE l

' ACTION TO

{3. l -I DATE L l ' il)l ( HOURS )l - ( t ) l REACTOR 43) l REPORT # l' (4) I (5) l PREVENT RECURRENCE z....................................................

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4 1.a70801 I ? F 'l 744.0 1 0-l 1:

l N/A l ZZ 'l 777777 l SHUTDONN OF UNIT DN THE ORDER OF THE NRC.

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(4) 7 - FORCED' REASON-HETHOD EXHIBIT G - INSTRUCTIONS h-SCHEDULED

'A - EQUIPHENT FAILURE '(EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B

MAINTENANCE OR TEST 2 - HANUAL 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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