ML20148C663
| ML20148C663 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 12/31/1987 |
| From: | Alden W, Middleton L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8801250232 | |
| Download: ML20148C663 (14) | |
Text
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AVERAGE DAILY WIT P0HER LEVEL DOCKET NO. 50 - 277
.=.....................
WIT PEACH BOTTON UNIT 2 DATE JANUARY 15, 1988 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON.
TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 HONTH DECEtBER 1987 DAY AVERAGE DAILY POMER LEVEL DAY AVERAGE DAILY P0HER LEVEL ll (19tE-NET )
(194E-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
10 0
30 0
1 15 0
31 0
16 0
hph' 8801250232 871231 PDR ADOCK 05000277
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.DCD l
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,4 AVERAGE DAILY LNIT P0HER LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTOM UNIT 3 DATE JANUARY 15, 1988 COMPANY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION PAJCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 HONTH DECEPBER 1987 DAY AVERAGE DAILY PONER LEVEL DAY.
AVERAGE DAILY P0HER LEVEL
( P9tE-NET 1
( P94E-NET )
1 0
17 0
2 0
18 0
3 0
19 0
4 0
20 0
5 0
21 0
0 0
22 0
7 0
23 0
8 0
24 0
C 0
G 0
10 0
26 0
11 0
27 0
12 0
28 0
13 0
29 0
1 14 0
30 0
15 0
31 0
16 0
1 i
DPERATING DATA REPORT DOCKET NO. 50 - 277 DATE JANUARY 15, 1988 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE ( 215) 841-6374 OPERATING STATUS
- 1. LNIT NAME PEACH BOTTOM UNIT 2 l NOTES: UNIT 2 REMAINED SHLITDODN l
l l
- 2. REPORTING PERIO0t DECEMBER, 1987 l
UNDER NRC ORDER HITH l
l l
- 3. LICENSED THERMAL P0HER(tHT):
3293 l
REFUEL ACTIVITY CONTIMJING.
l l
l
- 0. NAMEPLATE RATING (GROSS MME):
1152 l
l l
l
- 5. DESIGN ELECTRICAL RATING (NET MHE lt 1065 l
l l
l
- 6. HAXIHUN DEPENDABLE CAPACITY (GROSS HHE ) 1098 l
l l
l
- 7. HAXIMUM DEPENDABLE CAPACITY INET MHE ):
1051 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUPBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI
- 9. P0HER LEVEL TO HHICH RESTRICTED, IF ANY (NET MHE)
- 10. REASONS FOR RESTRICTIDHS, IF ANY i
THIS HONTH YR-TO-DATE CtMJLATIVE
- 11. HOURS IN REPORTING PERIDO 744 8,760 118,272
- 12. NUMBER OF HOURS REACTOR HAS CRITICAL 0
1,729.8 74,196.8
- 13. REACTOR RESERVE SHUTDOHN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 0.0 1,724.0 71,866.8
- 15. UNIT RESERVE SHUTDOHN HOURS 0.0 0.0 0.0
- 13. GROSS THERMAL ENERGY GENERATED (MHH) 0 4,979,376 212,810,745
- 17. GROSS ELECTRICAL ENERGY GENERATED IMHHI O
1,648,230 70,019,230
- 18. NET ELECTRICAL ENERGY GENERATED (MHH)
-3,844 1,552,256 67,041,116 PAGE 1 OF 2
-. \\
OPERATING DATA REPORT (CONTIPAJED)
DOCKET No. 50 - 277 DATE JANUARY 15, 1988 THIS HONTH YR-TO-DATE CUHULATIVE
- 19. UNIT SERVICE FACTOR 0.0 19.7 60.8
- 20. UNIT AVAILABILITY FACTOR 0.0 19.7 60.8
- 21. UNIT CAPACITY FACTOR (USING HDC NET) 0.0 16.9 53.9
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 16.6 53.2
- 23. LNIT FORCED OUTAGE RATE 0.0 42.9 14.6
- 24. SHUTD06fG SCHEDULED OVER NEXT 6 NONTHS (TYPE, DATE AND DURATION OF EACH)
REFUELING OUTAGE
- 25. IF SHUTDODN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUPI
- 26. [ NITS IN TEST STATUS (PRIOR TO CatNERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 C0teERCIAL OPERATION 07/05/74 l
4 i
i PAGE 2 0F 2 u - NEGATIVE VALUE REPORTED FOR CONSISTENCY MITH FEDERAL ENERGY REGULATORY C0tHISSION REPORTS.
I l
i
OPERATING DATA REPORT DOCKET NO. 50 - 278 DATE JANUARY 15, 1988 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETCH TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTNENT TELEPHONE 12151 841-6374 OPERATING STATUS
- 1. WIT NAME PEACH BOTTOM WIT 3 l NOTESI UNIT 3 REMAINED SHUTDom l
l l
=.......................
- 2. REPORTING PERIODI DECEPEER,1987 l
UNDER NRC ORDER HITH l
l l
- 3. LICENSED THERHAL PCHERIMT):
3293 l
REFUEL AND PIPE REPLACEMENT l
- - _ _ =...
l l
- 0. NAMEPLATE RATING (GRO'S WE ):
1152 l
IN PROGRESS.
l l
l S. DESIGN ELECTRICAL RATING (NET t94E ):
1065 l
l l
l
- 6. MAXItthi DEPENDABLE CAPACITY IGROSS P94E) 1098 l
l l
l F. MAXIMUM DEPENDABLE CAPACITY (HET P94E18 1035 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS IITEMS NLPSER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI
- 9. P0HER LEVEL TO HHICH RESTRICTED, IF ANY INET ME):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR-TO-DATE cut 0LATIVE
- 11. HOURS IN REPORTING PERIOD 744 8,760 114:168
- 12. HUteER OF HOURS REACTOR HAS CRITICAL 0
1,824.9 76.357.4
- 13. REACTOR RESERVE SHUTDO W HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON-LINE 0.0 1,659.6 73,929.3
- 15. WIT RESERVE SHtJTDom HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (t94H) 0 4,759,248 215,278,901
- 17. GROSS ELECTRICAL ENERGY GENERATED (t94H) 0 1,555,560 70,611 432
- 18. NET ELECTRICAL ENERGY GENERATED (t94H)
-3,844 1,460,062 67,702,155 PAGE 1 0F 2
OPERATING DATA REPORT (CONTINUED)
DOCKET NO. 50 - 278 DATE JANUARY 15, 1988
)
THIS HONTH YR-TO-DATE CUHULATIVE
- 19. UNIT SERVICE FACTOR 0.0 18.9 64.8
- 20. UNIT AVAILABILITY FACTOR 0.0 18.9 64.8
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 16.1 57.3
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 15.7 55.7
- 23. UNIT FORCED OUTAGE RATE 0.0 74.7 13.3
- 24. SHUTDORG SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)8 INDETERMINATE UNTIL NRC ORDER IS SATISFIED.
- 25. IF SHUTDODN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP8
- 26. LNITS IN TEST STATUS (PRIOR TO Cot 91ERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COMMERCIAL OPERATION 12/23/74 I
i l
PAGE 2 0F 2
LNIT SHUTDOpt4S AND P0HER REDUCTIONS DOCKET No. 50 - 277 LNIT NAME PEACH BOTTON UNIT 2 DATE JANUARY 15, 1988 REPORT HONTH DECEtBER: 1987 COHPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE (215) 841-6374 3..==--
l l
11 l
l NETHOD OF I LICENSEE ISYSTEHlCOHPONENTI CAUSE AND CORRECTIVE I
I TYPE l(IiURATION I RE ASON I SHUTTING Dotti l EVENT l CODE I CODE I ACTION TO
.I DATE I (1)lj (HOURS)l I2) l REACTOR (3) l REPORT 8 l t4) l (5) l PREVENT RECURRENCE I
I i
l I
i l
i I
7 l 871201 l % 1 7M.0 i
C l 1
l N/A l RC l FUELXX l CONTINUATION OF REFUEL ACTIVITY l
I i ----- 1 I
l l
l l
l
\\
l 7%.0 l l
l l
l l
(1)
(2)
(3) 141 i
- FORCED REASON HETHC0 EXHIBIT G - INSTRUCTIONS i
1
~ - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - HANUAL FOR PREPARATION OF DATA 1
B. HAINTENANCE OR TEST 2 - HAPAJAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT ILER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE (NUREG-0161) l E - OPER/ TOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHERIEXPLAIN)
EXHIBIT I - SAME SOURCE m
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UNIT SHUTDODNS AND P0HER REDUCTIONS DOCKET NO. 50 - 278 LMIT NAME PEACH BOTTOM UNIT 3 DATE JAPAJARY 15, 1968 REPORT HONTH DECEtBER, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE (215) 841-6374 3............................................................................................................................
l l
l l
l HETHOD OF l LICENSEE ISYSTEHICOMPONEtEl CAUSE AND CORRECTIVE l
l TYPE lDURATIOHlREASONISHUTTING DO>Nl EVENT l CODE l CODE l ACTION TO
.I DATE I (ll1 (HOURS)l (2) l REACTOR (3) l REPORT 4 l (4) l (5) l PREVENT RECURRENCE I
I I
I I
I I
I I
7 l 871201 l S l 744.0 1 C l 1
l N/A I RC l FUELXX l CONTINUATION OF REFUEL AND PIPE REPLACEMENT l
l l
l l
l l
l l ACTIVITY.
1 I
I ----- 1 I
I I
I I
l l
l 744.0 l l
l l
l l
(1)
(2)
(3)
(4)
- FORCED REASON HETHOD EXHIBIT G - INSTRUCTIONS
- SCHEDULED A - EQUIPHEtR FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTCHATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE (PAJREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN)
EXHIBIT I - SAHi* SOURCE
PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHI A, PA.19101 (215)841 4000 January 14, 1988 Docket Nos. 50-277 50-278 Director Office of Inspection & Enforcement US Nuclear Regulatory Comission 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 December 1987, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
Very truly yours, h
lf,
W. M. Alden Director
)
Licensing Section Nuclear Support Division Attachment cc:
W. T. Russell, Administrator, Region I, USNRC T. P. Johnson, PBAPS Resident Inspector S. P. Mangi, Dept. of Envir. Resources P. A. Ross, NRC (2 copies)
R. E. Martin, NRC Project Manager Thomas Magette, Maryland Power Plant Siting INP0 Records Center d
d
NRC Monthly Operations Summary Peach Bottom Atomic Power Station December, 1987 UNIT 2 Unit 2 remained shut down throughout the report period in compliance with the March 31, 1987 Shutdown Order, with maintenance and restart activities in progress.
l Unit 3 Unit 3 remained shut down throughout the report period in compliance with the March 31, 1987 Shutdown Order, with recirculation system pipe replacement activities in progress.
i l
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Docket No. 50-277 Attachment to Monthly Operating Report for December, 1987 UNIT 2 REFUELING INFORMATION 1.
Name of facility:
i Peach Botton Unit 2 2.
Scheduled date for next refueling shutdown:
Reload 7 in progress 3.
Scheduled date for restart following refueling:
Indeterminate due to Shutdown Order 1
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?
Modifications to reactor core operating limits.
(Reload 7 amendment issued September 11,1987.)
l 5.
Scheduled date(s) for submitting proposed licensing sction and supporting information:
Reload 8 license amendment to be submitted August 1989.
6.
Important licensing considerations associated with refueling, e.g., new or j
different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:
I None expected.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool:
(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 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.
e Docket No. 50-277 Attachment to Monthly Operating Report for December, 1987 Page 2 UNIT 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 March,1998 (March 1995, with reserve full core discharge) 1
Docket No. 50-278 Attachment to Monthly Operating Report for December, 1987 UNIT 3 REFUELING INFORMATION 1.
Name of facility:
Peach Botton Unit 3 2.
Scheduled date for next refueling shutdown:
Reload 7 in progress (Major Pipe Replacement Outage) 3.
Scheduled date for restart following refueling Indeteminate due to Shutdown Order 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 accomodate 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 March, 1988 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:
(a) Core - 0 Fuel Assemblies (b) Fuel Pool - 2260 Fuel Assemblies, 6 Fuel Rods
Docket No. 50-278 Attachment to Monthly Operating Report for December,1987 Page 2 UNIT 3 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 nr is planned, in number of fuel assemblies:
The spent fuel 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.
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 (reserve full core discharge cannot be accommodated after the restart following the completion of the October, 1987 refueling outage until the completion of the new fuel racks)
- 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 (March, 1996, with reserve full coredischarge)