ML20212K832
| ML20212K832 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/31/1986 |
| From: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8608250081 | |
| Download: ML20212K832 (14) | |
Text
.
P;Ech Bottom Atomic Power Station F
Nstrativ2 Summary of Oparating Experience July, 1986 UNIT 2 Unit 2 began the report period operating at full power.
With the exception of load reductions for main transformer high oil temperatures, the unit remained at full power until July 18.
On July 19, the main turbine was manually tripped with the reactor remaining critical at approximately 25% power, to repair steam leaks in the moisture separator manways.
The repairs were completed, and the unit was returned to service on July 20.
Full load was achieved on July 22.
-Later the same day, a 50 MW. load reduction was taken due to main transformer high oil temper 5ture, followed by a reduction to 650 MWe to accommodate a control rod pattern adjustment.
Load recovery was completed on July 24.
Unit 2 ended the report period operating at 100% power.
Unit 3 Unit 3 began the report period operating at full power.
Several load reductions were taken throughout he month as a result of main transformer high oil temperatures.
On July 5, the "B"
reactor feed pump (RFP), was manually tripped following a low flow annunciation and an observed decrease in reactor water level caused by binding in the "B"
reactor feedpump turbine control linkage.
The recirculation pump speeds were reduced to 40%, resulting in a load reduction to approximately 750 MWe.
The control linkage was relubricated and load recovery was initiated the same day.
On July 19, the reactor automatically scrammed from 87% power, due to high nedtron flux caused by the closure of the 80B main steam isolation valve (MSIV).
The closure occurred as a result of the DC solenoid valve coil being previously burned out, and the power to the AC solenoid valve being momentarily interrupted as a result of the opening of the 3SU-E breaker.
The AC and DC solenoid coils were replaced..Other work performed during the outage consisted of:
repairs to the reactor core isolation cooling (RCIC) o steam supply valve, o
3A recirculation pump seal repairs, o
replacement of the floating head gasket to remedy a leak in the "D" RHR heat exchanger, and o
cleaning of the main transformer oil coolers.
f Unit 3 ended the report period with startup in progress.
7
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9608230081 860730 PDR ADOCK 05000277 R
1 Docket No. 50-277 Attachment to Monthly Operating Report for July, 1986 UNIT 2 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
l February 28, 1987 3.
Scheduled date for restart following refueling:
May 30, 1987 l
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 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:
1 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 (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.
Replacement higher density fuel racks i
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 is scheduled for completion by January 31, 1987.
Docket No. 50-277 Attachment to Monthly Operating Report for July, 1986 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, 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) i
'L-
Docket No. 50-278 Attachment to Monthly Operating Report for July, 1986 UNIT 3 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
September 12, 1987 l
3.
Scheduled date for restart following refueling:
September 10, 1988 l
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 January 7, 1988 6.
Important licensing considerations associated with refueling, e.g.,
new or different fuel design or supplier, unreviewed design or performance analysis metheds, significant changes in fuel i
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 - 764 Fuel Assemblies (b) Fuel Pool - 1496 Fuel Assemblies, 6 Fuel Rods t
I
Docket No. 50-278 Attachmant to Monthly Operating Report for July, 1986 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 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 whicc 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 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 (March, 1996, with reserve full core discharge) l
=
I AVCASE DAILY LMIT POWE3 LEVEL DOCKET NO. 50 - 277 LMIT PEACH BOTTOM LMIT 2 DATE AUGUST 15, 1986 COMPANY PHILADELPHIA ELECTRIC COMPANY N.M. A LDEN ENGINEER-IN-CHARGE LICENSING SECTIDH MJCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 MONTN JULY 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-NET)
(MWE-NET) 1 1955 17 1056 2
1049 18 973 3
1056 19 0
4 1060 20 870 5
1056 21 925 6
1955 22 566 7
1039 23 820 i
j 6
1055 24 1929 l
-9 1061 25 1947 l
10 1049 26 1044 11 1055 27 1042 12 1956 28 1037 13 1054 29 1943 l
14 1953 30 1939 i
t 15 1954 31 1037 l
I li 1954 i
~
AVERAGE DAILY LMIT POWE2 LEVEL DOCKET ND. 50 - 278 LMIT PEActi BOTTOM UNIT 3 DATE AUGUST 15, 19%
COMPANY PHILADELPHIA [LECTRIC COMPANY W.M. ALDEN ENGINEER-IN-CHARGE l
LICENSING SECTION PAJCLEAR GENERATION DIVISION I
TELEPHONE 1215) 841-5022 MONTH
. ALLY 19%
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IPedE-NETI (PetE-NETI 1
1042 17 995 2
2004 18 941 3
1019 19 652 4
1043 20 0
5 958 21 0
6
%9 22 0
7 924 23 0
8 951 24 0
9 991 25 0
10 2004 26 0
11 1034 27 0
12 1004 28 0
13 985 29 0
14 985 30 0
15 1004 31 0
16 1035 J
a OPERATIPE DATA CEPORT DOCKET NO. 50 - 277 DATE AUGUST 15, 1986 CortPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M. ALDEH ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISIDH TELEPHONE (215) 841-5022 OPERATING STATUS
- 1. WIT HAttE: PEACH BOTTort WIT 2 l HOTES: UNIT 2 EXPERIENCED ONE l
l l
- 2. REPORTING PERIODI JULY, 1986 l
SCHEDULED SHUTD0544 Ale l
l l
- 3. LICEN5ED THERMAL PONER(PNTI:
3293 l
ONE SCHEDULED LOAD l
l l
- 4. HAffEPLATE RATING (GROSS P0dE):
1152 i
REDUCTION.
I e
l l
S. DESIGH ELECTRICAL RATING (HET P9dE):
1065 l
l l
l
==
- 6. NAXIrtkt DEPEPOABLE CAPACITY (GRUSS P9dE): 1098 l
l l
l
- 7. MAXIrt#1 DEPDCABLE CAPACITY (HET PedEli 1051 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS PAREER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO letICH RESTRICTED, IF ANY (HET PliEls v' 10. [EASONS FOR RESTRICTIONS IF ANY THIS NONTH YR-TO-DATE CUNULATIVE
- 21. HOLF43 IN REPORT 1HG PERIOD 744 5.087 105.839
- 12. 94kEER OF HOURS REACTOR HAS CRITICAL 744.0 4,400.7 69,594.9 fl [13. CEACTOR RESERVE SHLTTD0644 HOLWS 0.0 0.0 0
.i
'14. HOURS GENERATCR OH-LINE 715.1 4,273.8 67.402.6 15.154IT RESERVE SHUTDalet HOURS 0.0 0.0 0.0 li. GROSS THERMAL ENERGY GENERATED (Pteil 2,334,648 12.972.182 199,238,697
- 17. GROSS ELECTRICAL ENERGY GENERATED (Pteil 760.260 4.286,460 65,499.420
=__
'18. HET ELECTRICAL ENERGY GEHERATED (Ptoll 729,091 4.130,025 62.722.320
- 17. WIT SERVICE FACTOR
%.1 84.0 63.7 3.
=_
m
o
- 20. WIT AVAI, LABILITY FACVOR
%.1 84.0 03.7
_==
2I. WIT CAPACITY FACTOR (USING MDC NET) 93.2 77.2 56.4
- 22. WIT CAPACITY FACTOR (USING DER NET) 92.0 76.2 55.6
==
- 23. WIT FORCED OUTAGE RATE 0.0 13.4 13.0
- 20. SHUTD06NS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE. Afe CtRATION OF EACH):
REFUELING OUTAGE FEBRUARY 28,1987 TO MAY 30,1987
- 25. IF SHUTD0lM AT EPG OF REPOR) PERIOD, ESTIMATED DATE OF STARTUP:
- 26. WITS IN TEST STATUS (PRIOR TO COPMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 C0pmERCIAL OPERATI N 07/05/74 a
._,e.
-... ~ __
1 OPERATING DATA CEPORT DOCKET NO. 50 - 278 DATE AUGUST 15, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M. A LDEN ENGINEER-IN-CHARGE LICENSING SECTION MJCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 OPERATING STATUS
- 1. UNIT HAME PEACH BOTTOM (MIT 3 i NOTES: IMIT 3 EXPERIENCED ONE l
l l
- 2. REPORTING PERIODI JULY, 1986 l
AUTOMATIC SCRAM.
l l
l
- 3. LICENSED THERMAL POWERIMWTl*
3293 l
l l
l C. NAMEPLATE RATING (GROSS MWElt 1152 l
l l
l
- 5. DESIGN ELECTRICAL RATING (MET MWEls 1065 l
l l
l
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWElt 1098 l
l l
l
- 7. MAXIMUM DEPENDABLE CAPACITY INET MWElf 1035 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS fITEMS NLREER 3 THROUGH 7) SINCE LAST REPORT, GIVE REAS0tist
- 9. POWER LEVEL TO letICH RESTRICTED, IF ANY (HET ISiElf
- 10. REASON 3 FOR RESTRICTIONS IF ANY8 THIS MONTH YR-TO-DATE CUMULATIVE
- 11. P'JURS IN REPORTING PERIOD 744 5,087 101,735
- 12. NUMBER OF NOURS REACTOR NAS CRITICAL 437.9 2,927.8 71,541.0
- 13. REACTOR RESERVE SNUTDOWN NOURS 0.0 0.0 0.0
- 10. NOURS GENERATOR OH-LINE 448.2 2,681.5 69,535.9
- 15. UNIT RESERVE SHUTDOWN NOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED (MWHI 1,409,544 7,314,605 202,311,269
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWHI 463,720 2.368,950 66,362,620
- 18. NET ELECTRICAL ENERGY GENERATED (MWH3 440,295 2,257,687 63,650,428
- 19. UNIT SERVICE FACTOR 60.2 52.7 68.4
-e
- 20. WIT AVAILABILITT FACTOR CO.2 52.7 68.4 i
- 21. UNIT CAPACITT FACTOR (U5ING fGC NET) 57.2 42.9 60.4
- 22. WIT CAPACITT FACTOR (USING DER NET) 55.6 41.7 58.7
- 23. WIT FORCED OUTAGE RATE 39.8 13.4 7.4
- 24. SHUTDOWS SCHEDULED OVER NEXT 6 HUNTHS ITTPE, DATE. Ate DLRATION OF EACHl SAFE-EW/ PIPE WELD INSPECTION JAMJART 3,1987 TO JAMJART 23, 1987
- 25. IF SHUTDOW AT Em 0F REPORT PERIOD, ESTIHATED DATE OF STARTUP:
- 26. WITS IN TEST STATUS (PRIOR TO CortfERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CitITICALITT
___/.07 /_74 08 INITIAL ELECTRICITT ggjgg774 CottfERCIAL OPERATION M/U/74
I WIT SHUTD0604S AM) POWER REDUCTIONS DOCKET NO. 50 - 277
.......__ ___ =.
LMIT NAME PEACH BOTTOM UNIT 2 DATE AUGUST 15, 1986 REPORT MONTH JULYe 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY N.M. A LDEN ENGINEER-IN-CHARGE LICENSING SECTIDH MJCLEAR GENERATI0H DIVISIDH TELEPHONE (215) 841-5022
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> - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATI0H OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT ILER)
D - REGULATORY RESTRICTIDH 4 - OTHER (EXPLAIH)
FILE (HUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATIDH F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIH)
H - OTHERIEXPLAIH)
EXHISIT I - SAME SOURCE
D (MIT SHUTDolef5 Ate POWER RED'JCTIONS DOCKET NO. 50 - 278
. =-_ ____
UNIT NAME PEACH BOTTOM UNIT 3 DATE AUGUST 15, 1986 REPORT MONTH JULY, 1986 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY W.M. ALDEN ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATION DIVISION TELEPHONE (215) 841-5022 l
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1 3-86-16 l ED l CKTBRK l REACTOR SCRAM FROM 87% POWER ON HIGH NEUTRON I
l l
l l
l l
l l FLUX AS A RESULT OF THE TRIP OF THE 83 STARTUP l
l l
l l
l l
l l FEED BREAKER WHICH CAUSED THE FAST CLOSURE OF l
l l
l l
l l
l l THE 80-B MSIV.
I l
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l 295.8 l l
l l
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(1)
(2)
(3)
(4)
- FORCED REASON METHOD EXHIBIT S - INSTRUCTIONS
- SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MAI AJAL SCR AM.
tNIRT $HEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE (NUREG-0161)
E - OPERATOR TRAINING + LICENSC EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
N - OTHER(EXPLAIN)
EXHIBIT I - SAME SOURCE
PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.191o1 August 15, 1986 (215)841-4000 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 July, 1986, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
Very truly yours, tl g V
A r4 W. M. Alden Engineer-in-Charge Licensing Section Nuclear Generation Division 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)
G.
E.
Gears, NRC Project Manager Mr. Thomas Magette, Maryland Power Plant Siting INPO Records Center i
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