ML19320D013
| ML19320D013 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom |
| Issue date: | 07/10/1980 |
| From: | Alden W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML19320D003 | List: |
| References | |
| NUDOCS 8007180433 | |
| Download: ML19320D013 (9) | |
Text
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AVEdAGE 1AILY UNIT PO ER LEVEL 00CKET h0. $0 - 277 UNIT PEACH 601 TOM UN!! 2 OATE Ji't.Y 10, 1960 COMPANY PHILADELPHIA ELiCTRIC COMPANY W.N.ALDEN ENGINEER-IN-CHAdGE NUCLEAR SECi10N GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 MONTH Juht 19b0 DAY AVERAGE DAILY POWER Li'4EL OAY AVERAGE DAILY P0tdE4 LEVEL (MWh-NtTI (mwE-NEil 1
0 17 0
2 0
18 0
3 0
19 0
g 4
0 20 0
5 0
21 0
6 0
22 0
F 7
0 23 0
6 0
24 0
9 0
25 0
l 10 0
26 0
f 11 0
27 0
12 0
28 0
1 13 0
29 0
l 14 0
30 0
15 0
1 16 0
)
AWtRAGE DQlLY UNIT PODEA LEVEL LGCKET NO. 50 - 276 UNIT PE ACH BOTTOM UNii 3 DAIE JULY 10, 1980 COMPANY PHILAbELPHIA ELECIR1C COMPANY W.M.ALDEN E NGI N EE R-IN-CH ARGE NUCLEAR SECTION GENERAT10N DIVISION-NUCLcAR TELEPHONE (215) 841-5022 MONTH JUNE 1980
=
DAY AVERAGE DAILY POWEM-LEVEL DAY AVERAGE DAILY PDhER LEVEL (MWL-NET)
(MWE-NET) 1 0
17 1055 2
0 18 1053 3
121 19 1052 4
749 20 1055 5
1002 21 1057 o
1040
'2 1055 7
669 23 luS7 8
1053 24 1057 9
1053 25 1053 j
10 1055 26 1050 i
i 2
11 1055 27 1055 L
i 12 1054 26 1056 13 1027 29 1059 14 1057 30 1054 15 1050 l
16 1054 I
l
UNIT snuiDOWNS AND POWER REDUCTIONS DOCRET NO. 50 - 277
-_=.
UNIT NAME PEACH BOTTOM UNIT 2 DATE JULY 10, 1980 REPOk1 MONTH JU NE, 1960 COMPLETED SY PHILADELPHI A ELECTRIC COMPANY W.M.ALDEN ENGINEER-IN-CNARGE NUCLEAR SECTION GENERATIDN DIVI 51DN-NUCLEAR TELEPNONE (215) 841-5022 l
l l
l l METHOD OP l LICENSEE 15YSTEMICOMPONENil CAUSE AND CORRECTIVE i
ilVPE100kATIDNIREA50N15huiTING DOWNI EVENT l CODE l CODE I ACTION TO NO.!
LAlE I (1ll IHOUR5il (2) l REACTOR (3) l REPORT # l 14) i 153 l PREVENT RECURRENCE
==-
=-
i i
i l
i i
i i
I 9 l 600001 1 5 1 7?O.0 1
C l 2
i NCNE I RC l FULLXX l CONTINUATION OF REFUEL DUTAGE.
1 i
i i
i l
1 I
i i
i i 720.0 I
I I
I I
I (1)
(2)
(3)
(4) l F - FORCEO.
REA5GN METHOD EXHIBIT G - INSTRUCTIONS 5 - SCHf?utEO A - EQUIPMENT FAILURE (EXPLAIN) 1 - MA NU A L FOR PREPARATION OF DATA B - MAINTENANCE OR TCST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTDMATIC SCR AM.
EVENT REPORT (LERI D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE INUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINA110N F - ADMIN 151RAl!"*
(5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHERIEXPLAIN)
EXHIBIT I - SAME SOURCE
I uN11 ShuTDdhNS AND POkta REDUCTIONS 00CKkT NO. 50 - 278
_ __==_
UNIT NAME PEACH 80TTOM UN11 3 DATE JULY 10, 1960 REPORT MC'.TH JUNE, 1960 COMPLETED By PHILADELPHI A ELECTRIC CCMPANY W.M.ALDih ENGINEER-IN-CHARGE NUCLE AR SECTIDN GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 I
l l
l l METHOD OF l LICENSEE lSYS1EMlCOMPONENil CAUSE AND CORRECTIVE l
61YPelDuMAT10NldEASONISHUITING 00WN1 EVENT l CODE i CODE l ACTION TO NO.i DAlt 1 (all inOuRSil (21 1 REACTOR 43) l REPORT e 1 (4) l (5) l PREVENT RECURRENCE I
I I
i i
I i
i i
12 1 o00001 i F l 060.2 l
A l
1 l
NONE i Cb l PUMPXX l CGNT. OF 38 REACTOR RECIRC. PUMP SEAL REPLACEM1 i
i 1 ----- I i
l l
1 l
l l
l 60.2 l
l l
l l
l til (2)
(3)
(4)
F - FORCED REASON METHDO EXHIBIT G - INSTRUCTIONS S - SCHEDULED A - EQUIPMENT FAILURE REXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA 8 - MAIN 1ENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEE73 FOR LICENSEE C - R EF U E L. I NG 3 - AUTOMATIC SCR AM.
EVENT REPORT (LER)
O - REG'JLATDAY RES1RICTION 4 - OTHER (EXPLAINI FILE (NUREG-0161)
E - OPERATOR 1 RAINING + LICENSE EXAMINATION
~
F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAINI H - OTHER(EXPLAINI EXHIBIT I - SAME SOURCE
- n..
OPtRATING DATA REPORT DDGKET NO. 50 - 277 Daft JULY 10, 1960 i
COMPLETkD BY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN E NGINE E R-IN-CH A RGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TELEPHONE (215) 841-5022 GPtkATING STATUS
- 1. UNII NAME8 PEACH BOTTOM UNIT 2 1 NOTES: TH15 UNIT IS IN ITS l
l l
C. KE PORTING PERIOD:
JUNE, 1960 i
FOURTH REFUELING OUTAGE.
l l
l
- 3. LICENSED THERMAL POWER (MWils 3293 1
1 l
l
- . NAMtPLATE RATING (GR05S MWEla 1152 l
1 l
l
- 5. OE 51wN ELECTRICAL RATING (NET MWEl a 1065 l
l l
l
- o. MA AIMUM OEPENDAdLE CAPACITY (GROSS MWEls 1098 l
l g
l
- 7. MAXIMUM DEPENDABLE CAPAC11Y (NET MWEls 1051 1
I
- e. IF LHANGES DCCUR IN CAPACITY RATINCS 11TEMS NUMBER 3 THROUGH 73 SINCE LAST REPCAT, GIVE RE ASONS:
- v. Punen LtvEL TO WHICH RESTRICTiO, IF ANY INET MWEls
- 19. dcA50NS FOR RESTRIC'. IONS, IF ANY:
THIS MONTH YR-TO-CATE CUMULATIVE
- 11. Nouns IN REPORTims PERIOD 720 4,367 52,511
- 12. NUMmER OF HOURS REACTOR WAS CRITICAL 0
1,441 39,196 la. RE ACTOR RE5cRVE SHUT 00WN HOURS 0.0 0.0 0.0
- 14. noud5 GhNthATOR ON-LINE 0.0 1,390.2 38,373.0
- 15. UN11 RESERVE SHUTOOWN HOURS 0.0 0.0 0.0
- 16. 4RL55 THERMAL ENERGY GEhkRATED (MWHI O
3,831.770 110,597.41
- 17. GkOSS ELECTRICAL ENERGY GENERATED IMWHI 0
1,255,980 36bl4,210 le. NET cLkCTRICAL ENERGY GENERA 1ED (MwH)
-1,853 1,181,778 34,797,563 1v. UNIT StRv1CE F ACTOR 0.0 31.8 73.i
- 20. UN11 AV AIL ABILITY FACTOR 0.0 31.8 73.1
- 21. UNI T CAPAC ITY F ACTOR (USING MOC NET) 0.0 25.7 63.1
- 22. UNIT LAPACITY FACTOR (USING OER NET) 0.0 25.4 62.2
- 23. UNIT FORCED OUTAGE RATE 0.0 0.9 6.1
- 24. SHuTy0wNS SCMEDULc0 OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACHl UNI 1 2 SHUTDQuN FOR FCURTH REFUELING.
- 23. If snUTOCWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP 7/22/80
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCI AL OPcRATIONa s FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY
[
COMMERCIAL OPERATION l
0 - NEwA11VE VALUE REPORTED FOR CONSISTENCY WITH FEDERAL kNERGY REGULATORY COMMISSION REPORTS.
1
OrtRATING DATA REPCRT LOCnkT NO. 50 - 278 04Tt JULY 10, 1960 COMPLETED BY PHIL ADELPHI A ELECTRIC COMP ANY W.M.ALDEN ENGINEER-IN-CHA IGE NUCLEAR SECTION GENERATION DIVISION-NUCLEAR TEL EP HONt (215) 841-5022' OPERATING STATUS
- 1. uMIT NAMES PEACH 64TTOM UNIT 3 i NOTE 58 THIS UNIT EXPERIENCED ONE l
- 2. AiPuRTING PERIOD JUNE, 1980 l
00TAGE e
1 i
S. LICENSED THkRMAL POWERIMWTis 3293 I
I l
l
- 4. NAMkPLATE RAT!kG (GROSS MWEla 1152 l
1 l
l
- 5. OtSIGN ELECTRICAL RATING (NET MWEls 1065 I
l l
l
- e. MA AIMOM DEPhNDAOLk CAPACITY (GROS 5 MWEla 1098 i
I l
l
- 7. MA AIMUM DEPENDABLE CAPACITY INET MWEls 1035 l
l b.
IF CnANGES OCCUR IN CAPACITY R ATINGS (ITEMS NUMSER 3 THRDuGH 71 SINCE LAST REPORT, GIVE RE ASONS:
- 9. P0 hen LEvtL TO WHICH RESTRICTED, IF ANY (NET MWEls
- 10. Rc ASONS FOR RESTRICTIONS, IF ANY 8 THIS MONTH YR-TO-CATE CUMULATIVE
- 11. nouR$ IN REPORTING PER100 720 4,367 46.407
- 12. NuNcER GF nouRS Rt ACTOR WAS CRITIC AL 671 3,357 38,203
- 13. acACTG4 RESERVC SHUT 00WN HOURS 0.0 0.0 0.0
- 14. nouns GENERATOR ON-LINT 659.8 3,216.4 37,14a.2
- 13. UN11 RthERYk SHUTOOWN HOURS 0.0 0.0 0.0
==
- 10. GRG55 inEnPAL ENERGY GENERATED (MwH) 2,118,218 10,210,301 104,429,455
- 14. GR055 kLECTRICAL ENERGY GENERATED (MWH) 699,870 3,420,400 34,006,2eo
- 18. ht T cLEC1k1 CAL ENERGY GENERATED (MwHI 673,G42 3,296,504 32,o*1,30*
19. uN 11 SkRv1LE FAC104 91.6 73.7 76.7
- 20. UNIT AVAILAdILITY FACTOR 91.6 73.7 76.7
- 21. uN11 CAPACITY FACIOR tus1NG MOC Niil 90.*
72.9 65
- 22. uN11 CAPACITY FACTOR (U5ING DER NET) 67.9 70.9 63.3
- 23. UNIT FLRCEO QuTAGE R Af t S.4 18.3 7.9 24 SnulLLWNS SCHESULt0 OVtR NE AT 6 MONTHS (TYPL, DATE, AND DURATION OF EACHit is. IF 5NUTDbmN AT END OF REPORT PERIDO, ESTIMATED OATE OF 51ARTuPt 06/03/81
- 26. UNIIS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATIONI:
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY l-CGMMERCIAL OPERATION l
l
l D:ckst No. 50-277 Attachment to Monthly Operating Report for June,1980 REFUELING INFmMATIN 1.
Name of facility:
Peach Botton Unit 2 2.
Scheduled date for next refueling shutdown:
Fourth refueling outage in progress since March 21.
3.
Scheduled date for restart following refueling:
~.
July 22, 1980 h.
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?
Te'haie*1 specification changes to accommodate reload fuel.
Modifications to reactor corn operating limits are expected.
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
Amendment application submitted February 19 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 Initial utilization of General Electric pre-pressurized Fuel Ass e lies for this Unit.
7 The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a) Cors - 76h Fuel Assemblies (b) Fuel pool - 910 Fuel Asamblies 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, D number of fuel assemblies:
The spent fuel pool storage capacity has been relicerised for 2816 fuel assablies.
9 The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
September,1990
Docket No. 50-c to Attachment to Monthly Operating Report for June, 1980 REFUELING INFCRMATIN 1.
Name of facility:
Peach Botton Unit 3 2.
Scheduled date for next refueling shutdown:
March 7,1981 3
Schartuled date for restart following refueling:
June 5, 1981 h.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?
Yes.
If answer is yes, dtat, in general, will these be?
Technical specification changes to accoustodate reload fuel.
Mcdifications to reactor core operating limits are expected.
5 Scheduled date(s) for submitting proposed licensing action and supporting information:
January 23, 1981 6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviswed design or pet formance analysis methods, signifinant changes in fuel design, new operating procedurea.:
l None expected.
7.
The number of fuel assemblies (a) in the core ard (b) in the spent fuel storage pools (a)
Core 76h Fuel Assemblies (b)
Fuel pool - 712 Irradiated Fuel Assemblies 8.
Tne 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:
J The spent fuel pool storage capacity has been relicensed for 2816 fuel ass ablies.
9 The projected date of the last refueling that can be discharged to the j
spent fuel pool assuming the present licensed capacity:
1 1
September, 1991.
i
.~
.+ we;.m.w:
e...
p.-
O P3.iCM BOTIC: Ais !!IC PC.1:R STAi'Itti liN!RATIVZ GUI'l'!JE 0: 05'.:RATI:10 IGTSRlHICE3 J nl 2,. 1980 Unit ? 'ecraLions T'
Ottage begun on IIarch 21 continues. During the month the replac ant of the core spray piping inside the drywell, replacement of the
- cdwater spargers, and the cutting and capping of the Control Rod D*" te return line were complet.ed. In-service inspection work in the r octor vess21 was complet,ed on June 16. Return of the reactor fuel to the vessel was begun on June 22 following reflooding and other preparrton ucrl
- . One control red drive was replaced due to with-draw 31 difficulties associated with a bent spud finger at the rod to drive coup 1.ing. Reloading of the fuel to the vessel was canpleted on Julyjt.
Oi:e of the four diesels remains to be inspected.
SorPression pool (torus) modifications are completed and recoat-ing is in progress, i
Unit 3_ Operations The unit reached 1062 MWe on June 5, following the outage begun on 14ay 22 to replace the JB recirculation ptop seal. A load drop to 650 into was taken from June 6 to June 8 to perform control rod adjust-ment and repair a tube leak in the A-1 cendenser.
h}iA:jin 7/11/89
_