ML20214D693
| ML20214D693 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 04/30/1987 |
| From: | Alden W, Middleton L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC, NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8705210432 | |
| Download: ML20214D693 (14) | |
Text
)
Peach Bottom Atomic Power Station Narrative Summary of Operating Experience April, 1987 UNIT 2 Unit 2 remained shutdown during the report period for its seventh refuel outage.
The outage is scheduled for completion on June 24, 1987.
On April 7, the inboard and outboard Main Steam Line Drain Isolation Valves (MO-74 and MO-77) failed their local leak rate tests.
The MO-74 valve was repaired and retested satisfactorily.
Inspection of the MO-77 valve continues.
On April 8 at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />, the E-1 diesel generator was started for a weekly surveillance test.
The diesel was operating in parallel with the #3 startup feed at a load of approximately 1300 KW and connected busses E-13, E-22, E-33 and E-42.
At 0018 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />, the #3 startup feed was de-energized when an offsite power source was lost due to weather conditions causing the E-1 diesel load to increase to 3500 KW, 300 KW in excess of its design rating for approximately 20 minutes.
This condition resulted in a frequency reduction causing tripping of the 2B and 3A Reactor Protection System M-G sets.
At 0025 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />, busses E-13, E-22, E-33 and E-42 were transferred to the #2 startup bus by running l
diesel generators (E-1, 2, 3, 4).
On April 9, the E-1 diesel was blocked for service and inspection and found to be undamaged.
It was returned to service on April 12.
On April 18, core off-load was completed.
On April 21, a new control blade was being moved from the fuel pool to the core when it fell from the grapple into an empty region of the fuel pool racks.
A pin was found to be missing from the control rod blade grapple being used to handle the new blade.
No fuel damage and only superficial inconsequential damage to the control rod blade occurred.
i i
UNIT 3 Unit 3 remained in a cold shutdown condition during the report period in compliance with the March 31, 1987 Nuclear Regulatory Commission order, 8705210432 870430 PDR ADOCK 05000277 R
PDR y/ (p,y'
'h
n- _ -
~
, Dock 0t No. 50-277.
~ Attachment.to
. Monthly operating Report.for April, 1987-UNIT 2 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
March 13,.1987 3.
Scheduled date for restart following refueling:
Indeterminate due to Shutdown Order 4.
N111 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 submitted January 9, 1987.
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:
None expected.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pools (a) Core - 0 Fuel Assemblies, Core Offloaded During Outage (b) Fuel Pool - 2226 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 were approved b:r the NRC on February 19, 1986 which increases the imcensed fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.
This modification was completed on November 15, 1986.
1
DockGt No. 50-277 AttCchment to Monthly Operating _
Report for April,-1987 j
- 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, subsequent to the completion of the new fuel racks installation:
March, 1998 (March 1995, with reserve full core discharge) i 4
t m
~
DockGt No. 50-278 Attachment-to Monthly Operating Report for April,_1987 i
UNIT 3 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
September 12, 1987 (Major Pipe Replacement Outage) 3.
Scheduled date for restart following refueling:
June 17, 1988 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:
Relcad 7 License Amendment to be submitted February 5, 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:
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 l
1
Dock 3t No 50-278-
.Attcchm:nt to Monthly Operating
)
Report for April, 1987 Page 2 l
UNIT 3 REFUELING INFORMATION (Continued) 4 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 began on February'20, 1987_ and should be completed in mid July, 1987.
i 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
~
l to the spent fuel pool assuming the relicensed capacity, 1
subsequent to the completion of the new fuel racks installation:.
March, 1999 (March, 1996, with reserve full core discharge) i 4
I e
a l
)
)
~ AVERAGE DAILY LA41T PCMER LEVEL
+-
DOCKET No. 50 - 277 LA41T PEACH BOTTOM UNIT 2 DATE MAY 15,1987 COMPANY PHILADELPHIA ELECTRIC COMPANY-L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION-MJCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 l'
MONTH APRIL 1987 DAY-AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL
( 794E-NET 1 I#94E-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
29 0
14 0
30 0
15 0
16 0
AVERAGE DAILY LNIT PCHER LEVEL DOCKET NO. 50 - 278 UNIT PEACH BOTTON UNIT 3 DATE MAY 15,1987 COMPANY PHILADELPHIA ELECTRIC COMPANY
_=.
- - - = _ _ _ - - -...
L. L. HIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE ( 2151 841-6374 HONTH APRIL 1987 DAY AVERAGL DAILY POHER LEVEL DAY AVERAGE DAILY POHER LEVEL
( tNE-NET )
(ME-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
l 12 0
28 0
13 0
29 0
14 0
30 0
15 0
16 0
L j
OPERATING DATA REPORT DOCKET NO. 50 - 277 DATE MAY 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPAtTHENT TELEPHONE (215) 841-6374 OPERATING STATUS
- 1. UNIT NAHE PEACH BOTTON UNIT 2 l NOTES: UNIT 2 EXPERIENCE 0 ONE l
l l
- 2. REPORTING PERIOD 8 APRIL, 1987 l
SCHEDULED OUTAGE.
l l
l
- 3. LICENSED THERHAL P0HERINNT):
3293 1
l l
l
- 4. NAHEPLATE RATING 4 GROSS PHE ls 1152 l
l l
l S. DESIGN ELECTRICAL KATING INET HHEls 1065 l
l l
l
- 6. HAXIMUN DEPENDABLE CAPACITY (GROSS HHEls 1098 l
l l
l
- 7. HAXIMUN DEPENDABLE CAPACITY INET HHE li 1051 l
l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS IITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASONSI
- 9. P0HER LEVEL TO HHICH RESTRICTED, IF ANY INET HHE)I
- 10. REASONS FOR liESTRICTIONS. IF At#8 THIS HONTH YR-TO-DATE CUMULATIVE t
- 11. HOURS IN REPORTING PERIOD 719 2,879 112,391 l
- 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 OH-LINE 0.0 1,724.0 71,866.8
- 15. UNIT RESERVE SHUT 00HN HOURS 0.0 0.0 0.0
- 16. GROSS THERNAL LNERGY GENERATED IHHH1 0
4.979,376 212,810,745 4
- 17. GROSS ELECTRICAL ENERGY GENERATED IMHH1 0
1,648,230 70,019,230
- 18. NET ELECTRICAL ENERGY GENERATED IHHH)
-5,690 1,594,222 67,083,082 PAGE 1 0F 2 1
OPERATINS DATA REPORT (CONTIMJEO)
DOCKET NO. 50 - E77 DATE NAY 16.1997 lHIS NUNIH VR-10-DAIE CUMULATIVE 19 LRiff SERVICE FACTOR 0.0 59.9 63.9 0.0 59.9 43.9
- 10. Ut4II AVAIL 40ILITY FACTolt fl. IIIIT CAPACITY FACTOR IUSING NOC NET) 0.0 St.7 56.0
- 22. (1418 CAPACITY FACTOR IUSING DER NET) 0.0 5E.0 54.0 0.0 0.0 13.5
- 25. (Atti f 0RCED OUTAGE RATE F*e. SilU100HNS SCHEDULED OVER NEXT 6 NONTHS iTYPE, DATE, AND DURATION OF EACHit REFUELING OUTAGE MARCH 13e 1997 TO.AME E4 e 1997 I!i.1F SHUIDo>H AT END OF REPORT PER100. ESTIMATED DATE OF STARTUP8
- 76. UtitTS IN TEST STATUS (PRIOR TO COtMERCIAL OPERATIONif FORECAST ACHIEVED 19/16/F3 INITIAL CRITICALITY INITIAL ELECTRICITY 0E/10/74 COPMERCIAL OPERATION 97/05/T4 PAGE E OF E e. H4 HAf!VE VALUE REPORTED FOR CONSISTENCY NETH FEDERAL ENERGY REGULATONY COPMISSION REPORTS.
[
OPERATING DATA REPORT DOCKET NO. 50 - 278 DATE MAY 15,1987 l
COMPLETED DY PHILADELPHIA ELECTRIC COMPANY L. L. HIDLLETON TECHNICAL ASSISTANT LICENSING SECTION i
NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-63 74 CPERATING STATUS
- 1. UNIT NAME: PEACH BOTTott UNIT 3 l NOTES: UNIT 3 EXPERIENCE ONE l
l l
E. REPORTING PERIODI APRIL,1987 l
FORCED SHUTDOHN.
l l
l
- 3. LICENSED THERMAL P0HERIHHTit 3293 l
l l
- 4. NAMEPLATE RATING (CROSS HHEls 1152 l
l l
l S. DESIGN ELECTRICAL RATING INET MHE le 1065 l
l i
- 6. HAXIHUN DEPENDABLE CAPACITY (GROSS HHEls 1098 l
l l
l
- 7. HAXIHUN DEPENDADLE CAPACITY INET HHE):
1015 l
l
- 8. IF CHANGES QCCUR IN CAPACITY RATINGS IITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORTe GIVE REASONSI
- 9. P0HER LEVEL TO HHICH RESTRICTED IF ANY (HET HHEls
- 10. PEASONS FOR RESTRICTIONS IF AN(I THIS HONTH VR-TO-DATE CUNULATIVE
- 11. HOURS IN REPORTING PERIOD 719 2.879 100,287
- 12. HUNDER OF HOURS REACTOR HAS CRITICAL 0
1,823.2 76,355.7 II. REACTOR RESERVE F,HUTD0hN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR ON LINE 0.0 1e659.6 73,929.3
- 15. UNIT RESERVE SHUTDOHN HOOR$
0.0 0.0 0.0 I
- 16. GROSS THERHAL ENERGY GENERATED IMHHI 0
4,759.240 215.278.901 i
y j
- 17. GROSS ELECTRICAL ENERGY GENERATED (HHHI O
1,555,560 70.611.412 i
i i
1
- 18. NET ELECTRICAL ENERGY GENERATED (MHHI e
-5.690 1.502.029 67,744,122 i
I PAGE 1 0F t
OPERATING DATA REPORT (CONT!WED)
DOCKET No. 50 - 278 DATE HAY 15.1987 THIS NONTH YR *TO-D ATE CUHULATIVE
- 19. UNIT SERVICE FACTOR 0.0 57.6 68.3
- 20. UNIT AVAILABILITY FACTOR 0.0 57.6 68.3
- 21. UNIT CAPACITY FACTOR IUSING HDC NET) 0.0 50.4 60.4
- 22. UNIT CAPACITY FACTOR IUSING DER NkT) 0.0 41.0 58.7
- 23. UNIT FORCED OUTAGE RATE 100.0 42.4 9.4
- 24. SituTDORG SCHEDULED OVER NEXT 6 HONTHS (TYPE e DATE. AND DURATION OF EACH)8 INDETERMINATE UNTIL NRC ORDER IS SATISFIED.
- 25. IF SHUTDOW4 AT END OF REPORT PERIOD, ESTIHATED DATE OF STARTUPI
- 26. UNITS IN TEST STATU3 (PRIOR TO CormERCIAL OPERATIONil FORECAST ACHIEVED INITIAL CRITICALITY 06/07/74 INITIAL ELECTRICITY 09/01/T4 CormERCIAL OPERATION 12/23/T4 PAGE t CF 2 e
m
i L
UNIT SHUTD0te43 AND P0HER REDUCTIONS DOCKET No. 50 277 UNIT NAME PEACH BOTTON UNIT 2 DATE HAY 15.1987 REPORT HONTH APRIL, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. HIDDLETON TECHNICAL AS$1STANT LICENSING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE 1215) 841-6374 J
l l
l l
1 htTH00 0F 1 LICitett ISYSTEHlCOMPONENTI CAUSE AND CORRECTIVE I
ITYPtl0URATIONlREASONISHUTTING DOHNI EVENT l CODE i CODE I ACTION TO NO.I DATE I 1111 IHOURSil (t) i REACTOR III I REPORT S l 84) I 181 l PREVENT RECURRENCE i
l 1
1 i
l I
i I
i 5 l 870401 1 S 1 719.0 1 C l 1
1 N/A I RC l FUILXt i SHUTD0 Del FOR ITS SEVENTH REFUELING OUTAGC.
I I
I.-.-. I I
I I
I i
i i
1 719.0 I l
l l
l l
l lll (Il (3) 14)
F. FORCED REASON HETH00 EXHIBIT G. ItGTRUCTI0tG S - SCHEDULED A. EQUIPHCHT FAILURE (EXPLAINI
- 1. HAtAJAL FOR PREPARATION OF DATA l
B = HAINTENANCE OR TEST 2. HANUAL SCRAN.
ENTRY SHttTS FOR LICCtCtt C. REFUELING 3. AUTOHATIC SCRAN.
EVENT REPORT ILER)
D = REOULATORY RESTRICTION 4 - OTHER ltXPLAINI FILE INURto-0161)
( = OPERATOR TRAINIHQ + LICCtGE EXAMINATION F = ADMINISTRATIVE 151 0 = CPERATICHAL tRROR ltXPLAIN)
H = O!HERIEXPLAINI EXHIDIT I = SAHE SOURCE 1
i 4
~
I l
UNIT SHUTDoled AND P0HER REQUCTION3 DOCKET No. 50 ET8 UNIT HAHE PEACH BOTT0H UNIT 3 DATE HAY 15:1987 REPORT HONTH APRILe 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. HIODLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTNENT TELEPHONE 18151 841 6574 l
l l
l l HETH00 0F l LICEPCEE ISYSTCHlCOMPONENTl CAUOE AND CORRECTIVE l
l TY P E l DURATI ON l RE ASON I SHUTT ING 00691 l EVENT l CODE l C00C l ACTION TO
.NO.l DATE l 111l IHOUR311 lEl l REACTOR 45) l REPORT 8 l 44) l 181 l PREVENT RECURREtCE 1
I l
1 1
I l
I 1
6 l 070401 l F l 719.0 l D 1 1
l WA I ZZ l 777777 l SHUTDO>N OF UNIT ON THE ORDER OF THE NRC.
l l
l..... l l
l l
l l
l l
l 719.0 l l
l l
l l
til (El III 141 F - FORCEO REASON HETH00 EXHIBIT 0 - INSTRUCTION 3 S. SCHEDULED A. [QUIPHENT FAILURE (EXPLAIN) 1 HANUAL FOR PREPARATION OF DATA B. HAINTENANCE OR TEST E - NAPAJAL SCRAM.
INTRY $HEETS FOR LICEtCtt C - REFUELING 5 = AUTOHATIC LCRAH.
EVtHT REPORT ILER)
D = REGULATORY RESTRICTION 4. OTHER (EXPLAIN)
FILE INURt0 0161)
E - OPf RATOR TR4tNING e LICEidt EXAMINATION F
ADMINISTRATIVE 151 0. OPERATIONAL ERROR lEXPLAINI H. OTHERitXPLAIN)
LXHIBIT I. SAME GOURCE u
F
+
PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. DOX 8699 PHILADELPHI A. PA.191o1 t
May 15, 1987 2im e4i.4ooo 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 April, 1987, forwarded pursuant to Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
Very truly yours,
[//upy' <, -
. Alden W.
ineer-In-arge Licensing Section Nuclear Support Department 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. J. Clark, NRC Project Manager Thomas Magette, Maryland Power Plant Siting INPO Records Center i
t