ML20237K556
| ML20237K556 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 07/31/1987 |
| From: | Alden W, Middleton L PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| NUDOCS 8708190309 | |
| Download: ML20237K556 (14) | |
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l PeachsBottom Atomic Power Station s
Narrative Summary of Operating Experience July, 1987 O
UNIT 2 Unit 2 continued its seventh refueling outage through the month of July.
Fuel reload was completed on July 1, and core verification was completed en July 2.
By July 28, reactor vessel interval assembly was completed, and reactor vessel head installation and tensioning were completed by July 31.
On, July 10, a fuse failure deenergized the System IIB Residual Heat' Removal System Logic Bus, resulting in a Primary Containment laclation of Shutdown Cooling.
The cause of the fuse failure could not be determined; however, the fuse was replaced and the isolation was reset.
s AlEo on July 10, a lightning strike caused protective relay action which tripped the #3 Startup Feed Breaker.
The loss of
'the #3 $tartup, Feed caused fast transfers of Emergency Buses E13, E22, E33, and E42, and deenergization of the #2 and #3 unit auxil,iary buse's, resulting in Primary Containment Isolation System actuationsL(due to the fast transfers) and interruption of Service Water (due'to pump trips caused by loss of #2 and #3 unit i
auxiliary buses) for both Unit 2 and 3.
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On July 28, the E322 breaker, which feeds Emergency Bus E22, tripped ooen thus causing the E222 breaker to close.
The subsequent three-second deenergization caused a partial actuation of the Primary containment lToolation System including Shutdown Cooling and Reactor Water CJeanup.
It is believed that a protective relay may have b?en jarred by personnel working in the area, initiating a spurious relay trip.
The isolations were reset within five minutes.
e On July 31, personnel involved in excavation in the West Yard behind the Radwaste Building inadvertently ruptured the fire system header piping to the Radwaste Building.
The automatic start of'both purps was manually defeated to facilitate pipe repair.
The pipe repairs were completed and both fire pumps were returned to service that same day.
Up,it 3 Unit 3 remained shutdown through July in accordance with the NRC's Order.
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8708190309 870731
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lPOR. ADOCK 05000277 R
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Docket'No. 50-277 Attachment to Monthly Operating Report for July, 1987 t
r UNIT 2 REFUEL NG INFORMATION
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.e 1.
Name of facility:
Peach Bottom Unit 2 s
2.
Scheduled date for next refueling shutdown:
i Reload 7 in progress 3.
iScheduled date for restart following refueling:
(Indeterminate due'to Shutdown Order i
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Will refueling or resumption of operation thereaf ter require a d
technical specification change or other license amendment?
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t iq Yes
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If answer is,yes, whab,;;in general, will these be?
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T3chnical Specifications to accommodate reload fuel.
o Modifications to reactor core opersting limits.
'(,t5.\\,Ssupporting information:for submitting proposed licensing action and j
Scheduled date(s)
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Reload 8 license amendment to be submitted January 1989.
6.
Important licensing considerations associated with refuelirig, i,e.g., new or different fuel design or supplier, unreviewed design s y or performance analysis methods, significant ' changes in fuel design, new opera (ing procedures:
s None expected.
7.
The number of fuel assemblies (a) in the core ano (b) in the fuel 'torage pool:
spent S
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(a) Core - 764 Fuel Assemblies, Core Offloaded During Outage i s'1 s N )
(b) Fuel Pool - 1462 Fuel't Assemblies, 58 Fuel Rods l
3 8.
The present>1icensed spent fuel pool storage capacity and the l
size of any increase in licensed storage capacity that has been requested er is planned, in number of fuel assemblies:
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,The spect fuel pool storage capacity has been relicensed for 3819 fuel assemblies.
Replacement higher density fuel racks s3,,
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were, approved by the NRC on February 19, 1986 which
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incesases the licensed fuel pool capacity to a total of 3819 fuel bundler in each fuel pool.
This modification was s
completed on' November 15, 1986.
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I l-Docket No. 50-277 j
L Attachment to Monthly Ope: rating Report'for July, 1987 Page 2
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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 l
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Docket ik). 50-278 Attachment to Monthly Operating Report for July, 1987 UNIT 3 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
1 October 17, 1987 (Major Pipe Replacement Outage) 3.
Scheduled date for restart following refueling:
July 9, 1988 4.
W1111 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 March 11, 1988-6.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design 1
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 Poo; - 1496 Fuel Assemblies, 6 Fuel Rods l
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l Docket Noa 50-278 Attachment to Monthly Operating Report for July, 1987 Page 2 i
UNIT 3 REFUELING INFORMATION (Continued) i 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:
i The spent fuel pool storage capacity has been relicensed for.
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3819 fuel assemblies.
Replacement higher density fuel racks 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 FebruaryL 20, 1987.
The completion date for this modification has been rescheduled for~ February, 1987 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 l
the completion of the new fuel racks installation:
l March, 1993 (September, 1987, with reserve full I
core discharge)
-10.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the relicensed capacity, j
subsequent to the completion of the new fuel racks installation:
March, 1999 (March, 1996, with reserve full core discharge)
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AVERACE DAILY LRIIT PCMER LEVEL l
DOCKET No. 50 - 277 UNIT PEACH BOTTOM UNIT 2 DATE COMPAfU PHILADELPHIA ELECTRIC COMPAPU L. L. HICDLETON TECHHICAL ASSISTAtlT LICEHSING SECTION HUCLEAR SUPPORT DEPARTMENT TELEPH0t1E ( 215) 841-6374 NOHTtt JULY 1987 CAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL 01HE-NET I (MHE-NET) f 1
0 17 0
2 0
10 0
3 0
19 0
4 0
20 0
5 0
21 0
4 0
22 0
7 0
23 0
0 0
24 0
9 0
25 0
10 0
26 0
1
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11 0
27 0
12 0
to 0
1 13 0
29 0
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4 14 0
30 0
15 0
31 0
-16 0
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-. - - - - - - _ = _ _ _. - _ - _
1 AVERAGE DAILY UNIT P0HER LEVEL l
l DOCKET NO. 50 - 278 l
j UNIT PEACH BOTTON UNIT 3 l
DATE AUGUST 15,1987 l
COMPA?(t PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHitIC/,L ASSISTANT LICENSING SECTION PAJCLEAR SUPPORT DEPARTMENT TELEPHONE ( 215) 841-6374 MCNTH JU'LY 1987 DAY AVERAGE DAILY P0HER LEVEL DAY AVERAGE DAILY P0HER LEVEL (MHE-NET)
(MHE-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
.i OPERATING DATA REPORT DOCKET No. 50 - 277 DATE AUGUST 15,1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY l
4-L. L. HIDDLETON TECHNICAL ASSISTANT LICEtGING SECTION NUCLEAR SUPPORT DEPARTHENT TELEPHONE (215) 841-6374 q
OPERATING STATUS
- 1. UNIT NAHER PEACH D')TTOH UNIT 2 1 NOTES UNIT 2 REMAINED SHUTD0tN l
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- 2. REPORTING PERIODI JULY, 1987 l
FOR ITL SEVENTH REFUELING l
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- 3. LICENSEDLTHERHAL P0HER(tWris 3293 l
OUTAGE. THE UNIT HILL l
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- 6. NAMEPLATE RATING (GROGS HHE):
1152 l
REMAIN SHLITDOHN IN COMPLIANCE l l
l S. DESIGN ELECTRICAL RATING (NET HNE):
1065 l
HITH THE HARCH 31, 1987 l
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-6, HAXIMUM DEPENDABLE CAPACITY (GROSS HHE): 1098 l
SHUTDOHN ORDER.
l g-l 7.'HAXIMUM DEPENDABLE CAPACI1Y (HET HHE):
1051 l
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- 8. IF CHANGES OCCUR 1H CAPAC1 # RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORT, GIVE REASotGt 9, POHER LEVEL TO HHICH RESTRICTED, IF ANY (HET HHE li
- 10. REASONS FOR RESTRICTIOtG, IF ANY2 ThIS HJNTH YR-TO-DATE CUMULATIVE
- 21. HOURS IN REPORTING PERIOD 744 5,087 114 599
..s..........
- 12. NUMBER OF. HOURS REACTOR HAS CRITICAL 0
1,729.8 74.196.0
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- 33. REACTOR RESERVE SHUTDOHN HOURS 0.0 0.0 0.0
- 16. HOURS GENERATOR OH-LINE 0.0 1,724.0 71.866.8 I
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- 15. UNIT RESERVE SHUTDOFN HOURS 0.0 0.0 0.0 w....
- 16. GROSS THERMAL ENERGY GENERATE 0 (HHH) 0 4,979,376 212,8t0,745
.......~....
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- 17. GROSS ELECTAICAL ENERGY GENERATED (HHH) 0 13648,230 70,019,230
- 28. NET ELECTRICAL ENERGY GENERATED (HHH)
-5,950 1,576,697 67,065,557
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OPERATIM3 DATA REPORT (CONTINUED)
DOCKET HO. 50 - 277 DATE AUGUST 15,1987 THIS N0HTH YR-TO-DATE CUMULATIVE
- 19. UNIT SERVICE FACTOR 0.0 33.9 62.7 f
- 20. UNIT AVAILABILITY FACTOR 0.0 33.9 62.7
- 21. UNIT CAPACITY FACTOR (USING MOC NET) 0.0 29.5 55.7 j
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 29.1 55.0
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- 23. UNIT FORCED OUTAGE RATE 0.0 0.0 13.3
- 24. SHUTDOHHS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)*
REFUELING OUTAGE MARCH 13,1987 TO JULY 19, 1987
- 25. IF SHUT 00 bel AT END OF REPORT PERIODS ESTIMATED DATE OF STARTUPt
- 26. UNITS IN TEST STATUS'(PRIOR TO COMMERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY 09/16/73 INITIAL ELECTRICITY 02/18/74 COMMERCIAL OPERATION 07/05/74 PAGE 2 0F 2 m - N'JG4TIVL VALUE REPORTED FOR CONSISTCHCY HITH FEDERAL ENERGY REGULATORY COMMISSION REPORTS.
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1 OPERATING DATA REPORT DOCKET to. 50 - 278 DATE AUGUST 15,1907 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECilNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE (215) 841-6374 OPERATING STATUS
- 1. UNIT NAME PEACH BOTTOM UNIT 3 l PMTES UNIT 3 REMAINED SHUTDOHN l
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- 3. REPORTING PERIC01 JULY, 1987 l
IN ACCORDANCE HITH THE l
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- 3. LICENSED THERMAL POHER(MHT):
3293 1
MARCH 31, 1987 NUCLEAR l
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- e. NAMEPLATE RATItG (GROSS MHE ):
1152 l
REGULATORY COMMISSION ORDER.
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- 5. DESIGN ELECTRICAL RATING (NET MHE):
1065 l
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- 6. MAXIMUM DEPERDABLE CAPACITY (GROSS MHE)2 1098 l
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- 7. MAXIMUM DEPENDABLE CAPACITY (NET HHE):
1035 l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS NUMBER 3 THROUGH 7) SINCE LAST REPORTS GIVE REAS0tGt
- 9. P0HER LEVEL TO HHICH RESTRICTED, IF ANY (NET MHE):
- 10. REASONS FOR RESTRICTIOtG, IF ANY THIS MONTH YR-TO-DATE CUMULATIVE
- 11. HOURS IN REPORTING PERIOD 744 5,087 110,495
- 12. NUMBER OF HOURS REACTOR HAS CRITICAL 0
1,824.9 76,357.4
- 13. REACTOR RESERVE SHUTDOHN HOURS 0.0 0.0 0.0
- 14. HOURS GCNERATOR OH-LINE 0.0 1,659.6' 73,929.3
- 15. UNIT RESERVE SHUTDOHN HOURS 0.0 0.0 0.0 Ib. GROSS THERMAL ENERGY GENERATED (MHH) 0 4,759,240 215,278,901 I
- 17. GROSS ELECTRICAL ENERGY GENERATED (MHH) 0 1,555,566 70,611,432
- 18. NET ELECTRICAL ENERGY GENERATED (MHH)
-5,950 1,484,503 67,726,596 PAGE 1 0F 2 i
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OPERATING DATA REPORT (CONTINUED)
DOCKET No. 50 - 278 l
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l DATE AUGUST 15,1907 1
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THIS HONTH YR-TO-DATE Ctt0LATIVE
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- 19. UNIT SERVICE FACTOR 0.0 32.6 66.9 l
20, UNIT AVAILABILITY FACTOR 0.0 32.6 66.9
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- 21. UNIT CAPACITY FACTOR (USING MDC NET) 0.0 28.2 59.2
- 22. UNIT CAPACITY FACTOR (USING DER NET) 0.0 27.4 57.6
- 23. UNIT FORCEO QUTAGE RATE 100.0 67.4 11.8
- 24. SHtTTDOHH3 SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE, AND DURATION OF EACH)
INDETERMINATE UNTIL HRC ORDER IS SATISFIED.
I
- 25. IF SHUTDOHN AT END OF REPORT PERIOD. ESTIMATED DATE OF STARTUP i
- 26. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL OPERATION)
FORECAST ACHIEVED INITIAL CRITICALITY 08/07/74 INITIAL ELECTRICITY 09/01/74 COMMERCIAL OPERATION 12/23/74 PAGE 2 0F 2
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UNIT SHUTD0tttS AND P0HER REDUCTI0tG DOCKET NO. 50 - 277 UNIT NAME PEACH BorTOM UNIT 2 LATE AUGUST 15,1987 l
REPORT HONTH JULY, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY L. L. MIDDLETON TECHNICAL ASSISTANT LICENSING SECTION NUCLEAR SUPPORT DEPARTMENT TELEPHONE ( 215) 841-6374 l
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l l METH00 0F l LICEttSEE ISYSTEMICOMPONENTl CAUSE AND CORRECTIVE i
l TYP E l DURATI 0H l RE ASON I SHUTTING DOtel l EVENT l CODE l CODE l ACTION TO NO.I DATE l (lil (HOURS)l (2) l REACTOR (3 ) l REPORT # 1 (4) l (5) l PREVENT RECURRENCE
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I S l 870701 l S l 744.0 i C !
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N/A l RC l FUELXX l SHUTDOHN FOR ITS SEVENTH REFUELING OUTAGE.
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! 744.0 l
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(2)
(3)
(4)
F - FORCED REASCH HETH00 EXHIBIT 0 - INSTRUCTI0tG
@ - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL 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
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UNIT SHUTD0ktG AND P0HER REDUCTIOtG DOCKET to. 50 - 278 UNIT NAME PEACH BOTTOM UtlIT 3 DATE AUGUST 15,1987 REPORT MONTH JULY, 1987 COMPLETED BY PHILADELPHIA ELECTRIC COMPA?f(
L. L. MIDDLETON TECHNICAL ASSISTANT LICEtGItG SECTI0tl NUCLEAR SUPPORT DEPARTMEt4 TELEPHONE ( 215) 841-6374 i
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I l METH00 0F l LICEttiE E ISYSTEHlCOMPONENTl CAUSE AND CORRECTIVE I
ITYPElDURATIONIREASONISHUTTING 00ttil EVENT l CODE l CODE l ACTION T0 to.1 DATE I (lli (HOURS)l (2) i REACTOR (3) l REPORT S I (4) l (5) i PREVEt6 RECURRENCE l
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6 l 870701 1 Fl 744.0 1 0 1 1
i N/A l ZZ l ZZZZ77 i SHUTD0tti 0F UNIT ON THE ORDER OF THE NRC.
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l 744,0 l l
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(2)
(3)
(4)
F - FORCED REAS0tl METH00 EXHIBIT G - ItGTRUCTIONS
@ - SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATION OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICEFGEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT ( LER) l D - REGULATORY RESTRICTION 4 - OTHER (EXPLAIN)
FILE 1NUREG-0161)
E - OPERATOR TRAINING + LICEtGE EXAMINATION i
F - ADMINISTRATE'IVE (5) l l
0 - OPERATIONAL ERROR (EXPLAIN)
H - OTHER( EXPLAIN)
EXHIBIT I - SAME SOURCE l
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l' PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O, BOX 8699 PHILADELPHIA PA.19101 (2isi e414ooo August 14, 1987 Docket Nos. 50-277 50-278 Director I
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Office of Inspection & Enforcement US Nuclear Regulatory Commission Washington, DC 20555 e
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 1987, forwarded pursuant to. Technical Specification 6.9.1.d under the guidance of Regulatory Guide 10.1, Revision 4.
Very truly yours, W. M. Alden Engineer-In-Charge 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.
E.. Martin, NRC Project Manager
-Thomas Magette, Maryland Power Plant Siting INPO Records Center i
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