ML20138B680
| ML20138B680 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/30/1985 |
| From: | Alden W, Logue R PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8510210299 | |
| Download: ML20138B680 (12) | |
Text
AVCAGE DAILY UNIT POWE3 LEVEL CDCKET HO. 50 - 277 LMIT PEACH BOTT0t1 LNIT 2 DATE OCTOBER 15.1985 COMPANY PHILADELPHIA ELECTRIC COMPANY W.M.ALDEN ENGINEER.IN-CHARGE LICENSING SECTION NUCLEAR GENERATI0H DIVISION TELEPHONE (2153 841-5022.
MONTH SEPTET 2ER 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL iPWE-NET)
(NWE-NETI 1
1000 17 1023 2
2006 18 1025 3
1029 19 882 4
1028 20 0
5 1028 21 0
6 1024 22 0
7 1029 23 0
8 1027 24 0
9 1022 25 0
10 1026 26 0
11 1024 27 0
12' 1922 28 0
13 1028 29 0
14 1929' 30 0
15 987 16
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8510210299 850930 PDR ADOCK 05000277
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AV GAGE DAILY UNIT POWE2 LEVEL DOCKET NO. 50 - 278 tMIT PEACH BOTTOM UNIT 3 I
DATE OCTOBER 15.1985 CortPANY PHILACELPHIA ELECTRIC C0rtPANY W.M. ALDEN ENGINEER-IN-CHAEGE LICENSING SECTION MJCLEAR GENERATION DIVISION TELEPHONE (2151 841-5022 MONTH SEPTENER 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
( todE-NET )
(tWE-NET) 1 0
11 0
2 0
18 0
3 0
19 0
4 4
0 20 0
5 0-21 0
6 0
22 0
7 0
23 0
O O
24 0
9 0
25 0
10 0
26 0
11 0
27 0
i 12 0
28 0
13 0'
29 0
14 0
30 0
15 0
i 16 0
i a
-e-.
OPEIATING DJ.TA CEPORT 4
DOCKET HO. 50 - 277 5
DATE DCTOBER 15.1985 i
COMPLETED BY PHILADELPHIA ELECTRIC COMPANY Y
W.M.ALDEN I
ENGINEER-IN-CHARGE LICENSING SECTION NUCLEAR GENERATIDH DIVISIDH TELEPHONE (215) 841-5022 t
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OPERATING STATUS
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- 2. REPORTING PERI 001 SEPTEMBER, 1985 l
SCHEDULED LOAD REDUCTIONS.
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- 3. LICENSED THERMAL POWERittdTit 3293 l
APO ONE FORCED MANUAL l
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- 4. NAMEPLATE RATING E GROSS MWEls 1152 i
SHUTDOWN.
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- 5. DESIGN ELECTRICAL RATING (NET MWEls 1065 l
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- 6. MAXIMUM DEPEND ABLE CAPACITY (GROSS MWEll 1058 l
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- 7. MAXIMUM DEPENDABLE CAPACITY (HET MWEls 1031 l
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- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEMS Hut 2ER 3 THROUGH 7) SINCE LAST REPORT. GIVE REASONS:
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- 9. POWER LEVEL TO WHICH RESTRICTED IF ANY (HET MWEls 5
- 10. CEASONS FOR RESTRICTIONS. IF ANY:
+
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THIS MONTH YR-TO-DATE CUMULATIVE f
i
- 11. HOURS IN REPORTING PERIOD 720 6.551 98.543
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 453.9 1.485.2 63.768.8 I
- 13. REACTOR RESERVE SHUTDOWN HOURS
~ 0.0 0.0 0.0 I
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- 14. HOURS GENERATOR OH-LINE 453.9 1.229.6 61.766.2 l
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GROSS THERMAL ENERGY GENERATED IMWH) 1.477.464 3.553.608 181.973.609 l
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- 17. GROSS ELECTRICAL ENERGY GENERATED (MWHI 480.800 1.099.330 59.817.990 l
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- 18. NET ELECTRICAL ENERGY GENERATED IMWH) 458.555 991.254 57.253.592 l
- 19. UNIT SERVICE FACTOR 63.0 18.8 62.7 I
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20.' UNIT AVAILASILITY FACTOR 63.0 18.0 02.7
- 21. UNIT CAPACITT FACTOR (USING ttC NET) 60.6 14.4 55.3
- 22. UNIT CAPACITT FACTOR (USIt4G DER NET) 59.8 14.2 54.6
- 23. LMIT FORCED OUTAGE RATE 37.0 -
31.2 13.0
' 20. SHUTD06445 531EDULED OVER NEXT 6 NONTHS (TYPE, DATE. AM) DURATION OF EACH):
- 25. IF SHUTD0684 AT END OF REPORT PERIOD, ESTIMATED OATE OF STARTUP8 10/4/85
- 26. 04ITS IN TEST STATUS (PRIOR TO Core 1ERCIAL OPERATION):
FORECAST ACHIEVED INITIAL CRITICALITY INITIAL ELECTRICITY Cort 1ERCIAL OPERATION L
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OPERATING CATA CEPORT DOCKET NO. 50 - 278
===- _ __...................
DATE OCTDBER 15.1985 COMPLETED BY PHILADELPHIA ELECTRIC COMPANY
___=.
W.M.ALDEN
[NGINEER-IN-CHARGE LICENSING SECTICH PAJCLEAR GENERATION DIVISIDH
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TELEPHONE (2151 841-5022 OPERATING STATUS
- 1. WIT HAME: PEACH BOTTOM WIT 3 i NOTES: UNIT 3 CONTINUED ITS SIXTH l
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- 2. EEPORTING PERIDO: SEPTEMBER 1985 l
REFUELING AFC MAINTENANCE l
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- 3. LICENSED THERMAL POWERIMWT):
3293 l
OUTAGE.
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- 4. NAMEPLATE RATING (GROSS MWE ):
1152 l
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- 5. DESIGN ELECTRICAL RATING INET MWE):
1065 I
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- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWE): 1098 l
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- 7. MAXIMUN DEFENCABLE CAPACITY (HET MWEl:
1035-I l
- 8. IF CHANGES OCCUR IN CAPACITY RATINGS (ITEttS Ntk1BER 3 THROUGH 73 SINCE LAST REPORT. GIVE REASONS:
- 9. POWER LEVEL 70 befICH RESTRICTED. IF ANY (HET PldEl:
- 10. REASONS FOR RESTRICTIONS. IF ANY:
i THIS MONTH YR-TO-DATE CUMULATIVE I
- 11. HOURS IN REPORTING PERIOD 720 6.551 94.439
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL 0
4.055.7 68.613.2
- 13. EEACTOR RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 14. HOURS GENERATOR OH-LINE 0.0 3.989.3 66.854.4
- 15. UNIT RESERVE SHUTDOWN HOURS 0.0 0.0 0.0
- 16. GRDSS THERMAL ENERGY GENERATED (MWH) 0 10.796.856 194.996.664
- 17. GROSS ELECTRICAL ENERGY GENERATED IMWH 3 0
3.466.130 63.993.670
- 18. NET ELECTRICAL ENERGY GENERATED (MWH3
-9.529 3.303.199 61.412.501
- 19. UNIT SERVICE FACTOR 0.0 60.9 70.8 T
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- 20. L94IT AVAILABILITY FACTOR 0.0 60.9 70.8 21.. WIT CAPACITY FACTOR (USING MDC NET) 0.0 48.7 62.8
- 22. UNIT CAPACITT FACTOR (USING DER NET) 0.0 47.3 61.1
- 23. L941T FORCED OUTAGE RATE 0.0 0.8 7.1
- 24. SHUTD0544S SCHEDULED DVER NEXT 6 MONTHS ETYPE, DATE. AND DURATIDH OF EACHl:
SCHEDULED SHUTD0644 FOR REFUELING APG MAINTENANCE OUTAGE.
STARTED T/14/85
- 25. IF SHUT 00144 AT DC OF REPORT PERICO. ESTIMATED DATE OF STARTUP: 12/1/85
- 26. WITS IN TEST STATUS (PRIOR TO CON 1ERCIAL OPERATIOHl:
FORECAST ACHIEVED INITIAL CRITICALITY t
INITIAL ELECTRICITY CON 1ERCIAL OPERATION o. NEGATIVE VALUE REFORTED FOR CONSISTENCY WITH FEDFf:AL ENERGY REGULATORY Cort 1ISSIDH REPORTS.
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r LNIT SHUTDOWHS AND POWER REDUCTIONS DOCKET NO. 50 - 277 UNIT HAME PEACH BOTTOM UNIT 2
=_-.........__...
DATE OCT06ER 15 1985 REPORT MONTH SEPTEMBER, 1985 COMPLETED BT PHILADELPHIA ELECTRIC COMPANY
[
W.M.ALDEN
[
ENGINEER-IN-CHARGE LICENSING SECTION HUCLEAR GENERATIDH DIVISIDH TELEPHONE (215) 841-5022
[
_............__..........___.__................................==_-
_...........=== =_._= =...................
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l NETH00 CF l LICENSEE lSYSTEtilCOMPONENTl CAUSE AND CORRECTIVE
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l l TYPE l DUR ATIDH I R E ASON I SHUTTING DOWH 1 EVENT l CODE I CODE-I ACTION TO
..l DATE i (Ill.(HotESil. (2) l REACTOR (3) l REPORT 8 I (4) I
( 5')
l PREVENT RECURRENCE
_==..._
-- =__
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I 37 l 850915 l S l 000.0 l B l 4
i N/A l. CB l PIPEXX l LCAD REDUCTICH TO 945 MWE FOR MODIFICATI0H/
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l TESTING (RECIRC. PIPE REPLACEMENT).
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i 18 l 850916 i S l 000.0 l B l 4
I N/A I
RC. l ZZZZZZ l LO14 REDUCTION TO 800 MWE FOR R00 PATTERN l
l l
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l 1 ATJUSTMENT.
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i 19 l 850919 l F l 266.2 l A l 1
1 2-85-19 l CF l PUMPXX l TECH. SPEC. REQUIREC SHURDC544 DUE TO E-2 l
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l l DIESEL GENERATOR OUTAGE FOR ALTERNATE SHUTDOWN I
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l TESTING. WITH COINCIDENT LPCI PUMP CAPACITY l
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1 l D7FICIENCY (2A RHR PUMP).
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I 266.2 I i
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(1)
(2)
(3)
(4)
{-FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS j - SCHEDULED
' A - EQUIPMEhT FAILURE (EXPLAIN) 1 - MANL'4L FOR PREPARATI0H OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRY SHEETS FOR LICENSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER)
D - REGULATORY RESTRICTIDH 4 - OTHER (EXPLAIH)
FILE (HUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIDHAL ERROR (EXPLAIN)
H - OTHER(EXPLAINI EXHIBIT I. SAME SOURCE L.
LA4IT SHUT 00644S Ate POWER REDUCTIONS DOCKET NO. 50 - 278 UNIT NAME PEACH BOTTOM UNIT 3 DATE OCTOBER 15.1985 REPORT MONTH SEPTEtt1ER. 1985 COMPLETED ST PHILADELPHIA ELECTRIC COMPANT W.M.ALDEN ENGINEER.IN-CHARGE LICENSING SECTION NUCLEAR GENERATION OIVISION TELEPHONE t215) 841-5022 l
l l
l l NETH00 0F l LICENSEE 151STEMlCOMPONENTl CAUSE AND CORRECTIVE l
lTTPElDURATIONlREASONISMUTTING 006H1 EVENT l CODE l CODE l ACTION TO I OATE l ill! (HOURSil (2) l REACTOR (3) I REPORT 8 l (4) I
- 15) l PREVENT RECURRDiCE I
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1 1
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.3 1 850901 l $ l 720.0 l C l 1
l N/A l RC l REFUEL l SHUTDOWN FOR SIXTH REFUELING / MAINTENANCE OUTACt i
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1 720.0 l l
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(1)
(2)
(3)
(4)
- FORCED REASON METHOD EXHIBIT G - INSTRUCTIONS
. SCHEDULED A - EQUIPMENT FAILURE (EXPLAIN) 1 - MANUAL FOR PREPARATI0H OF DATA B - MAINTENANCE OR TEST 2 - MANUAL SCRAM.
ENTRf SHEETS FOR LICDiSEE C - REFUELING 3 - AUTOMATIC SCRAM.
EVENT REPORT (LER) 0 - REGULATORY RESTRICTION 4. OTHER (EXPLAIN)
FILE INUREG-0161)
E - OPERATOR TRAINING + LICENSE EXAMINATION F - ADMINISTRATIVE (5)
G - OPERATIONAL ERROR (EXPLAIN)
H - OTHER(EXPLAIN)
EXHIBIT I - SAttE SOURCE I
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4
Paach Bottom Atomic Power Station Narrative Summary of Operating Experiences.
Septcmbar, 1985 Unit 2 The unit began the month of September operating at full power, and continued full power operation until September 19.
On September 19, the unit was removed from service due to deteriorating performance of the 2A Residual Heat Removal
( RHR) system pump, coincident with the E-2 diesel generator being out-of-service.
Investigations were conducted to determine why the pump did not meet Technical Specification flow requirements.
The investigation continued through the end of the month.
On September 23 while the unit was shutdown for 2A RHR pump testing, high conductivity was detected in a reactor water sample.
A leak was found.in the 2B RHR heat exchanger.
The gasket on the floating head was replaced to remedy the leak.
Unit 3 Unit 3 continued its sixth refuel outage through September.
The fuel inspection program was completed at the end of August.
Instead of purchasing new fuel bundles, defective fuel pins have been replaced to provide 101 reconstituted fuel bundles for the next operating cycle.
As of the end of September, 131 of 132 RHR and recirculation system pipe welds have been inspected.
Results have identified 39 with crack indications.
20 of these have been accepted as-is for use during the next operating cycle, based on a fracture mechanics analysis.
19 of the welds must be overlay repaired.
All 10 recirculation safe ends have crack indications in the thermal sleeve to safe end crevice area.
Continued operation through the next cycle is justified based on crack growth analysis.
Currently, it is planned to replace the ten N-2 nozzle safe ends during the 1987 refueling outage.
Core spray piping inspection revealed pipe cracking at one of the two junction boxes just inside the reactor vessel.
Identical weld bracket repairs will be made to both junction box arrangements to assure continued safe operation.
Crack-indications have also been found on both sides of a weld in the heat af fected zone of one of the two recirculation suction pump inlet safe ends.
Excessive cold working of the safe end during construction fit-up is thought to be the cause of this unexpected cracking.
Repair methods are currently being evaluated.
These findings were discussed with the NRC technical staf f on September 19, 1985.
All 12 SRM and IRM dry tubes have been replaced as a result of cracking detected in the upper region near the spring
(
assembly.
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Docket No. 50-277 Attachmsnt to Monthly Operating Report for September, 1985 REFUELING INFORMATION 1.
Name of facility:
Peach Bottom Unit 2 2.
Scheduled date for next refueling shutdown:
November 15, 1986 3.-
Scheduled date for restart following refueling:
January 31, 1987 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 September 26, 1986.
6.
Important licensing considerations associated with refueling, e.g., new or dif ferent fuel design or supplier, unreviewed design or performance analysis methods, signi ficant 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 - 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:
Tne spent fuel pool storage capacity has been relicensed for 2816 fuel assemblies.
A request for approval of replacement higher density fuel racks was submitted to the NRC on June 13, 1985 which will increase the fuel pool capacity to a total of 3819 fuel bundles in each fuel pool.
9.
The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.
i l
March, 1991 (September, 1986, with reserve full core discharge)
Docket No. 50-278 Attachment to Monthly Operating Report for September, 1985 REFUELING INFORMATION 1.-
Name of facility:
Peach Bottom Unit 3 2.
Scheduled date for next refueling shutdown:
July 14, 1985 3.-
Scheduled date for restart following refueling:
December 1, 1985 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:
MAPLHGR Limits Submitted January 7, 1985 Additional Core Limit Information - April 12, 1985 6.
Important licensing considerations associated with refueling, e.g., new or dif ferent 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 - 1212 Fuel Assemblies, 6 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 2816 fuel assemblies.
A request for approval of replacement higher density fuel racks'was submitted to the NRC on June
~
13, 1985 which will increase the fuel' pool. capacity to a total of 3819 fuel bundles in each fuel pool.
l 9.
The projected date of the last refueling that can be discharged to l
the spent fuel pool assuming the present licensed capacity.
March,-1992 (March, 1987 with reserve for full core discharge)
L
PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA. PA.19101 12158 e4i.4ooo October 15, 1985 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 September, 1985 forwarded pursuant to Technical Specification 6.9.1.C under
~
the guidance of Regulatory Guide 10.1, Revision'4.
Very truly rs, J '/~
R.
H.
Logue Superintendent Nuclear Services 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)
Mr. Thomas Magette, Maryland Power Plant Siting t
INPO Records Center i
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