ML20116K579
| ML20116K579 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/31/1992 |
| From: | Broughton T, Heysek W GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| C311-92-2149, NUDOCS 9211170265 | |
| Download: ML20116K579 (10) | |
Text
N g s
[ O-GPU Nuclear Corporation gg gf Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 '
717 944 7621-TELEX 84 2386 Writer's Direct L,41 Number:
(717) 948-8005 November 12, 1992 C311-92-2149 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Monthly Operating Report for October 1992 Enclosed are two. copies of the October 1992 Monthly Operating Report for Three Mile Island Nuclear Station, Unit 1.
Also included are amended Operating Data Report and Average Daily Power pages for the month of September.1992.
The-pages correct data inaccuracies contained in the September 1992 submittal that resulted from an intermittent malfunction of the plant watt hour meter.
Sincerely, Y
T. G. Bro ghton Vice President and Director, THI-l WGH Attachments cc: Administrator, Region I THI Senior Resider.t Inspector 170011
- PDR ADOCK 05000289
-h 9211170265 921031 R
PDR GPU Nuclear Corporation is a subsidiary of Generai Pubhc Utihties Corporation
OPERATIONS
SUMMARY
OCTOBER 1992 The plant entered the month of October operating at 100% power producing 860
- MWe, It continued full power operation for the entire period and closed the month producing 860 MWe.
MAJOR SAFETY RELATED MAINTENANCE During October, the following major safety related maintenance was performed:
Boric Acid Tank Mixer CA-M-1 Boric Acid Tank Mixer CA-M-1 was removed from service to replace a sheared drive shaft taper pin.
Upon completion of the work, the mixer was satisfactorily tested and returned to service.
Fire Service System Altitude Tank FS-T-1 Altitude Tank FS-T-1 was removed from service in order to accomplish a level switch replacement modification and perform various corrective maintenance tasks.
The corrective maintenance tasks accomplished included: replacement of valves FS-V-83 A/B/C, FS-V-278, FS-V-1007 and FS-V-1226 with ball valves, replacement of recirculation pump FS-P-6,- replacement of valte FS-V-6 with a flanged tee, _ and repair as necessary of the 6" and 12" piping with welded contoured plate. Additionally, heater elements FS-C-1, FS-C-2, and FS-C-3 were replaced, and a new 24 inch ball valve was installed in the heater recirculation piping._ Because of flow restrictions in the Altitude Tank-piping, a contractor was brought on-site to perform high pressure water blasting to clean the 12" discharge pipe, the 6"_ filter water supply pipe,-and the 2)" heater recirculation pipes.
Painting and level switch. calibration continue and the tank is expected to be returned to service in November.
Intermediate Closed Coolina Water Pume IC-P-1A Intermediate Closed Cooling Water Pump IC-P-1A_was taken out of service 1because of noisy motor bearings. The motor and pump' internals were removed and taken to the shop for repairs.
In the shop, a new pump shaft was-fitted and pinned to a new, replacement motor. The pump rotating assembly was installed along with a new mechanical seal. The motor / pump: assembly was reinstalled and after being satisfactorily tested, IC-P-1A was returned to service.
2
Waste Gas System Check Valve WDG-V-41 WDG-V-41, the Waste Gr: Decay Tank inlet check valve was removed from service because of seat leakage.
An inspection of the disassembled valve revealed that the disc was sticking in the bonnet guide. The parts were cleaned and the valve reassembled. WDG-V-41 was returned to service after being satisfactorily tested.
Sample Isolation Valve CA-V-2 Reactor Coolant sample isolation valve CA-V-2 was removed from service because of leakage at the to bonnet-to-body gasket.
The operator air lines-and limit switches were removed and the operator / bonnet assembly was lifted from the valve body to gain access to the gasket seating surfaces. The surfaces were cleaned and a new bonnet gasket was inserted prior to reinstalling and torquing the operator / bonnet assembly.
The operator air-lines and limit switches were reconnected.
CA-V-2 was returned to service after completion of a satisfactorily local leakrate test.
3
4 -'
i OPERATING DATA REPORT DOCKET NO.
50 289 DATE N0vember 12, 1992
. COMPLETED.BY W G HEYSEK-
. OPERATING STATUS TELEPHONE (717). 948 8191-
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 ' NOTES:
l 2, REPORTING PERIOD:
OCTOBER 1992 l.-
3.
LICENSED THERMAL POWER:
2568 l
4.
NAMEPLATE RATING (GROSS MWe):
871 l
-l
- 5. DESIGN ELECTRICAL RATING (NET MWe):
819 l l~
- 6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe) :
834 l l
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
786 l
-l l
l
- 8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
- 10. REASONS FOR RESTRICTIONS, IF ANY:
THIS MONTH YR-TO DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD (HRS) 745.0 7320,0 159241.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 745.0 7281.8 84012.8
- 13. REACTOR'RESEtVE SHUTDOWN HOURS (HRS)-
0.0 38.2 2283.8
- 14. HOURS GENERATOR ON-LINE (HRS) 745.0 7279.0
-82935.2
- 15. UNIT r.ESERVE SHUTDOWN HOURS-(HRS)-
0.0 0.0-0.0
-16. GROSS THERMAL ENERGY GENERATED:
(MWH) 1910592
.18517951'- '202386996 17.. GROSS ELECTRICAL ENERGY GENERATED (MWH) 636326 6124904 68119163 18.: NET ELECTRICAL ENERGY GENERATED (MWH) 601021 5779255 63936580
- 19. UNIT SERVICE FACTOR
(%)
100.0 99.4 5221
- 20. UNIT AVAILABILITY FACTOR
(%)
100.0 99.4-52.1
- 21. UNIT CAPACITY FACTOR (USING MDC NET) 102.6 100.4
.51.1 -
-22. UNIT CAPACITY FACTOR (USING DER NET) 98.5-96.4' 49.0 23.. UNIT FORCED' OUTAGE-RATE
(%)~
0.0
.0.6' 42.3'-
- UNIT FORCED OUTAGE HOURS
-(HRS) 0.0 41.0--
60689.7-i=
24.1 SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE, DATE AND DURATION OF EACH) :
- 25. IF SHUT DOWN AT END OF REPORT PERIOD, ESTIMATED DATE OF STARTUP:
i 4
w
AVERAGE DAILY. UNIT POWER LEVEL DOCKET NO.
50-289 UNIT TMI 1-DATE November 12, 1992 COMPLETED BY W G HEYSEK TELEPHONE (717) 948-8191 MONTH:
OCTOBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL-(MWe NET)
(MWe-NET) 1 807 17 814 2
803 18 819 3
799 19 818 4
801 20 821 5
807 21 815 6
808 22 816 7
806
.23 815 8
801 24 806 9
790 25 811 10 797 26 810 11 799 27 809 12 801 28 810 13 802 29 807 14 803 30 805 15 799 31 809 16 801 5
+-
UNIT SHUTDOWNS AND PCHER REDUCTIONS DOCKET NO.
50-289 UNIT NAME TMI-1 REPORT MONTH October 1992 DATE November 12, 1992 COMPLETED BY W. G. Heysek TELEPHONE (717) 948-8191 Methoc of Licencee system :onponent Cause & Corrective i
No*
Date Type' Duration Reason
- Sht.
3 Event Code Code Action to (Hours)
Dow,e Report #
Prevent Recurrence Reactor' NONE 2
3 4
F Forced Reason Method Exhibit G - Instructions for S Schedated A iquipment Failure (Explain) 1-Manust preparation of Data Entry Sheets B-Maintenance or Test 2-Manueil Scram for Licensee Event Report (LER)
C-Refueling 3-Autoratic Scram File (NUREG-0161)
D-Regulatory Restriction 4-Other (Explain)
E-Operator Tra*ning & t.icensing Examination 5 Exhibit 1 same sot.rce F-Adninistrative G-Operationtt Irror (Explain) 6 Actustly used exhibits F & II WJREG 0161 H-Other (Explain) 6
7 - --.
~
REllILING INFORMATION RE0 VEST 1.
Name of Facility:
Three Mile Island Nuclear Station, Unit 1 P
2.
Scheduled date for next refueling shutdown:
September 17, 1993 (10R) 3.
Scheduled date for restart following current refueling: NA 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? YES In general, these will be:
a)
Technical Specification Change Request (TSCR) No. 212 requesting'"an increase of the allowable enri:hment of fresh fuel to 5.0 wt/o U was submitted August 25, 1992. The TMI-1 Senior Project Manager-comitted to completir.g approval prior to January 1,_1993.
b)
TSCR No. 220 requesting approval to move the Maximum Allowable LOCA Linear Heat Rate. Limits (T.S. Figure 3.5-2M) to the Core Operating _
Limits Report was submitted on October 29, 1992-c)
Use of gadolinia-urania fuel and B&W Fuel Corporation (BWFC) changes in core physics methods will require change to T.S. 6.9.5.2 which lists approved analytical methods references to support the core Operating Limits Report values.
Changes will include-reference to BAW-10180, Rev. 1, NEMO and BAW-10184P, GDTACO methods (see #6, Item 1,below). Use of the gadolinium integral burnable poison may also require changes to the Reactor Core fuel descriptions in T.S. 5.3.1.
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
Submittals made to date are described in 4a and b above. -The TSCR-submittal schedule for use of the gadolinia-urania fuel will depend -
on completion of the USNRC review of-the applicable BWFC methods addressed in 4c above. Per recent discussions,_NEMO, Rev. 1-approval is expected prior to January 1, 1993 and the review of GDTACO is expected in May 1993.
B1 sed on these expected approval dates, the GPUN TSCR would be submitted in June 1993.
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:
a)
BWFC and GPUN are now performing tM fuel cycle design for cycle 10, which is scheduled for startup in ber 1993. This design-incorporates reload fuel that cor.
gadolinia-urania.
Use of this type of fuel will require cht
.. to the plant Technical-Specifications as noted in 4c above. These changes will need to be i
supported by approval of BWFC topical reports on reload design l
methods revisions that account for the'Gd effects in the analyses; L
noted in 5 above. To ensure that no delays occur to reload analyses, fuel manufacturing and plant startup schedules, approval of these topicals has been requested for April 1,1993.
b)
TM1-1 will use the new Mark 09 fuel assembly in the Cycle 10 reload
)
batch.
This design is an upgrade of the Mark B8 assetily used in Cycles 8 and 9.
The Mark B9 provides improved fuel thermal limits (LOCA, DNBR, CLM) and repair capabilities. The Mark B9 design meets current BWFC fuel design criteria and has been previously used at other B&W 177 FA plants.
c)
BWFC has several licensing changes under USNRC review. Changes are necessary to upgrade their shipping containers for shipment of fuel up to 5 wt/o U. These changes are necessary to support the TM1-1 Cycle 10 refueling schedule.
Approval of the B&W Model B fuel assembly shipping" container for shipment of single assemblies from 4.6 to 5.1 wt/o U ' is expected in January 1993.
Approval of the SiemensfuelassemblyshippggcontainerfortwoBWFCMarkBfuel assemblies up to 5.0 wt/o U is expected in March 1993.
7.
The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool:
(a) 177 (b) 521 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 present licensed capacity is 1991.
Phire 1 of the reracking project to increase spent fuel pool storage capacity permits storage of 1496 assemblies. Upon completion of Phar.) 11 i ! the reracking project, the full licensed capacity will b. atteined.
9.
The projected date of the last refueling that can be discharged t spent fuel pool assuming the present licensed capacia:
Completion of Phase 1 of the reracking project permits full core off-load (177 fuel assemblies) through the end of Cycle 13 and on completion of the rerack project full core off-load is assured through the end of the current operating license and beyond.
t 4
{
CORRECTED COPY OPERATING DATA REPORT I
DOCKET NO.
50 289 DATE October 13. 1992 COMPI.ETED BY W G HEYSEK OPER4 TING STA7VS TELEPHONE (717) 948 8191 f
- 1. UNIT NAME:
THREE MILE ISLAND UNIT 1 l NOTES:
l
- 2. REP ^ttTING PERIOD:
SEPTEMBER 1992 l
j
- 3. LIC iSED THERMAL POWER:
2568 l THIS AND THE FOLLOWING PA'JE 4.
!UsMEPLATE RATING (GROSS MWe) :
871 l INCLUDE CORRECTIONS TO ITEMS l
- 5. DESIGN ELECTRICAL RATING (NET MWe) :
819 l 17, 18, 21, 22, & THE AVERAGE l
- 6. MAXIM 0M DEPENDABLE CAPACITY (GROSS MWe) :
834 i DAILY POWER LEVEL FOR 03 03 92. l
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe):
78G l l
I I
- 8. IF CHANGES OCCUR IN (ITEMS 3 7) SINCE LAST REPORT, GIVE REASONS:
- 9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MWe):
t i t.. REASONS FOR RESTRICTIONS, IF ANY:
i THIS MONTH YR TO*DATE CUMMULATIVE
- 11. HOURS IN REPORTING PERIOD (HRS) 720.0 6575.0 158496.0
- 12. NUMBER OF-HOURS REACTOR WAS CRITICAL (HRS) 681.8 6536.8
=83267.8
- 13. REACTOR RESERVE SHUTDOUN HOURS (HRS) 38.2 38.2 2283.8.
- 14. HOURS GENERATOR ON LINE (HRS) 679.0 6534.0 82190.2
- 15. UNIT RESERVE SHUTDOWN HOURS (HRS) 0.0 0.0 0.0-
- 16. GROSS THERMAL ENERGY GENERATED (MWH) 1591955 16607159
.200476404-17, 3ROSS ELECTRICAL ENERGY GENERATED (MWH) 516394 54 8 8 r.78 67482837
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 483704 5178234 63335559 19-UNIT SERVICE FACTOR
(%)
94.3 99.4 51.9
- 20. UNIT AVAILAB*iLITY FACTOR
(%)
94.3 99.4 51,9 21.. UNIT CAPACITY FACTOR' (USING MDC NET) 85.5-100.2
.50.8
- 22. UNIT CAPACITY FACTOR (USING DER NET) 82.0 96.2 48.8
- 23. UNIT FORCED OUTAGE RATE (t) 5.7 0.6
'42.5 UNIT FORCED OUTAGE HOURS
_ (HRS )
41.0 41.0 60689.7
- 24. SHUTDOWNS SCHEDULED OVER NEXT 6 MCNTHS -(TYPE, DATE AND DURATION OF EACH):
- 25. IF SHUT DOWN AT END OF REPORT. PERIOD, ESTIMATED DATE OF STARTUP:
4 1
rr--.
<.~
v m
..,.e,
.r
..,,.,, ~ - - -.
,, ~ -.. -. -
r-y,.
i,... s o
. 0, CORRECTED COPY i
AVERAGE DAILY UNIT POWER LEVEL I
DOCKET NO.
50 289 UNIT TM1 1 DATE 0ctober 13, 1992 COMPLETED BY W G HEYSEK l
TELEPHONE (717) 948-8191 I
MO!U'H SEPTEMBER DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL r
(MWe NET)
(MWe NET) 1 334 17 776 1
340 18 555
+
3 341 19 39 4
344 20 160 5
688 21 782 6
"91 22 787 I
7 788 23 804 8
783 24 809 9
783 25 807
-10 776 26 800 11 789 27 793 12 797 28 799 13
.795 29 804 14 793 30 809 i
15 788 31 NA 16 779 i
1 c
e P
L
'5
..; _, u.
., ~