|
---|
Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 ML20203K4081997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for TMI-1 ML20199E3401997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for TMI-1 ML20198J8121997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for TMI-1 ML20217A8761997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for TMI-1 ML20210K0331997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Three Mile Island, Unit 1 ML20196G8401997-06-30030 June 1997 Monthly Operating Rept for June 1997 for TMI-1 ML20210K0401997-06-30030 June 1997 Revised App B of Monthly Operating Rept for June 1997 for Three Mile Island,Unit 1 Correcting Calculational Error in Shutdown Duration Hours Value ML20141C6521997-05-31031 May 1997 Monthly Operating Rept for May 1997 for TMI-1 ML20141G2801997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for TMI-1 ML20140D6601997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Three Mile Island, Unit 1 ML20136G3891997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Three Mile Island Nuclear Station,Unit 1 ML20134Q2071997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for TMI-1 ML20133G8231996-12-31031 December 1996 Monthly Operating Rept for Dec 1996 for TMI-1 ML20132D5431996-11-30030 November 1996 Monthly Operating Rept for Nov 1996 for Three Mile Island Nuclear Station,Unit 1 (TMI-1) ML20135A8291996-10-31031 October 1996 Monthly Operating Rept for Oct 1996 for TMI-1 ML20129B6621996-09-30030 September 1996 Monthly Operating Rept for Sept 1996 for Three Mile Island Nuclear Station Unit 1 (TMI-1) ML20129C2661996-08-31031 August 1996 Monthly Operating Rept for Aug 1996 for Three Mile Island Nuclear Station,Unit 1 ML20116N6571996-07-31031 July 1996 Monthly Operating Rept for July 1996 for Three Mile Island Nuclear Station,Unit 1 ML20115E2071996-06-30030 June 1996 Monthly Operating Rept for June 1996 for TMI-1 ML20117M1581996-05-31031 May 1996 Monthly Operating Rept for May 1996 for Three Mile Island Unit 1 ML20112A2171996-04-30030 April 1996 Monthly Operating Rept for Apr 1996 for Three Mile Island Nuclear Station Unit 1 ML20117D3691996-03-31031 March 1996 Monthly Operating Rept for March 1996 for TMI-1 ML20101C6811996-02-29029 February 1996 Monthly Operating Rept for Feb 1996 for Three Mile Island Nuclear Station,Unit I ML20149K7551996-01-31031 January 1996 Monthly Operating Rept for Jan 1996 for TMI-1 ML20096D5781995-12-31031 December 1995 Monthly Operating Rept for Dec 1995 for TMI Nuclear Station ML20095E0521995-11-30030 November 1995 Monthly Operating Rept for Nov 1995 for TMI-1 ML20094L7651995-10-31031 October 1995 Monthly Operating Rept for Oct 1995 for TMI-1 ML20093E6731995-09-30030 September 1995 Monthly Operating Rept for Sept 1995 for TMI-1 ML20092F4401995-08-31031 August 1995 Monthly Operating Rept for Aug 1995 for TMI-1 ML20086F5021995-06-30030 June 1995 Monthly Operating Rept for June 1995 for TMI Unit 1 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G1001999-10-14014 October 1999 Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20216F9231999-09-22022 September 1999 Safety Evaluation Supporting Amend 216 to License DPR-50 05000289/LER-1999-010, :on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With1999-09-21021 September 1999
- on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With
ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211E8731999-08-24024 August 1999 Safety Evaluation Supporting Amend 215 to License DPR-50 ML20211B1931999-08-19019 August 1999 Safety Evaluation Supporting Amend 214 to License DPR-50 ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With 05000289/LER-1999-009, :on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced1999-07-22022 July 1999
- on 990626,automatic Start of EDG 1A Occurred. Caused by Failure of Fault Pressure Relay on Auxiliary Transformer 1B.Failed Pressure Relay Has Been Replaced
ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20212H9101999-06-21021 June 1999 Safety Evaluation Supporting Amend 212 to License DPR-50 05000289/LER-1999-007, :on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed1999-06-18018 June 1999
- on 990528,increasing Failure Rate of ESAS Relays Characterized by Coil Overheating & Failing to Fully re-close After Being de-energized Was Discovered.Cause Indeterminate.Relay Check Procedure Has Been Changed
05000289/LER-1999-005, :on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With1999-06-14014 June 1999
- on 990514,open Flood Path Between Turbine Bldg & Control Bldg Was Noted.Caused by Failure to Recognize That Mods Affected Flood Protection.Revised Flood Procedures.With
ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 05000289/LER-1999-003-01, :on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open1999-05-0707 May 1999
- on 990310,discovered Failure of Manual Balancing Damper in Supply Duct of Control Bldg Evs.Caused by Failure to Adequately Review Risk & Consequences of Change.Failed Damper Was Clamped Open
ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20205Q6111999-04-15015 April 1999 Safety Evaluation Supporting Amend 210 to License DPR-50 ML20205Q5981999-04-13013 April 1999 Safety Evaluation Supporting Amend 209 to License DPR-50 ML20206P2841999-04-12012 April 1999 SER Approving Transfer of License for Tmi,Unit 1,held by Gpu Nuclear,Inc to Amergen Energy Co,Llc & Conforming Amend, Per 10CFR50.80 & 50.90 ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) 05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With1999-03-14014 March 1999
- on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With
ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With 05000289/LER-1999-001-01, :on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys1999-02-19019 February 1999
- on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys
ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits 05000289/LER-1998-014-01, :on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With1999-01-11011 January 1999
- on 981210,missed TS Surveillance Was Noted. Caused by Human Error.Absolute & Relative Control Rod Positions Were Obtained Immediately & Verified to Agree within Required Range.With
ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing 05000289/LER-1998-013, :on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance1998-10-15015 October 1998
- on 980916,failure to Perform Fire Protection Program Surveillances at Required Frequency Was Noted.Caused by Changes Not Being Made to Surveillance Schedule.Performed Missed Insp Surveillance
05000289/LER-1998-010-01, :on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued1998-10-0909 October 1998
- on 980825,potential Violation of Design Criteria During Single Auxiliary Transformer Operation Occurred.Caused by Failure to Adequately Define Job Performance Stds.Temporary Change Notice Issued
ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With 05000289/LER-1998-011, :on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge1998-09-23023 September 1998
- on 980825,Thermo-Lag Fire Barrier Was Found Installed Outside Approved Joint Design Arrangement.Caused by Personnel Error.Initiated Continuous Fire Watch & Installed Trowel Grade Thermo-Lag in Void & on Outer Edge
05000289/LER-1998-009-01, :on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised1998-09-18018 September 1998
- on 980820,discovered Potential Loss of HPI During Postulated Loca.Caused by Misapplication or Interpretation of Design Inputs.Revised OL Was Implemented & Mut Pressure & Level Limits Analysis Revised
1999-09-30
[Table view] |
Text
. . .
9
GPU Nuclear,Inc.
( Route 441 South Mi d e wn 17057-0480 Tel 717-944-7621 6710-97-2190 May 14,1997 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
Three Mile Island Nuclear Stition, Unit I (TMI-1)
Operating License No. DPR 50 Docket No. 50-289 Monthly Operating Report for April 1997 Enclosed are two copies of the April 1997 Monthly Operathg Report for Three Mile Island Nuclear Station, Unit 1.
Sincerely, ji 1 y' / l fj$'
J. W. Langenbach Vice President and Director, TMI WGli cc: Administrator, Region I TMI Senior Resident Inspectcr 97001
,h,bffff nnnn 9705220254 970430 PDR ADOCK 05000289 R PDR .,
.I 3
p OPERATIONS
SUMMARY
April 1997 The plant entered the month operating at 100% power and remained at that power level for the remainder of the month. Net unit electrical output averaged approximately 816 MWe during l April.
MAJOR SAFETY RELATED MAINTENANCE ;
The major safety related maintenance items completed during the month involved the following equipment:
Enctor Building Fans AH-E-1BIC During the March 1997 repairs were made to AH-E-1 A fan motor to correct a fault at a 4/0 cable connection into the weld connector. Engineering recommended that heat shrink. tubing be installed over the exposed metal and on to the spark plug porcelain to meet EQ configuration requirements. The recommendation was inconsistent with previous direction provided for maintenance performed on the AH-E-1 A/B/C fan motors in 1986 and 1993. On both these occasions, the motor connections were remade using the "as found" configuration.
i Differences between the recent direction and that used in 1986 and 1993 brought into question ,
)
4 the EQ basis and the qualification of the configuration resulting from the prior maintenance. The ;
Plant Review Group met on April 24,1997 and concluded that AH-E-1B/C fan motors could not l 4
be expected to remain operable in a post LOCA environment (100% humidity being the concern )
- on exposed metal conductors). AH-E-1B/C were declared inoperable with a seven day Technical j .. Specification time clock applicable. The event was reported to the NRC under 10 CFR
- 50.72(b)(2)(iii)(D).
. Temporary repairs were made on April 25,1997 to the connections on the B/C fan motors in
! accordance with directions mimicking those used by Commonwealth Edison to qualify a similar
- splice. Permanent repairs, providing a qualified EQ configuration will be completed during the j- 12R outage.
Auxiliary and Fuel Handling Building Fan AH-E-14C E Repairs to Auxiliary and Fuel Handling Building Ventilation Exhaust Fan AH-E-14C, begun in ;
March, were completed during April. The fan / motor assembly was reassembled and tested prior
]
' to installing it in the ducting. Once installed, AH-E-14C was aligned and the elecrticalleads j i-terminated. Post-maintenance testing of the unit was completed satisfactorily and the fan was j returned to semce. j 4
+
l
l 1
l Emergency 3iesel Generators EG-Y-1 A/B Emergency Diesel Generators EG-Y-1 A/B were removed from service to perform the scheduled l annual inspection.' A reduced scope inspection was performed this year and the scheduled :
activities accomplished included engine oil changes, valve inspections and testing, fan drive unit l inspections, instrument calibrations, and various corrective and preventative maintenance tasks.
. Work was started and was completed on EG-Y-1B during the week of April 7th. Work on EG- i Y-1 A was started and completed during the week of April 14th. It was during the inspection of '
the ve:tical drive on EG-Y-1 A, that lockwire on the bolts was found to be broken and undersized.
The lockwire was replaced on the vertical drive bolting and EG-Y-1 A was returned to service.
Subsequently, EG-Y-1B was removed from service to determine whether the lockwire was l
-deficient on that engine. No diserepancies were identified with the lockwire installed on the EG- l Y-1B vertical drive bolting and the engine was returned to service. ,
Sp.pnt Fuel Activities In order to support a root cause evaluation of the distinctive crud pattern (DCP), six irradiated fuel rods which were removed from assemblies were transferred to a fuel shipping canister in the Spent Fuel Pool. The DCP was identified on fuel rods contained in several fuel assemblies, during inspection of fuel discharged from the core following the completion of operating Cycle 10. The canister containing the rods will be loaded into an NRC licensed shipping cask in Iune 1997 for transport to a hot cell facility where the evaluation will be performed.
)
l
)
l
, )
i I 4
I: ;
l l
7 i
e 2
l 4
- m. , ._, - . _ - _ . ._
U h
OPERATING DATA REPORT L
DOCKET NO. 50-289 .'
DATE M 14 1997 COMPLETUD Bt W. HEYSEK TELEPliONE (717)948-8191 OPERATING STATUS NOTES:
- 1. UNIT NAME: TliREE MILE ISLAND UNIT 1
- 2. REPORTING PERIOD: APRIL 1997
- 3. LICENSED TilERMAL POWER: 2568
- 4. NAMEPLATE RATING (GROSS MWe): 872
- 5. DESIGN ELECTRICAL RATING (NET MWe): 819 6 MAXIMUM DEPENDABLE CAPACITY (GROSS MWe): 834
- 7. MAXIMUM DEPENDABLE CAPACITY (NET MWe): 786
- 8. IF CHANGES OCCUR IN (ITEMS 3-7) SINCE LAST REPORT, GIVE REASONS:
9 POWER LEVEL TO WillCII RESTRICTED, IF ANY (NET MWe):
- 10. REASONS FOR RESTRICTIONS,IF ANY:
Tills MONTIi YR.TO-DATE CUMMULATIVE
- 11. IlOURS IN REPORTING PERIOD: (HRS) 719.0 2,879,0 198,648.0
- 12. NUMBER OF HOURS REACTOR WAS CRITICAL (HRS) 719.0 2,879.0 121,206.1
- 13. REACTOR RESERVE SHUTDOWN ilOURS (HRS) 0.0 0.0 2,283 9
- 14. HOURS GENERATOR ON LINE (llRS) 719.0 2,879.0 120,044.3
- 15. UNIT RESERVE SIIUTDOWN IIOURS (HRS) 0.0 0.0 0.0
- 16. GROSS TIIERMAL ENERGY GENERATED (M'VH) 1,844,645.8 7,385,978.9 295,991,654.3
- 17. GROSS ELECTRICAL ENERGY GENERATED (MWil) 620,401.0 2,496,840.0 99,461,386.1
- 18. NET ELECTRICAL ENERGY GENERATED (MWH) 587,030.0 2,361.136.0 93,504,800.1 19 UNIT SERVICE FACTOR (%) 100.0 100 0 60.4
- 20. UNIT AVAILABILITY FACTOR (%) 100.0 100.0 60.4
- 21. UNIT CAPACITY FACTOR (MDC NET) 103.9 104.3 59.9
- 22. UNIT CAPACITY FACTOR (DER NET) 99.7 100.1 57.5
- 23. UNIT FORCED OUTAGE RATE (%) 0.0 0.0 33.6 UNIT FORCED OUTAGE IlOURS (HRS) 0.0 0.0 60,761.2
- 24. SilUTDOWNS SCilEDULED OVER THE NEXT SIX MONTHS (TYPE, DATE AND DURATION OF EACH):
The unit will shutdown for a refueling outage scheduled to begin on September 5,1997 with a duration of 55 day s.
- 25. IF SHUTDOWN AT Tile END OF THE REPORT PERIOD, ESTIMATE DATE OF STARTUP:
3
3 '. 'o .
a AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-289 - -l DATE May 14 1997 COMPi.ETED BY,'W. HEYSEK
' TELEPIIONE (717) 948-8191 ,
. MONTH: APRIL :
DAY. AVERAGE DAILY POWER DAY . AVERAGE DAILY POWER ,
LEVEL (MWe NET) LEVEL (MWe NET) 1 819 16 817 2 816 17 816- ,
3 813 18 818 l 4 810 19 820 l
- 5 815 20 819 6 811 21 819 7 809 22. 818 8 818 23 816 9 823 24 815. ,
J 10 824 25 816 11 822 26 814 12 819 27 815 13 815 28 813 14 820 29 814
- 1
'15 821 30 810 31 i
-4 1
l
)
]
4 t, %
DocxET mo. 50-289 '
IMBIT MAbs TMI-It . . 7.-
nata May 14,1997 ~
REPORT MONTH AP".II997 W. G.'Heysek;
". . _^
mmg nr ~ :(7171 948-8191
^
htethod of Ucermee . System Component Cmase a Cauctn
~ h Shutans Evan Code Cade Acara m Dame Type 8 Dwanan Reason * % p - %%
N as cear' *a= ,
None i
L i.
1- 2 3 4
- F Faroed Reesas Method Exhk G . _ fm 5 SchsMed A-Eqtapteent Fashns @cphun) 1-Mannst prgernean ofDesa Eney Shees B-Masemance a Test 2-ManualScrarn for facensee Event Report (LER)
C-Reihehng FAutornstic Scrara File (NUREG4161)
D-Reguisecry Resencaon 40ther(Expland E4peramrTn==ng a u'==* ' 5 Emi F?
Cope meanal Ena @tplaW nohar w 6 Acnmity used exhitman F a R NUREG 0101 -
5
_ . - _ - - . . . ~ . . , . - ~- _. _ . - ,u,. _. - . , .~ _ - . - - - . - . . . , _ . . - ~ . , ~ . _ . - . . . . _
REFUELING INFORMATION REOUEST
- 1. Name of Facility: Three Mile Island Nuclear Station, Unit 1
- 2. Scheduled date for next refueling shutdown: September 5,1997
- 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. To support GPU Nuclear's independent reload analyses for Cycle 12 as discussed in response to Question 6 below, T.S. 6.9.5.2 will require revision to include references to the GPU Nuclear analysis methods applied to the reload.
t
- 5. Scheduled date(s) for submitting proposed licensing action and supporting information: Technical Specification Change Request Number 264 for the changes as discussed above will be submitted in early May 1997.
- 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:
4 a) GPU Nuclear Letter 6710-96-2092, dated March 28,1996 confirmed
- plans to perform independent reload design evaluations for Cycle 12, the next operation cycle, based on NRC approved methods described in GPU Nuclear Topical Reports TR-091-A (core physics), TR-087-A (core thermal I hydraulics), TR-078-A (FSAR safety analyses) and TR-092P-A (design and setpoints methodology) submitted to the NRC. The NRC has approved all of the associated topical reports.
The GPU Nuclear Cycle 12 reload program and results are expected to be l available for NRC review in the May to June 1997 time frame.
f 6
l
i b) Cycle 12 fuel rod performance calculations (e.g. internal pin pressure) ,
will be performed by Framatome Cogema Fuels Company (FCF) using the approved TACO 3 (BAW-10162P-A) and GDTACO (BAW-10184P-A) fuel codes. Results require minor changes to the Mark B9 fuel rod design (lower fill gas prepressure, increased plenum volume). The new design will meet all fuel criteria in the latest approved revision of BAW-10179P-A, Safety Criteria and Methodology for Acceptable Cycle Reload Analyses. Fuel rod i cladding corrosion calculations for all Cycle 12 fuel are being done by FCF using the COROS2 methodology described in Topical Report BAW 10186P,
" Extended Burnup Evaluation" which was approved by the NRC en April 29.1997. The TACO calculations are being done using power histories ,
generated with the GPU Nuclear approved core physics codes CASMO- !
3/ SIMULATE-3 (TR-091 A). Use of the SIMULATE-3 power peaking ;
uncertainty of 5.5% with the TACO methodologies, rather than the current FCF NEMO physics code (BAW-10180A, Rev 1) unnrtainty of 4.8%, was approved by NRC on October 4,1995 for application to TMI-1 only.
- 7. The number of fuel assemblies (a) in the core, and (b) in the spent fuel storage pool: (a) 177 (b) 864
- 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 1990. Phase I of the reracking project to increase spent fuel pool storage capacity permits storage of 1342 assemblies.
Upon completion of Phase II of the reracking project, the fulllicensed capacity will be attained. Phase 11 b expected to be started in 2002.
- 9. The projected date of the last refueling that can be discharged to the spent fuei ,
pool assuming the present licensed capacity:
Completion of Phase I of the reracking project permits full core off-load (177 fuel assemblies) through the end of Cycle 14 and on completion of the rerack project full core off-load is assured through and beyond the end of the current operating 3icense.
4
)
4 7
____.;