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Category:MONTHLY OPERATING ANALYSIS REPORT
MONTHYEARML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant ML20198J8941997-09-30030 September 1997 Monthly Operating Repts for Sept 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20216J6011997-08-31031 August 1997 Monthly Operating Repts for Aug 1997 for Sequoyah Nuclear Plant ML20210K5781997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Sequoyah Nuclear Plant ML20141H3071997-06-30030 June 1997 Monthly Operating Repts for June 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20140H1571997-05-31031 May 1997 Monthly Operating Repts for May 1997 for SQN ML20141F4321997-04-30030 April 1997 Monthly Operating Repts for Apr 1997 for Sequoyah Nuclear Plant Units 1 & 2 ML20137T3011997-03-31031 March 1997 Monthly Operating Repts for March 1997 for SQN ML20136H2191997-02-28028 February 1997 Monthly Operating Repts for Feb 1997 for SQN ML20134M2001997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for SQN ML20133K4861996-12-31031 December 1996 Monthly Operating Repts for Dec 1996 for Sequoyah Nuclear Plant Units 1 & 2 ML20133A1121996-11-30030 November 1996 Monthly Operating Repts for Nov 1996 for SQN Plant ML20134N2501996-10-31031 October 1996 Monthly Operating Repts for Oct 1996 for Sequoyah Nuclear Plant ML20128Q0251996-09-30030 September 1996 Monthly Operating Repts for Sept 1996 for Sequoyah Nuclear Plant,Units 1 & 2 ML20129C2181996-08-31031 August 1996 Monthly Operating Rept for Aug 1996 for Sequoyah Nuclear Plant ML20116M1511996-07-31031 July 1996 Monthly Operating Repts for July 1996 for Sequoyah Nuclear Plant ML20115H0371996-06-30030 June 1996 Monthly Operating Repts for June 1996 for SQN ML20112H6351996-05-31031 May 1996 Monthly Operating Repts for May 1996 for Sequoyah Nuclear Plant ML20112A7901996-04-30030 April 1996 Monthly Operating Rept for Apr 1996 for Sequoyah Unit 1 & 2 ML20107B7591996-03-31031 March 1996 Monthly Operating Repts for Mar 1996 for Sequoyah Nuclear Plant,Units 1 & 2 ML20101D3351996-02-29029 February 1996 Monthly Operating Repts for Feb 1996 for Sequoyah Nuclear Plant ML20149K2341996-01-31031 January 1996 Monthly Operating Repts for Jan 1996 for Snp ML20096F0201995-12-31031 December 1995 Monthly Operating Repts for Dec 1995 for Snp ML20095J0461995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for Snp ML20094L7381995-10-31031 October 1995 Monthly Operating Repts for Oct 1995 for Sequoyah Nuclear Plant ML20093F5351995-09-30030 September 1995 Monthly Operating Repts for Sept 1995 for Sequoyah Nuclear Plant ML20092G2981995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Sequoyah Nuclear Plant 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
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tennessee Vaaey Authert,. Post Of'-ce Ocx 2000 Scxt@O.rsy Tennessee 3?r9 2000 Raben A. Fenech v<e nes.aent, sequeyan Neear Mant February 15, 1994 U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555 Gentlemen:
l l In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 SEQUOYAll NUCLEAR PLANT (SQN) - JANUARY 1994 MONTHLY OPERATING REPORT Enclosed is the January 1994 Monthly Operating Report as required by SQN Technical Specification 6.9.1.10. It should be noted that the unit capacity indicators, gross maximum capacity and net maximum dependable capacity, have been revised to reflect baseline testing that was performed on each unit.
If you have any questions concerning this matter, please call J. W. Proffitt at (615) 843-6651.
Sincerely, f /Ycep h Robert A. Fenech
, Enclosure cc: See page 2 1
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U.S. l'eclear aegulatory Commission Page 2 i February 15, 1994 i
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! INP0 Records Center
' Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, Georgia 30339-5957 Mr. D. E. LaBarge, Project Manager U.S. Nucicar Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Mr. Ted Marston, Director Electric Power Research Institute P.O. Box 10412 Palo Alto, California 94304 NRC Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administration U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 Regional Administrator U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323-2711 j l
Mr. F. Yost, Director Research Services i Utility Data Institute l 1200 G Street, NW, Suite 250 l Washington, D.C. 20005
i b
f TENNESSEE VALLEY AUTHORITY NUCLEAR POWER GROUP SEQUOTAH NUCLEAR PIANT MONTHLY OPERATING REPORT TO THE NUCLEAR REGUIATORY COPMISSION JANUARY 1993 i
i UNIT 1 ;
DOCKET NIMBER 50-327 1
LICENSE NUMBER DPR-77 i UNIT 2 l 1
DOCKET NUMBER 50-328 LICENSE NUMBER DPR-79
1 l
t OPERATIONAL SUMttARY l JANUARY 1994 l mIIa The Unit 1 Cycle 6 refueling outage continues. Unit i remained in Mode 5 through the end of January.
i 173E_2 Unit 2 generated 713,520 megawatthours (MWh) (gross) electrical power during January with a capacity factor of 83.69 percent. Unit 2 was operating at approximately 100 percent reactor power at the beginning of January.
At 1610 Eastern standard time (EST) on January 5, the 2B-B centrifugal l charging pump (CCP) tripped on timed overcurrent "A" phase, and letdown l isolated. The 2A-A CCP was started. It was later discovered that the 2B-B l
CCP had a broken shaft. On January 7 at 1352 EST, a power decrease was !
initiated because of technical specification requirements when it was !
determined that the repair time on the 2B-B CCP would exceed the 72-hour '
limiting condition for operation requirement. !
Unit 2 was taken offline on January 8 at 0420 EST and entered Mode 2 at ,
1420 EST, maintaining reactor power at approximately 2 percent to test the main steam isolation valves at operating temperature. Unit 2 entered Mode 3 at 1838 EST on January 8 and entered Mode 4 at 2305 EST that day.
Unit 2 heatup to Mode 3 was initiated on January 11 at 0625 EST. Unit 2 entered Mode 3 at 0708 EST on January 11, and the reactor was taken critical at 0612 EST on January 12. Unit 2 entered Mode 1 on January 12 at 1428 EST and tied to the grid at 2159 EST that day. Unit 2 was operating at 100 percent reactor power on January 14 at 1446 EST and continued to operate at 100 percent reactor power through the end of January.
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 5Q-311 UNIT No. _ Qne DATE: _Q2_-f4-94 COMPLETED BY: T. J. Ilo110 mon TELEPHONE: 1615) 843-7528 MONTil: . JANllARY_.1294 AVERAGE DAILY POWER LEVEL AVERACE DAILY POWER LEVEL DAY IMWe-Net) DAX (MWe-Netl 1 -2 17 -1 2 -2 18 -1 3 -1 19 -1 4 -1 20 -2 _
5 -1 21 - Z_
6 -L._ 22 -1
-2 7 23 .
8 -28 24 -2 9 -26 25 -1 10 - 16 26 -1 11 -2.8 27 -2 12 -35 28 -1 ,
1 13 -7 29 .
-1 14 -2 30 -1 15 -2 31 -1 16 -1 l l
l . .
l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. ___1Q-328 UNIT No. _ lwo _. DATE: _02-01-3 1 4 l
COMPLETED BY: L._Jdlqllamon TELEPil9NE: 16111_643-15 Z8 l
MONTil: __JARUARY 1994 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (tMe-Ne t ) DAY (MWe-Net) 1 1142 17 1144 2 1M3 18 1142 3 1142 19 1L42 4 1M2 20 1L42 5 1135 21 1142 6 1143 22 1143 7 106h 23 143 8 47 24 11A0 9 -2 _ 25 1143 10 -3 __ 26 1143 11 -5 27 1144 12 10 28 _ ll40 13 437 29 1143 l 14 1085 30 11A2_
15 1143 31 1142 16 1143
OPERATING DATA REPORT l DOCKET NO. _50-321 - .
i DATE _QZlDA/.94 COMPLETED BY I .J _tiollcmon TELEPHONE 161hLO.43_l52S_
O RRAUt!G_ilA M l Notes l
- 1. Unit Name: J tquoyab Unit One l l
- 2. Reporting Period: _ _).gnyary._1294 l l
- 3. Licensed thermal Power (HWt): 3411.0 l l
- 4. Nameplate Rating (Gross HWe): 1220.6 l l S. Design Electrical Rating (Net MWe): 1148.0 l l
- 6. Maximum Dependable Capacity (Gross MWe): 1151.0 l l
- 7. Maximum Dependable Capacity (Net MWe): 1111.0 1 1
- 8. If Changes Occur in Capacity Rat {ngs (Item Numbers 3 Through 7) $1nce Last Report, Give Reasons:
l l
l 9. Power Level fo Which Restricted, If Any (Net HWe): N/A
- 10. Reasons For Restrictions, If Any: N/A l
This Month Yr-to-Date Cumulative l
- 11. Hours in Reporting Period 744 744 110.3 M. _
- 12. Number of Hours Reactor Was Critical 0 0 56.q29
- 13. Reactor Reserve Shutdown llours 0 _
0 0 j l 14. Hours Generator On-Line 0 ..D._ 54,02L5_ l
- 15. Unit Reserve Shutdown Hours 0 0 0 l
- 16. Gross Thermal Energy Generated (HWH) 0 0 178.893.714 )
- 17. Gross Electrical Energy Generated (MWH) Q 0 __501112,654
- 18. Het Electrical Energy Generated (MWH) -4.536 -L516 __50,159,501
- 19. Unit Service factor 0 0 49.7
- 20. Unit Availability Factor 0 0 49.7.
- 21. Unit Capacity Factor (Using MOC Net) -015 -011_ 47.4
- 22. Unit Capacity Factor (Using DER Net) -0 5 -0,1 45,9 _
- 23. Unit forced Outage Rate 0 _0_ ._301_
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup: __11 arch _26J29119t0_synd _
l
. . 1 1
1 OPERATING DATA REPORT l l
DOCKET NO.10-328 DATE JZl.04/94 COMPLETED BY T, J. Hgligino t TELEPHONE [ft151343_Z520_
QEfaAllNG STATVS l Notes l
- 1. Unit Name: _St.qunnh Unit Two l l
- 2. Reporting Period: . January 1994 _ l l
- 3. Licensed Thermal Power (HWt): .3411.0 l l 4 Nameplate Ratiig (Gross HWe): _.1220.6 l l
- 5. Design Electrical Rating (Net HWe): __1148.0 l l
- 6. Maximum Dependable Capacity (Gross HWe): 1146.0 l l
- 7. Maximum Dependable Capacity (Net HWe): 1106.0 l l
- 8. If Changes Ucrur in Capacity Ratings (Item Numbers 3 Through 7) Since Last Report, Give Reasons:
- 9. Power Level To Which Restricted. If Any (Net HWe): N/A
- 10. Reasons for Restrictions, If Any: N/A This Month Yr-to-Date Cumulative
- 11. Hours in Reporting Period 744 744_ _ 1021313
- 12. Number of Hours Reactor Was Critical 6{L4.4 68LL SL443
- 13. Reactor Reserve Shutdown Hours 9 0 0
- 14. Hours Generator On-Line 630.4 630.4_ 57.923.9
- 15. Unit Reserve Shutdown Hours 0 0 Q
- 16. Gross Thermal Energy Generated (HWH) 2.081.774.4 2.08 LIZ_4A _ _lft)1Dd4,126
- 17. Gross Electrical Energy Generated (HWH) . 713.520 . 71L320 __1L641.464
- 18. Net Electrical Energy Generated (HWH) 689.135 689.135 58.967.421 l
- 19. Unit Service Factor 0_4. 7 84t L _56 t6 .
- 20. Unit Availability Factor __. 8411 _. 84 2 , Sfu6_
- 21. Unit Capacity factor (Using HDC Net) HLL,_, 83t L SLL_
- 22. Unit Capacity Factor (Using DER Net) 8 037 801L 302L_
- 23. Unit Forced Outage Rate 15.3 15.L 37.0
- 24. Shutdowns Scheduled Over Next 6 Honths (Type, Date, and Duration of Each):
UnLL2_Cnis_52thteling_outagt: Juiv 3.1994LftLdays I
- 25. If Shut Down At End Of Report Period Estimated Date of Startup:
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DOCKET NO: 50-327 UNIT SHUTDOWNS AND POWER TEDUCTIONS UNIT NAME: One DATE: 02/09/94 .
REPORT HONTH: January l')94 COMPLETED BY:T. J. Hollomon TELEPHONE:f6151 843-7528 Method of Licensee Cause and Corrective !
Duration Shutting Down Eveet System Component Action to l 4 No. Date Type (Hours) Reason2 Reactor 3 Report No. Code Code 5 Prevent Recurrence 1 940101 5 744 C 4 N/A N/A N/A The Unit 1 Cycle 6 refueling cutagh continues.
t 1
4 2 Reason: #
I:F Forced Hethod: Exhibit G-Instructions 5: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data i
B-Maintenance or Test 2-Manual Scram Entry sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Examination 5-Reduction F-Administrative 9-Other S
G-Operational Error (Explain) Exhibit I-Same Source ;
H-Other (Explain)
}
k
DOCKET NO: 50-328 tjNIT SHUTDOWNS AND P0WER REDUCTIONS UNIT NAME: Two .
DATE: 02/09/94 - - .
REPORT NONTH: January 1994 COMPLETED BY:T. J. Hollomon TELEPHONE:f615) 843-7528 Nethod of Licensee Cause and Carrective Duration Shutting Down Event System Cormgnent Action to .
, 4 Prevent Recurrence No. Date Type (Hours) Reason' Reactor Report No. Code Code 1 940107 F 113.7 A 1 328/94002 CB P On January 7, 1994. at 1352 EST, a' reactor power shutdown was initiated because repairs to the 28-B centrifugal charging pump (CCP) broken shaft could not be completed within the 72-hour tech-nical specification time limit.
The shaf t break was determined to be the result of material fatigue.
The pump shaft was replaced, and the pump was tested and returned to service. ' The cause of the fatigue failure is being further evaluated.
Unit 2 was returned to service on January 12 at 2159 EST after the repairs were completed on the 2B4 CCP.
2 Reason: #
'I:FForced Method: Exhibit G-Instructions 5: 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) File D-Regulatory Restruction 4-Continuation of Existing Outage (NUREG-1022)
E-Operator Training and License Examination 5-Reduction F-Administrative 94ther 5
G-Operational Error (Explain) Exhibit I-Same' Source H-Other (Explain)
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