ML17306B381

Monthly Operating Repts for Mar 1993 for Pvngs,Units 1,2 & 3.W/930414 Ltr

ML17306B381
Person / Time
Site:	Palo Verde
Issue date:	03/31/1993
From:	Ecklund B, James M. Levine ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
417-00051-JML-B, 417-51-JML-B, NUDOCS 9304150149
Download: ML17306B381 (23)

Text

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ACCESHO&j NBR:9304150149 DOC.DATE: 93/03/31 NOTARIZED: NO DOCKET FAOIL:iSTN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION ECKLUND,B.S. Arizona Public Service Co. (formerly Arizona Nuclear Power LEVINE,J.M. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION I D

SUBJECT:

Monthly operating repts for Mare 1993 for PVNGS,units 1,2 3.W/930414 ltr. &

DISTRIBUTION CODE: IE24D COPIES RECEIVED:LTR TITLE: Monthly Operating Report (per Tech Specs)

L ENCL i SIZE: l~

NOTES:STANDARDIZED PLANT 05000528 A Standardized plant. 05000529 Standardized plant. 05000530 RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ONDD LA 3 3 ONDD PD 1 1 TRAMMELLgC 1 1 TRANiL 1 1 INTERNAL: ACRS 10 10 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 NR DSR OEAB 1 1 NRR/DRIL/RPEB 1 1 G F L Ol 1 1 RGN5 1 1 EXTERNAL EG&G BRYCE i J ~ H 1 1 NRC PDR 1 1 NS I'C 1 1 NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT TFIE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 504-2065) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 25 ENCL 25

I Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034 ~ PHOENIX, ARIZONA85072-2034 JAMES M. LEVINE 417-00051-JML/BSE/FHD/GEZ VICE PRESIDENT April 14, 1993 NUCLEAR PRODUCTION U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Docket Nos. STN 50-528/529/530 Monthly Operating Reports for March 1993 File: 93-024-404 93-056-026 Enclosed are the Monthly Operating Reports for March 1993, prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the PVNGS Units 1, 2, and 3 Operating Licenses. By copy of this letter, Arizona Public Service Company is also forwarding the Monthly Operating Reports to the Regional Administrator, NRC Region V.

If you have any questions, please contact Brad S. Ecklund at (602) 340-4068.

Sincerely, JML/BSE/FHD/gez Enclosures cc: J. B. Martin (all w/en'closures)

A. C. Gehr A. H. Gutterman NRC Senior Resident Inspector INPO Records Center Utility Data Institute 9304i50i49 93033i PDR 05000528

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY B S. Ecklund MONTH: March 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1251 1248 1251 18 1248 1249 1250 1249 20 1249 1251 1248 1251 22 1248 1248 23 1248 1249 24 1247 1248 25 1169 10 124 26 1078 1247 27 1248 12 1248 28 1248 13 1251 29 1246 14 1248 30 1247 15 1249 31 1249 16 1249 2

REFUELING INFORMATION DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY B. S. Ecklund Scheduled date for next refueling shutdown.

09/04/93, 4th refueling Scheduled date for restart following refueling.

11/23/93 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendments There will be no need for a Technical Specification change or other license amendment.

Scheduled date for submitting proposed licensing action and supporting information.

N/A 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, and new operating procedures.

APS intends to use Guardian' debris resistant grids in Unit 1 Batch 6 fuel and has submitted, for NRC review, a Topical Report, "System 80' Inlet Flow Distribution, Supplement 1-P to Enclosure 1-P to LD-82-054," that discusses a revision to the analysis method.

The number of fuel assemblies.

a) In the core. 241 b) In the spent fuel storage pool. 276 Licensed spent fuel storage capacity. 1329 Intended change in spent fuel storage capacity. None Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

2005 (18 Month reloads and full core discharge capability).

3

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY B. S. Ecklund March 1993 03/01 0000 Unit began the month in Mode 1; 100% RX power.

03/25 1613 Due to PC/CMC COLSS stalling, a power reduction was commenced to meet out of service specifications.

03/25 1707 Power reduction was stopped at 80%.

03/25 1832 CMC COLSS was restored to operable status. The PC was still halted.

03/25 2238 A power reduction from 80% to 70% was started to replace a speed probe on the Feedwater Pump Turbine "A".

03/26 0002 Power reduction was stopped at 70%.

03/26 0430 Commenced RX power ascension back to 80%.

03/26 0630 Stabilized RX power at 82%.

03/26 0639 Restored plant computer back to service and commenced RX power ascension to 100%.

03/26 0915 Stabilized RX power at 90% to perform a surveillance test.

03/26 1300 Recommenced RX power ascension to 100%.

03/26 1627 Stabilized RX power at 100%.

03/31 2400 Unit ended the month in Mode 1; 100% RX power.

4

SHUTDOWNS AND POWER REDUCTIONS March 1993 DOCKET NO 50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY B. S. Ecklund No. Date Type'ours Outage Duration Reason~

Method Shutting Down of Reactor'ER No.

Code'ause System Component Code'revent and Corrective Action to Recurrence 93-03 03/25/93 F N/A N/A N/A N/A RX power reduction to 80%

due to PC/CMC COLSS stalling problems.

93-04 03/25/93 F N/A N/A N/A N/A RX power reduction from 80%

to 70% to replace a speed probe on FW Pump Turbine A.

'F- Forced 'Reason: <<Method: 4Exhibit F-Instructions S-Scheduled A-Equipment Failure(Explain) 1-Manual for Preparation of the Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training & License Previous Month Examination 5-Reduction of 20% or F-Administrative Greater in the Past 'Exhibit H-Same Source G-Operational Error 24 Hours H-Other (Explain) 9-Other-(Explain) 5

C

AVERAGE DAILY UNIT POWER LEVEL

'OCKET NO. 50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY B S Ecklund MONTH: March 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1183 17 1237 18 1240 19 1239 20 1237 21 7'209 1238 22 23 119 24 1192 25 10 1205 26 1217 27 12 1226 28 13 1230 29 14 209 30 15 31 16

REFUELING INFORMATION DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY B. S. Ecklund Scheduled date for next refueling shutdown.

03/20/93, 4th refueling Scheduled date for restart following refueling.

06/08/93 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

No, however, a change to the moderator temperature coefficient curve will occur in the Unit 2 Cycle 5 Core Operating Limits Report.

Scheduled date for submitting proposed licensing action and supporting information.

N/A 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, and new operating procedures.

Minor modifications to the fuel pellet design is considered to be within the current Technical Specifications and no revision is required.

The number of fuel assemblies.

a) In the core. 241 b) In the spent fuel storage pool. 288 Licensed spent fuel storage capacity. 1329 Intended change in spent fuel storage capacity. None Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

2005 (18 Month reloads and full core discharge capability).

8

t t

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY B S Ecklund March 1993 I

03/01 0000 Unit began the month in Mode 1; 100% RX power.

03/14 0425 RCS pressure and pressurizer level suddenly decreased but no radiation monitors except RU140 and RU7 were alarming.

03/14 0447 Manually tripped RX and received SIAS and CIAS.

03/14 0458 Declared NUE.

03/14 0502 Upgraded emergency classification to an ALERT based on RCS leakage greater than 44 gpm.

03/14 0604 Commenced a cooldown per Functional Recovery Procedure.

03/14 0721 Recommenced RCS cooldown.

03/14 0728 Steam Generator ¹2 determined to have tube rupture and was isolated.

03/14 0804 Isolated aux. steam. Aux. steam now supplied by Unit 3.

03/14 1029 Entered Mode 4.

03/15 0115 ALERT terminated.

03/15 0556 Entered Mode 5.

03/19 0001 Official refueling outage start time.

03/24 1612 Entered Mode 6.

03/31 2400 Unit ended the month in Mode 6; 4th refueling outage in progress.

9

SHUTDOWNS AND POWER REDUCTIONS March 1993 DOCKET NO 50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY B. S. Ecklund No. Date Type'ours Outage Duration Method Shutting Reason'own Reactor'ER of No.

Code'ause System Component Code'revent and Corrective Action to Recurrence 93-01 03/14/93 F 115.2 N/A N/A N/A Manual RX trip due to tube rupture in SG42.

93-02 03/19/93 S 312.0 N/A N/A N/A Continued from manual RX trip on 3/14/93. Fourth refueling outage officially started at 0001 hrs. on 3/19/93.

'F- Forced 'Reason: 'Method: 'Exhibit F-Instructions S-Scheduled A-Equipment Failure(Explain) 1-Manual for Preparation of the Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training & License Previous Month Examination 5-Reduction of 20% or F-Administrative Greater in the Past 'Exhibit H-Same Source G-Operational Error 24 Hours H-Other (Explain) 9-Other-(Explain) 10-

NRC MONTHLY OPERATINQ REPORT DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY B S Ecklund OPERATING STATUS

1. Unit Name: Palo Verde Nuclear Generatin Station Unit 3

2. Reporting Period: March 1993

3. Licensed Thermal Power (MWt): 3800

4. Nameplate Rating (Gross MWe): 1403

5. Design Electrical Rating (Net MWe): 1270

6. Maximum Dependable Capacity (Gross MWe): 1303

7. Maximum Dependable Capacity (Net MWe): 1221 8 ~ If Changes Occur In Capacity Ratings (Item Numbers 3 Through 7)

Since Last Report, Give Reasons: N A

9. Power Level to Which Restricted, If Any (Net'We): None

10. Reasons For Restrictions, If Any: N A j:.:i'Yxg:~.t(j:.";::Qafe:".j g~g'::.Cuaiula:trav'e:,:.3.:.':

744 2,160 45,840 744.0 2,088.5 33,096.2 0.0 0.0 0.0 744.0 2,064.2 32,588.4 0.0 0.0 0.0 16.:::::::::;:.':::C$ ss,':,,,Thiriiia3;:,:-:;::,":,Exie':x'jy.",:0'exra",e'e'.d 2,756,155 7,578,081 119,595,086 963,800 2,649,900 41,877,700 909,919 2,498,511 39,401,831 100.0% 95.6% 71.1%

20.:;:.".:::,:.:'Qriie;:::-'::Avaig;'ab;$.'l'i,tj',,:Factor',::,:.,':,(:%)',:-',";:",',:::.-::t'~'-."g('.R'. 100.0% 95.6% 71.1%

21.:,,"::;;:::;:,:,Vn);:, 100.2% 94.7% 70.4%

22. 96.3% 91.1% 67.7%

0.0% 4.4% 7.7%

24.

25. If Shutdown At End of Report Period, Estimated Date of Start-up: N A Forecast Achieved INITIAL CRITICALITY ~08 ~0/025 87 INITIAL ELECTRICITY 07 87 11 28 87 COMMERCIAL OPERATION 09 87 01 08 88 11

I AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-530 UNIT NAME PVNGS-3 COMPLETED BY B. S. Ecklund MONTH: March 1993 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1265 17 1254 1263 18 1255 1261 19 1257 1002 20 1257 842 21 1258 1003 22 1256 1143 23 1252 1260 24 1254 1261 25 1254 10 1259 26 1256 1258 27 1257 12 1258 28 1258 13 1260 29 1259 14 1258 30 1257 15 1258 1255 16 125 12

REFUELING INFORMATION DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY B. S. Ecklund Scheduled date for next refueling shutdown.

03/12/94, 4th refueling.

Scheduled date for restart following refueling.

05/31/94.

Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Unknown at this time. Unit 3 Cycle 5 is presently in the preliminary design stages.

Scheduled date for submitting proposed licensing action and supporting information.

Mid 1993.

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, and new operating procedures.

The NRC granted a license amendment (No. 35) which allows the use of 80 fuel rods clad with advanced zirconium based alloys (other than Zircaloy-4) in two fuel assemblies during Unit 3 Cycles 4, 5, and 6 for in-reactor performance evaluation. Date of issuance was July 20, 1992.

The number of fuel assemblies.

a) In the core. 241 b) In the spent fuel storage pool. 284 Licensed spent fuel storage capacity. 1329 Intended change in spent fuel storage capacity. None Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity, 2005 (18 Month reloads and full core discharge capability).

13

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY B S Ecklund March 1993 03/01 0000 Unit began the month in Mode 1, 100% RX power.

03/04 1315 Control channels for the steam generator level control'n feedwater control system 2 (FWCS 2) were observed to be oscillating with large amplitude swings. Variation in main feedwater pump speed caused by the level oscillations caused a decrease in main feedwater pump suction pressure to the extent that the low suction pressure trip circuits energized for both feedwater pumps. FWCS 2 master controller was placed in manual and main feedwater pump A was tripped in a successful attempt to restore suction pressure.

The trip of the "A" main feedwater pump initiated a reactor power cutback which was successfully completed. CEA regulating Groups 4 6c 5 dropped and the turbine generator ranback to 55% power.

03/04 1400 Stabilized RX power at 55%.

03/04 1434 Commenced RX power ascension to 60$ at 5S per hour.

03/04 1535 Stabilized RX power at -60%.

03/05 0517 Commenced RX power increase to 70%.

03/05 0606 Stabilized RX power at -70%.

03/05 2105 Commenced RX power increase to 80%.

03/06 0100 Stabilized RX power at 80%.

03/07 0800 Commenced RX power increase to 100%.

03/07 1345 Stabilized RX power at 100%.

03/31 2400 Unit the ended month in Mode 1; 100% RX power.

14-

SHUTDOWNS AND POWER REDUCTIONS March 1993 DOCKET NO 50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY B. S. Ecklund Outage Method of Cause and Corrective Duration Shutting Code'omponent System Action to No. Date Type'ours Reason'own Reactor'ER No. Code~ Prevent Recurrence 93-03 03/04/93 F N/A N/A N/A N/A RX power reduction to 55%

due to the conditions identified on page 14 at 1315 hrs. on 3-4-93.

'F-Forced 'Reason: 'Method: 'Exhibit F-Instructions S-Scheduled A-Equipment Failure(Explain) 1-Manual for Preparation of the Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training & License Previous Month Examination 5-Reduction of 20% or F-Administrative Greater in the Past 'Exhibit H-Same Source G-Operational Error 24 Hours H-Other (Explain) 9-Other-(Explain) 15