ML17306B381

Monthly Operating Repts for Mar 1993 for Pvngs,Units 1,2 & 3

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

aecmzazx ooeUMKm MSX arroz SVSmM REGULA INFORMATION DISTRIBUTIO SYSTEM (RIDS)

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

SUBJECT:

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

DISTRIBUTION CODE:

IE24D COPIES RECEIVED:LTR L ENCL i SIZE: l~

TITLE: Monthly Operating Report (per Tech Specs)

D NOTES:STANDARDIZED PLANT Standardized plant.

Standardized plant.

05000528 A

05000529 05000530 RECIPIENT ID CODE/NAME ONDD LA TRAMMELLgC INTERNAL: ACRS AEOD/DSP/TPAB NRR/DRIL/RPEB RGN5 EXTERNAL EG&G BRYCE iJ

~ H NS I'C COPIES LTTR ENCL 3

3 1

1 10 10 1

1 1

1 1

1 1

1 1

1 RECIPIENT ID CODE/NAME ONDD PD TRANiL AEOD/DOA NR DSR OEAB G

F L Ol NRC PDR COPIES LTTR ENCL 1

1 1

1 1

1 1

1 1

1 1

1 D

NOTE TO ALL"RIDS" RECIPIENTS:

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

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 25 ENCL 25

JAMES M. LEVINE VICE PRESIDENT NUCLEAR PRODUCTION I

Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX 52034

~

PHOENIX, ARIZONA85072-2034 417-00051-JML/BSE/FHD/GEZ April 14, 1993 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 (all w/en'closures) cc:

J. B. Martin A. C. Gehr A. H. Gutterman NRC Senior Resident Inspector INPO Records Center Utility Data Institute 9304i50i49 93033i PDR ADGCK 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 03/25 0000 1613 Unit began the month in Mode 1; 100%

RX power.

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

03/25 03/25 03/25 03/26 03/26 03/26 03/26 1707 1832 2238 0002 0430 0630 0639 Power reduction was stopped at 80%.

CMC COLSS was restored to operable status.

The PC was still halted.

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

Power reduction was stopped at 70%.

Commenced RX power ascension back to 80%.

Stabilized RX power at 82%.

Restored plant computer back to service and commenced RX power ascension to 100%.

03/26 03/26 03/26 03/31 0915 1300 1627 2400 Stabilized RX power at 90% to perform a surveillance test.

Recommenced RX power ascension to 100%.

Stabilized RX power at 100%.

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.

Outage Method of Duration Shutting System Date Type'ours Reason~

Down Reactor'ER No. Code'ause and Corrective Component Action to Code'revent Recurrence 93-03 03/25/93 F

93-04 03/25/93 F

N/A N/A N/A N/A N/A N/A N/A N/A RX power reduction to 80%

due to PC/CMC COLSS stalling problems.

RX power reduction from 80%

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

'F-Forced S-Scheduled

'Reason:

<<Method:

A-Equipment Failure(Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-Operator Training & License Previous Month Examination 5-Reduction of 20% or F-Administrative Greater in the Past G-Operational Error 24 Hours H-Other (Explain) 9-Other-(Explain) 4Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

'Exhibit H-Same Source 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 1238 22 7'209 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 03/01 03/14 03/14 03/14 03/14 03/14 03/14 03/14 03/14 03/14 03/15 03/15 03/19 03/24 03/31 0000 0425 0447 0458 0502 0604 0721 0728 0804 1029 0115 0556 0001 1612 2400 I

Unit began the month in Mode 1; 100%

RX power.

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

Manually tripped RX and received SIAS and CIAS.

Declared NUE.

Upgraded emergency classification to an ALERT based on RCS leakage greater than 44 gpm.

Commenced a cooldown per Functional Recovery Procedure.

Recommenced RCS cooldown.

Steam Generator ¹2 determined to have tube rupture and was isolated.

Isolated aux.

steam.

Aux. steam now supplied by Unit 3.

Entered Mode 4.

ALERT terminated.

Entered Mode 5.

Official refueling outage start time.

Entered Mode 6.

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.

Outage Method of Duration Shutting System Date Type'ours Reason'own Reactor'ER No. Code'ause and Corrective Component Action to Code'revent Recurrence 93-01 03/14/93 F

115.2 93-02 03/19/93 S

312.0 N/A N/A N/A N/A N/A N/A Manual RX trip due to tube rupture in SG42.

Continued from manual RX trip on 3/14/93.

Fourth refueling outage officially started at 0001 hrs.

on 3/19/93.

'F-Forced S-Scheduled

'Reason:

'Method:

A-Equipment Failure(Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-Operator Training & License Previous Month Examination 5-Reduction of 20% or F-Administrative Greater in the Past G-Operational Error 24 Hours H-Other (Explain) 9-Other-(Explain)

'Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

'Exhibit H-Same Source 10-

NRC MONTHLY OPERATINQ REPORT DOCKET NO.

50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY B S

Ecklund OPERATING STATUS 1.

2.

3.

4.

5.

6.

7.

8

~

9.

10.

Unit Name:

Palo Verde Nuclear Generatin Station Unit 3 Reporting Period:

March 1993 Licensed Thermal Power (MWt):

3800 Nameplate Rating (Gross MWe):

1403 Design Electrical Rating (Net MWe):

1270 Maximum Dependable Capacity (Gross MWe): 1303 Maximum Dependable Capacity (Net MWe):

1221 If Changes Occur In Capacity Ratings (Item Numbers 3 Through 7)

Since Last Report, Give Reasons:

N A Power Level to Which Restricted, If Any (Net'We):

None Reasons For Restrictions, If Any:

N A 16.:::::::::;:.':::C$$ss,':,,,Thiriiia3;:,:-:;::,":,Exie':x'jy.",:0'exra",e'e'.d 20.:;:.".:::,:.:'Qriie;:::-'::Avaig;'ab;$.'l'i,tj',,:Factor',::,:.,':,(:%)',:-',";:",',:::.-::t'~'-."g('.R'.

21.:,,"::;;:::;:,:,Vn);:,

22.

744 744.0 0.0 744.0 0.0 2,756,155 963,800 909,919 100.0%

100.0%

100.2%

96.3%

0.0%

j:.:i'Yxg:~.t(j:.";::Qafe:".j 2,160 2,088.5 0.0 2,064.2 0.0 7,578,081 2,649,900 2,498,511 95.6%

95.6%

94.7%

91.1%

4.4%

g~g'::.Cuaiula:trav'e:,:.3.:.':

45,840 33,096.2 0.0 32,588.4 0.0 119,595,086 41,877,700 39,401,831 71.1%

71.1%

70.4%

67.7%

7.7%

24.

25.

If Shutdown At End of Report Period, Estimated Date of Start-up:

N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast

~08 07 87 09 87 Achieved

~0/025 87 11 28 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 03/04 03/04 03/05 1400 1434 1535 0517 Stabilized RX power at 55%.

Commenced RX power ascension to 60$ at 5S per hour.

Stabilized RX power at -60%.

Commenced RX power increase to 70%.

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

03/05 03/06 03/07 03/07 03/31 2105 0100 0800 1345 2400 Commenced RX power increase to 80%.

Stabilized RX power at 80%.

Commenced RX power increase to 100%.

Stabilized RX power at 100%.

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 No.

Outage Method of Duration Shutting System Date Type'ours Reason'own Reactor'ER No.

Code'omponent Code~

Cause and Corrective Action to 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 S-Scheduled

'Reason:

'Method:

A-Equipment Failure(Explain) 1-Manual B-Maintenance or Test 2-Manual Scram C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-Operator Training & License Previous Month Examination 5-Reduction of 20% or F-Administrative Greater in the Past G-Operational Error 24 Hours H-Other (Explain) 9-Other-(Explain)

'Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

'Exhibit H-Same Source 15