ML17310A698

Monthly Operating Repts for Sept 1993 for Palo Verde Nuclear Generating Station Units 1,2 & 3

ML17310A698
Person / Time
Site:	Palo Verde
Issue date:	09/30/1993
From:	Ecklund B ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17310A697	List: ML17310A696 ML17310A698 ML17310A699
References
NUDOCS 9310190212
Download: ML17310A698 (26)

Text

ENCLOSURE 1 MONTHLYOPERATING REPORT FOR SEPTEMBER 1993 93101'70212 931013 PDR ADQCK '5000528'

'DR

dOPERATING STATUS 1.

2.

3.

4 5.

6.

7.

8.

9 10.

Unit Name:

Reporting Period:

Palo Verde Nuclear Generatin Station Unit 1 Licensed Thermal Power (MWt): 3800 Nameplate Rating (Gross MWe):

Design Electrical Rating (Net MWe): 1270 Se tember 1993 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:

Power Level to Which Restricted, If Any (Net MWe): None Reasons For Restrictions, If Any: N/A NRC MONTHLYOPERATING REPORT 1403 N/A DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50-528 PVNGS-1 10/04/93 B. S. Ecklund 602 340-4068 HOuf8~irI!Re .Oitin ";.P<<& re ',i.'.lie,"gi%igK':5'll!ilia'".'!$)pe~<.'i'i'ilialiliesi!i';!li%iii"i%"'""? 720 6,552 67,272 12 Hours:Reactofiwas:,CAttG81 ':~j%@gg':'::ll::"':""'.: -' '::i ':"'i-"; -:':-: ::"':: 72.0 5,873.7 41,049.3 13 Rea'otor..;:Reset'e;.:'8'fi5tig@i'tt Haurs::,;",::.:::: 0.0 0.0 0.0 14 HotlrS.'9erte fatOWtas','OA tlAe",::.;:,%@i.~Le:,,"::~%::;::;i:;:.:,,,~<<Xi'.':<:.,'.;:i, i'.::<<:;:!~~jP 72.0 5,822.0 40,155.8 15 VAN::ReseNN'!Sh9tttbwA:;::,Hours'4>',@'""'45Ãs'i~~8 '""%@~555<<~~rr': 0.0 0.0 0.0 16 Grog's'::.;7hemiaI.::Ene'rg j'0'en'e'ra'ted! ';::::::::,';! ..::-,',:.':",',;:,:,:,:,:,::,:;,:,:,:,",:,:;:";::;:., 174,976 20,667,595 146,446,606 17 0m'ss':Efeotri8aI'.,:Eji'erjjj",Q'erie'ra<<te5.::. :( 58,400 7,123,700 50,753;900 18 47,395 6,690,681 47,634,277 19 10 0% 88 9% 59.7%

20 U'riR::.'A%a<<)la<<blINj:.:::.Ficta'r':',(:f~):;":,'i;;:;:g.,::::,;:,:;::,':;:;:;:;;".:';:i::::, 10 0% 88 9% 59 7%

21 UiiR':.,Ca'p'aclt j'!Fa'Ctor::,:,( 54 83 6% 58.0%

22 2% 804 55 8%

23 Urift'.,Forceful:;;QtiRi5e::,Rate~',(ia): 5!!';.!':':::'::':';-'i:::.:,'.::::-',::;:.:,'::,:::';::::;:,::::';:;;.:.:;.'::.;,-:;:,: 00% 1.4 16.0%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): Refuelin outa e Se tember 4 1993. 80da s.

25. If Shutdown At End of Report Period, Estimated Date of Start-up: 11/23/93 Forecast Achieved INITIALCRITICALITY 05/85 05/25/85 INITIALELECTRICITY 06/85 06/10/85 COMMERCIALOPERATION 11/85 01/28/86

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. KL526 UNIT NAME MbK~

DATE KDHM COMPLETED BY ELREalduod TELEPHONE MONTH: September 1993 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 763 17 761 18 722 19 20 21 22 23 24 25 10 26 27 12 28 13 29 14 30 15 16

REFUELING INFORIVIATION DOCKET NO. 50-528 UNIT NAME PVNGS-1 DATE 10/04/93 COMPLETED BY B. S. Eckiund TELEPHONE 602 340-4068 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 amendment?

Yes, required to add topical report "Sys 80" Inlet Flow distribution to Tech. Spec. Section 6.9.1.10.

Scheduled date for submitting proposed licensing action and supporting information.

Submitted 09/08/93.

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 G 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. 0 b) In the spent fuel storage pool. 609 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 (1 8 Month reloads and full core discharge capability).

I$

t

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH I

DOCKET NO. SH26 UNIT NAME EHRki DATE 1QQHL92 COMPLETED BY 9 '~a!duad TELEPHONE 09/01 0000 Unit began the month in Mode 1, approximately 65% RX power, with end of core life coastdown in progress.

09/03 2137 Commenced borating to reduce RX power in preparation for refueling outage.

09/04 0001 RX manually tripped. Unit entered Mode 3.

09/05 0443 Entered Mode 4.

09/05 1549 Entered Mode 5.

09/11 1402 Entered Mode 6.

09/20 0429 Core off-load completed. Exited Mode 6, Unit defueled.

09/30 2400 Ended month with the Unit defueled. Refueling outage in progress.

SHUTDOWNS AND POWER REDUCTIONS September 1993 DOCKET NO 50-528 UNIT NAME PVNGS-1 DATE 10/04/93 COMPLETED BY B. S. Ecklund Cause and Outage Method of Corrective Action Duration Shutting System Component to Prevent No. Date Type Hours Reason Down Reactor LER No. Code4 Code5 Recurrence 93-06 09/01/93 S N/A N/A N/A N/A Power reduction of greater than 20%

due to end of core life coastdown.

93-07 09/04/93 S 648 N/A N/A N/A Commenced refueling outage 1F-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 8 License Previous Month Examination 5-Reduction of 20% or F-Administrative Greater in the Past 5Exhibit H-Same Source G-Operational Error 24 Hours H-Other (Explain) 9-Other-(Explain)

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. lg lpga UNIT NAME MIGH.

DATE MMM COMPLETED BY 9 'Malduad TELEPHONE MONTH: September 1993 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 94 17 1113 422 18 1116 802 19 1115 815 20 1113 818 21 1114 1059 22 1113 1234 23 1106 1239 24 1053 1239 25 1061 10 1213 26 1058 978 27 1057 12 974 28 1059 13 1012 29 1057 14 1108 30 1058 15 1110 1112

REFUELING INFORMATION DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 10/04/93 COMPLETED BY B. S. Eckiund TELEPHONE 602 340-4068 Scheduled date for next refueling shutdown.

The 5th refueling outage is tentatively scheduled for 09/17/94.

Scheduled date for restart following refueling.

12/06/94.

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

A change may be required to Technical Specification 3.9.6 to raise the overload cutoff limit to accommodate the new fuel assembly modification. Also, Technical Specification Section 6.9.1.10 will be modified to add the new Inlet Flow Distribution methodology.

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.

The fuel assembly will consist of a denser fuel pellet, Erbium burnable absorber and guardian grid. A primary temperature drop of 10' is currently planned.

The number of fuel assemblies.

a) In the core. 241 b) In the spent fuel storage pool. 384 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).

W-1 t

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH t

DOCKET NO. 50-529 UNIT NAME PVNGS-2 DATE 10/04/93 COMPLETED BY B. S. Ecklund TELEPHONE 602 340-4068 Se tember 1993 09/01 0000 Began the month in Mode 1, turbine off-line for overspeed testing.

09/01 0111 Synchronized main turbine to grid. Official end of refueling outage.

09/01 0150 RX power stabilized at 18'or planned post-refueling outage power ascension testing.

09/02 0415 Commenced RX power ascension to 70lo.

09/02 2220 RX power stabilized at 69/o for planned post-refueling outage power ascension testing.

09/06 0130 Commenced RX power increase to 90/o.

09/06 1330 Stopped RX power increase at 90 '.

09/06 1510 Commenced RX power ascension to 100~/o by dilution.

09/06 2125 Stabilized RX power at 100/o.

09/10 1710 Commenced RX power decrease to 80/o for SG chemistry clean-up.

09/1 1 0200 RX power stabilized at 80/o.

09/13 1347 Commenced RX power increase to 89%%d.

09/13 1650 Stabilized RX power at 89 h.

09/14 1436 Directed by plant management to operate with T-cold at 5624 F. Commenced lowering T-cold from 564.5'.

09/14 1729 T-cold at 562.5 F.

09/23 1932 Commenced downpower from 89/o RX power per plant management to reduce RCS temperature and decrease the probability of a SG tube failure.

09/23 2352 RX power stabilized at 85k.

09/30 2400 Ended month in Mode 1, 85% RX power.

SHUTDOWNS AND POWER REDUCTIONS September 1993 DOCKET NO 50-529 UNIT NAME DATE COMPLETED BY PVNGS-2 10/04/93 B. S. Ecklund BW

"o.

Cause and Outage Method of Corrective Action Duration Shutting System Component to Prevent Date Type Hours Reason Down Reactor LER No. Code4 Code5 Recurrence 93-03 09/10/93 S N/A N/A N/A N/A Power reduction of 20% fol SG chemistry clean-up.

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 Entp Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG 0161)

E-Operator Training 8 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)

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. SLHQ UNIT NAME MbLGR2 DATE 1QLQSL92 COMPLETED BY L 'Malduad TELEPHONE MONTH: September 1993 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 1242 17 1253 1242 18 1256 1243 19 1255 1238 20 1256 1240 21 1252 1241 22 1252 1244 23 1248 1248 24 958 1246 25 916 10 1243 26 980 1220 27 1058 12 1222 28 1056 13 1238 29 1056 14 1249 30 1063 15 1249 16 1250

REFUELING INFORMATION DOCKET NO. SLKR UNIT NAME EHK2 DATE 10LML92 COMPLETED BY 9 '~cldund TELEPHONE 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?

At present, two Tech. Spec. changes are in process. One for increasing the radially averaged weight percent of U235 in fuel rods to 4.30%. The other is to change the DNBR setpoint limit from 1.24 to 1.30. These are generic Tech. Spec. changes, and will be implemented on a Unit by Unit basis, beginning with U3C5.

Scheduled date for submitting proposed licensing action and supporting information.

Started in July 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.

U3C5 will incorporate a new higher maximum enrichment level of 4.30% U235 and will also utilize a new integral burnable absorber, Erbium.

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<) in two fuel assemblies during Unit 3 Cycles 4, 5, and 6 for in-reactor performance evaluation. Date of issuance was July 20, 1992.

e) tn the core. ~

The number of fuel assemblies.

b) In the spent fuel storage pool.

Licensed spent fuel storage capacity.

Intended change in spent fuel storage capacity.

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).

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. SH39 UNIT NAME EHK2 DATE MAM COMPLETED BY 9 'Mukluk TELEPHONE 09/01 0000 Unit began the month in Mode 1, 100% RX power.

09/24 0100 Commenced RX power reduction to 75% at a rate not to exceed 5% per hour.

09/24 0604 RX power stabilized at 75% for chemistry clean-up of steam generators.

09/26 1200 Commenced increasing RX power from 75% to a target of 85%, while maintaining T-cold at 562'.

09/26 1400 RX power stabilized at 85% to reduce RCS temperature and decrease the probability of a SG tube failure.

09/30 2400 Unit ended the month in Mode 1, 85% RX power.

SHUTDOWNS AND POWER REDUCTIONS September 1993 DOCKET NO ~39 UNIT NAME LVHGM DATE ~/6LKi COMPLETED BY ~XQEIIQQ Cause and Outage Method of Corrective Action Duration Shutting System Component to Prevent No. Date Type Hours Reason Down Reactor LER No. Code4 Code5 Recurrence 93-05 09/24/93 S N/A N/A N/A N/A N/A Power reduction of 25% for SG chemistry clean-up.

"F-Forced 2Reason. 3 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 8 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)

I,