ML17310A698

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Monthly Operating Repts for Sept 1993 for Palo Verde Nuclear Generating Station Units 1,2 & 3
ML17310A698
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 09/30/1993
From: Ecklund B
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17310A697 List:
References
NUDOCS 9310190212
Download: ML17310A698 (26)


Text

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

'DR

NRC MONTHLYOPERATING REPORT DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50-528 PVNGS-1 10/04/93 B. S. Ecklund 602 340-4068 OPERATING STATUS 1.

2.

3.

4 5.

6.

7.

8.

9 10.

Unit Name:

Palo Verde Nuclear Generatin Station Unit 1 Reporting Period:

Se tember 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 IfChanges Occur In Capacity Ratings (Item Numbers 3 Through 7)

Since Last Report, Give Reasons:

N/A Power Level to Which Restricted, IfAny (Net MWe):

None Reasons For Restrictions, IfAny:

N/A 12 13 14 15 16 17 18 19 20 21 22 23 HOuf8~irI!Re.Oitin

";.P<<&red

',i.'.lie,"gi%igK':5'll!ilia'".'!$)pe~<.'i'i'ilialiliesi!i';!li%iii"i%"'""?

Hours:Reactofiwas:,CAttG81 ':~j%@gg':'::ll::"':""'.:-' '::i ':"'i-";-:':-:

Rea'otor..;:Reset'e;.:'8'fi5tig@i'tt Haurs::,;",::.::::

HotlrS.'9erte fatOWtas','OA tlAe",::.;:,%@i.~Le:,,"::~%::;::;i:;:.:,,,~<<Xi'.':<:.,'.;:i,i'.::<<:;:!~~jP VAN::ReseNN'!Sh9tttbwA:;::,Hours'4>',@'""'45Ãs'i~~8

'""%@~555<<~~rr':

Grog's'::.;7hemiaI.::Ene'rg j'0'en'e'ra'ted!

0m'ss':Efeotri8aI'.,:Eji'erjjj",Q'erie'ra<<te5.::. :(

U'riR::.'A%a<<)la<<blINj:.:::.Ficta'r':',(:f~):;":,'i;;:;:g.,::::,;:,:;::,':;:;:;:;;".:';:i::::,

UiiR':.,Ca'p'aclt j'!Fa'Ctor::,:,(

Urift'.,Forceful:;;QtiRi5e::,Rate~',(ia):

5!!';.!':':::'::':';-'i:::.:,'.::::-',::;:.:,'::,:::';::::;:,::::';:;;.:.:;.'::.;,-:;:,:

720 72.0 0.0 72.0 0.0 174,976 58,400 47,395 10 0%

10 0%

54 2%

00%

6,552 5,873.7 0.0 5,822.0 0.0 20,667,595 7,123,700 6,690,681 88 9%

88 9%

83 6%

804 1.4 67,272 41,049.3 0.0 40,155.8 0.0 146,446,606 50,753;900 47,634,277 59.7%

59 7%

58.0%

55 8%

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.

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

11/23/93 INITIALCRITICALITY INITIALELECTRICITY COMMERCIALOPERATION Forecast 05/85 06/85 11/85 Achieved 05/25/85 06/10/85 01/28/86

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE KL526 MbK~

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

REFUELING INFORIVIATION DOCKET NO.

UNITNAME DATE COMPLETED BY TELEPHONE 50-528 PVNGS-1 10/04/93 B. S. Eckiund 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 I

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE SH26 EHRki 1QQHL92 9 '~a!duad 09/01 09/03 09/04 09/05 09/05 09/11 09/20 09/30 0000 2137 0001 0443 1549 1402 0429 2400 Unit began the month in Mode 1, approximately 65% RX power, with end of core life coastdown in progress.

Commenced borating to reduce RX power in preparation for refueling outage.

RX manually tripped. Unit entered Mode 3.

Entered Mode 4.

Entered Mode 5.

Entered Mode 6.

Core off-load completed.

Exited Mode 6, Unit defueled.

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 No.

Outage Duration Date Type Hours Method of Shutting Reason Down Reactor LER No.

System Code4 Component Code5 Cause and Corrective Action to Prevent 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 S-Scheduled Reason:

A-Equipment Failure(Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Examination F-Administrative G-Operational Error H-Other (Explain)

Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20% or Greater in the Past 24 Hours 9-Other-(Explain)

Exhibit F-Instructions for Preparation ofthe Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161) 5Exhibit H-Same Source

AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE lg lpga MIGH.

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

REFUELING INFORMATION DOCKET NO.

UNITNAME DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 10/04/93 B. S. Eckiund 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 t

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

UNITNAME DATE COMPLETED BY TELEPHONE 50-529 PVNGS-2 10/04/93 B. S. Ecklund 602 340-4068 Se tember 1993 09/01 09/01 09/01 09/02 09/02 09/06 09/06 09/06 09/06 09/10 09/1 1 09/13 09/13 09/14 0000 0111 0150 0415 2220 0130 1330 1510 2125 1710 0200 1347 1650 1436 Began the month in Mode 1, turbine off-line for overspeed testing.

Synchronized main turbine to grid. Official end of refueling outage.

RX power stabilized at 18'or planned post-refueling outage power ascension testing.

Commenced RX power ascension to 70lo.

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

Commenced RX power increase to 90/o.

Stopped RX power increase at 90 '.

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

Stabilized RX power at 100/o.

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

RX power stabilized at 80/o.

Commenced RX power increase to 89%%d.

Stabilized RX power at 89 h.

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 09/23 09/30 1932 2352 2400 Commenced downpower from 89/o RX power per plant management to reduce RCS temperature and decrease the probability of a SG tube failure.

RX power stabilized at 85k.

Ended month in Mode 1, 85% RX power.

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

"o.

Date Outage Duration Type Hours Reason Method of Shutting Down Reactor LER No.

System Code4 Component Code5 Cause and Corrective Action to Prevent 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 S-Scheduled Reason:

A-Equipment Failure(Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Examination F-Administrative G-Operational Error H-Other (Explain)

Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20% or Greater in the Past 24 Hours 9-Other-(Explain)

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

Exhibit H-Same Source I

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'I t-Jt jl I

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO.

UNITNAME DATE COMPLETED BY TELEPHONE SLHQ MbLGR2 1QLQSL92 L 'Malduad MONTH: September 1993 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 10 12 13 14 15 16 1242 1242 1243 1238 1240 1241 1244 1248 1246 1243 1220 1222 1238 1249 1249 1250 17 18 19 20 21 22 23 24 25 26 27 28 29 30 1253 1256 1255 1256 1252 1252 1248 958 916 980 1058 1056 1056 1063

REFUELING INFORMATION DOCKET NO.

UNITNAME DATE COMPLETED BY TELEPHONE SLKR EHK2 10LML92 9 '~cldund 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 limitfrom 1.24 to 1.30. These are generic Tech. Spec. changes, and willbe 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.

The number of fuel assemblies.

e) tn the core.~

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.

UNIT NAME DATE COMPLETED BY TELEPHONE SH39 EHK2 MAM 9 'Mukluk 09/01 09/24 09/24 09/26 0000 0100 0604 1200 Unit began the month in Mode 1, 100% RX power.

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

RX power stabilized at 75% for chemistry clean-up of steam generators.

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

09/26 09/30 1400 2400 RX power stabilized at 85% to reduce RCS temperature and decrease the probability of a SG tube failure.

Unit ended the month in Mode 1, 85% RX power.

SHUTDOWNS AND POWER REDUCTIONS September 1993 DOCKET NO

~39 UNITNAME LVHGM DATE

~/6LKi COMPLETED BY

~XQEIIQQ No.

Date Outage Duration Type Hours Method of Shutting Reason Down Reactor LER No.

System Code4 Component Code5 Cause and Corrective Action to Prevent 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 S-Scheduled 2Reason.

A-Equipment Failure(Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training 8 License Examination F-Administrative G-Operational Error H-Other (Explain) 3Method:

1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction of 20% or Greater in the Past 24 Hours 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 I,