ML17310B216

Monthly Operating Repts for Mar 1994 for PVNGS Units 1,2 & 3

ML17310B216
Person / Time
Site:	Palo Verde
Issue date:	03/31/1994
From:	Ecklund B ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17310B215	List: ML17310B214 ML17310B216
References
NUDOCS 9404180395
Download: ML17310B216 (17)

Text

I t NRC MONTHLY OPERATiNG REPORT DOCKET NO.52525 UNIT NAME 22~DATE MOD COMPLETED BY MMG!~1.Unit Name: Palo Verde Nuclear Generating Station, Unit 1 2.Reporting Period: March 1994 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 MWe): None 10.Reasons For Restrictions, If Any: N/A 13.Rea'star,::Re's'e'rv'e:::,,8hiitdaw'ri";:.'Haiirs':,'::.::,::,',:i 14.Hai'i'rs,:0'e'iie rata 15.UiiIt':Reserve':;Shiitdo'w j,HS6:::.'eigg.'.Ir.'.qg;;:::::<.:........'.......!::~m@e;:

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6'ra'ss.:Ele'ctjicat,::Ei)erg'.:,'Geii'excited:.::(lNWH):

18.Net::;Efeckri~'~l:::,,E'rI'erg j.19.Uriit::.'8 21.U'nit".Cap)'i".ibj.';:F,'acta'i':,;(0'iin'g'!I 22.UIIIt:::::.C'i'pa'citjj'.Fjctai.'.(U'sliig':,0 23.U'rii,t f ore'e.'d:::;

744 744.0 0.0 744.0 0.0 2,397,621 838,000 784,102 100.0%100.0%86.3%83 0%0.0%2,160 2,160.0 0.0 2,160.0 0.0 6,969,924 2,449,800 2,294,736 100 0%100 0%87 0%83 7%0.0%71,640 44,117.4 0.0 43,159.9 0.0 156,000,472 54,104,400 50,753,097 60.2%60.2%58.0%55 8%15.1%24.Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): N/A 25.If Shutdown At End of Report Period, Estimated Date of Start-up: N/A INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 94Oe<aO395 5OOO528 qjpiia PgR AgQCK 05 Forecast 95'QLLi 12K Achieved Q5I25LK

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.QL529 UNIT NAME LVHG.R1 DATE MLQGLK COMPLETED BY MMQklLlQ5l MONTH: March 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1083 17 1073 1083 18 1075 1083 19 1072 1079 20 1072 622 21 1072 988 22 1075 1077 23 1078 1077 24 1078 1077 25 1078 10 1078 26 1075 1079 27 1074 12 1079 28 1074 13 1078 29 1074 14 1076 30 1071 15 1075 31 1076 16 1074 REFUELING INFORMATION DOCKET NO.59-529 UNIT NAME~59~DATE HLQEK COMPLETED BY 9'MQkllKLC laRIRMW Scheduled date for next refueling shutdown.The 5th refueling outage is tentatively scheduled for 04/02/95.Scheduled date for restart following refueling.

06/21/95.Will refueling or resumption of operation thereafter require 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.

N/A.The number of fuel assemblies.

b)In the spent fuel storage pool.Licensed spent fuel storage capacity.Intended change in spent fuel storage capacity.~!le 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.~25 UNIT NAME EL~DATE MQEK COMPLETED BY 9 l~GklLIQC 03/01 0000 03/04 2300 Unit began the month in Mode 1, 86 RX power.Commenced power decrease to 50%for steam generator cleanup and extraction drain pump"A" maintenance.

03/05 0659 03/06 0030 03/06 0915 03/31 2400 Stabilized RX power at 51%.Began power increase from=51%to 86%.Stabilized RX power at 86%.Unit ended the month in Mode 1, 86%RX power.

SHUTDOWNS AND POWER REDUCTIONS March 1994 DOCKET NO$4526 UNIT NAME~VGS='L DATE g4I(~I/COMPLETED BY~BF~~I ilP2MtSR No.Date Outage Method of Duration Shutting Down Type" Hours Reason2 Reactor3 LER No.System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence 94-01 03/04/94 34.3 N/A N/A N/A Reduction of RX power to 51%for steam generator cleanup and extraction drain pump"A" maintenance.

1F-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) 4Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER)File (NUREG0161)

Exhibit H-Same Source NRC MONTHLY OPERATING REPORT DOCKET NO.~29 UNIT NAME MHGR2 DATE MlQBLR4 COMPLETED BY EUMQklUQSf 1 2 3 4 5 6 7 8 9 10 Unit Name: Palo Verde Nuclear Generating Station, Unit 2 Reporting Period: March 1994 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 MWe): None Reasons For Restrictions, If Any: N/A[g<'Tliief Meiifh!!;:;:,':::,::kl;:.',::

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744 232.0 0.0 2,160 400.6 0.0 66,024 44,949.1 0.0 14 Ha'ure',;,,'0'e'i'i'e'ratar misQii-.,'87.1 355.7 44,035.6 15 16 Unit:Ri'sepia'::8h'utjaw'n';:Ha'urs~):

Gro'ss:.',Ther'mat,:EiiirjySe'n'i rated<(MWH);;::"::,:,::j(g~

17.GereassEte'r'tihaJ'6iii r'gey'6'enerate'dl/MNH)";:,".,';':~!;.::':~":,:::LP:,'::

0.0 411,841 134,000 0.0 946,633 320,900 0.0 160,780,878 55,983,870 18 19 20 Neetf6f'e'c'trtcat,:::Eries jy,::6i'i'ierated..'(NINH):,'-,'.::j!:'-:,~",,;:;:">:"",..'.'nit":8ervlc'O',:.Facfcir:('lo)':.':,:':!i~)i::-,':!;,::!:':::,;::,.:::::!!:::,"::;:~

109,153 25 1%25 1%12.0 278,205 16.5%16 5%10 5%52,398,239 66.7%66.7%65 0%22.Ujjlt:::;Capi'citjjFaota'i;."(Usln6:;GER.:Net).':;:::.';:::;::;:::;:fj;g-~:,:::.,':!:;

23.UiiIt,':Farci.'d~'0'uta ji:::.Rat 11.6%13 7%10 1o/o 62.5%6.1%24.Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): NIA 25.If Shutdown At End of Report Period, Estimated Date of Start-up: NIA INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OP ERATION-6-Forecast 93lK Q6LK 12K Achieved MLNQ5 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.59-529 UNIT NAME EEKiR2 DATE QdQELR4 COMPLETED BY MMQ!5KKf MONTH: March 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 17 18 19 20 21 22 23 125 24 239 25 186 10 26 27 400 12 28 140 13 29 1064 14 30 1071 15 31 1076 16 REFUELING INFORMATION DOCKET NO.~29 UNIT NAME DATE ALGER COMPLETED BY MM&lQ05l coerce Scheduled date for next refueling shutdown.The 5th refueling outage is scheduled for 02/01/95.Scheduled date for restart following refueling.

04/22/95.Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

A change mgy.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.

10/13/94.Important Licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes ln 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.

et In the core.~b)In the spent fuel storage pool.~5 Licensed spent fuel storage capacity.~29 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).

l t

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.I 9-'j29 UNIT NAME EL5GR2 DATE QCQGLK COMPLETED BY EL5~klQEi 51gKltL1996 03/01 0000 Unit began the month in Mode 5, mid-cycle outage in progress.03/15 2013 Entered Mode 4.03/19 1519 Entered Mode 5.03/21 1546 RX critical.Entered Mode 2.03/22 0000 Entered Mode 1.03/22 2309 Synchronized main turbine/generator to the grid.03/23 0310 Commenced plant power increase from 13/o to 18/o.03/23 0350 RX power at 20/o.Downcomer swap over did not occur.Commenced RX power reduction to 14'/o.03/24 0400 At 17/o plant power swap over of SG01 Feedwater Control System occurred.RX power stabilized at 17/o.03/23 0440 Commenced plant power reduction to 13/o to investigate problem with Feedwater Control System.03/23 0525 Stabilized RX power at~13'/o.03/23 1530 Commenced raising RX power to 18.5'/o after repairing a broken wire in the Feedwater Control System cabinet.03/23=1800 Stabilized RX power at 18.5/o.03/23 2135 Commenced increasing RX power to 29.5'/o.03/24 0445 Stabilized RX power at 29./o/o.03/25 1802 Commenced RX power reduction to 20/o for RX shutdown due to RCP 1A oil leakage from a loose fitting.03/25 1815 Manually tripped RX from the Control Room.Entered Mode 3.03/26 0853 Commenced RX start-up after the fitting on RCP 1A was tightened.

03/26 1028 RX critical.Entered Mode 2.03/26 1222 Entered Mode 1.03/26 1530 EHC PMG+24V power supply drifted low.Plant management decided to replace the power supply before continuing with startup.

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH (Con't)March 1994 03/26 1714 03/26 1800 03/26 2357 03/28 1134 03/30 1020 03/30 1057 03/31 2400 Commenced power reduction to 8/o.Stabilized RX power at 8'/o.Synchronized main turbine/generator to the power grid.Commenced power ascension to 85/o RX power at 3/o per hour.Stopped power ascension as necessary to perform operational surveillance testing and high rate SG blowdown.RX power stabilized at 85/o.Commenced RX power increase to 86/o.Stabilized RX power at 86/o.Unit ended the month in Mode 1, 86/o RX power.-9a-SHUTDOWNS AND POWER REDUCTIONS March 1994 DOCKET NO~~9 UNIT NAME MbK&2 DATE+~/9 COMPLETED BY kg~in IRRRCHM No.Date Outage Method of Duration Shutting Down Type" Hours Reason2 Reactor3 LER No.System Component Cause and Corrective Action Code4 Code5 to Prevent Occurrence 94-01 01/08/94 94-02 03/25/94 527.2 29.7 N/A N/A N/A N/A N/A N/A Continuation of planned mid-cycle from previous month.Manually tripped RX to repair oil leakage from a loose fitting on RCP 1A.1F-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) 4Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER)File (NUREG0161) 5Exhibit H-Same Source NRC MONTHLY OPERATING REPORT DOCKET NO.¹HQ UNIT NAME LVHRR2 DATE MLQ9lk4 COMPLETED BY~MRS!LED IERIBSBM 1 2 3 4 5 6 7 8 9 10 Unit Name: Palo Verde Nuclear Generating Station, Unit 3 Reporting Period: March 1994 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 MWe): None Reasons For Restrictions, If Any: N/A 12 13 14 15 16 17 18 19 20 21 22 23 H'aii'is:.'.'0'eii'era'torw'i~,o)'i-::f.:I'i';:::::,jinni,."::::;:QIji~($

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744 432.6 0.0 432.6 0.0 1,411,156 499,000 462,290 58.1%58 1 50.9%48 9%p.p@j,;:::Yfj':,tojPite':.',,'~@

2,160 1,848.6 0.0 1,848.6 0.0 5,995,571 2,120,500 1,976,048 85.6%85.6%74 9%72.0%pp Ni";::::;::::,Qimulat))i,',.-.',,-:;:

54,600 40,864.5 0.0 40,272.7 0.0 146,666,831 51,342,400 48,274,269 73.8%73 8%72.4%69 6%6.6 24 25 Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): 4th Refueling outage began March 19, 1994.80 days duration.If Shutdown At End of Report Period, Estimated Date of Start-up: 06/07/94 INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION-11-Forecast QZSZ QZLGZ QKQ7 Achieved Kl25$Z AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.59-539 UNIT NAME ELbLGR2 DATE QdLQGLK4 COMPLETED BY MMQRlUQSt MONTH: March 1994 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1088 17 1083 1085 1045 1089 19 1090 20 1084 21 1085 22 1086 23 1090 24 1085 25 10 1086 26 1088 27 12 1090 28 13 1090 29 14 1087 30 15 1087 31 16 1084 REFUELING INFORMATION DOCKET NO 5~UNIT NAME 2289M DATE MLQUlk4.COMPLETED BY jL~hMQklLESl eeorere Scheduled date for next refueling shutdown.03/19/94, 4th refueling.

Scheduled date for restart following refueling.

06/07/94.Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

At present, four Tech.Spec.changes are in process.One for increasing the radially averaged weight percent of U235 in fuel rods to 4.30w/o.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.Also, there are two other Tech.Spec.changes that will allow U3C5 to operate at 100%power due to the steam generator issues.Scheduled date for submitting proposed licensing action and supporting information.

The fuel enrichment change was submitted in October 1993 and the DNBR setpoint change was submitted in January 1994.important Licensing considerations associated with refueling, e.gnew 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 4.30w/o 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 Zlrcaloy<)

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).

t t

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.5~UNIT NAME LVHGR2 DATE MLQGLK COMPLETED BY~~I5IUM 03/01 0000 03/18 2123 03/19 0034 03/1 9 1303 03/20 0449 03/26 1505 03/31 2400 Unit began the month in Mode 1, 86%RX power.Commenced downpower in preparation for commencement of 4th refueling outage.Manually tripped RX with power at 21%.Entered Mode 3.Entered Mode 4.Entered Mode 5.Entered mode 6.The RX vessel head detensioned.

Unit ended the month in Mode 6, with the 4th refueling outage in progress and fuel off-load in progress.

March 1994 DOCKET NO SL5K UNIT NAME PVNQ5-3.DATE~04I 8/94 COMPLETED BY~B.EckI 0 No.Date Outage Method of Duration Shutting Down Type" Hours Reason2 Reactor3 LER No.System Component Cause and Corrective Action Code Code5 to Prevent Occurrence 94-01 03/19/94 S 311.4 C 2 N/A N/A N/A RX manually tripped to begin the fourth refueling outage.1F-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) 4Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER)File (NUREG0161)

Exhibit H-Same Source