ML17310A906

Monthly Operating Repts for Dec 1993 for PVNGS Units 1,2 & 3

ML17310A906
Person / Time
Site:	Palo Verde
Issue date:	12/31/1993
From:	Ecklund B ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17310A905	List: ML17310A904 ML17310A906 ML17310A907
References
NUDOCS 9401270044
Download: ML17310A906 (29)

Text

ENCLOSURE 1 MONTHLYOPERATING REPORTS FOR DECEMBER 1993 R,

9401270044 940113 PDR

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. ~29 UNIT NAME ~59.~

DATE 92QZ/K4 COMPLETED BY MONTH: December 1993 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 815 17 1066 860 18 1067 1192 19 1068 1225 20 1064 1227 21 1066 1226 22 1066 1066 23 1057 8 1067 24 1065 1068 25 1065 10 1066 26 1064 1062 27 1065 12 1059 28 1068 13 1066 29 1069 14 1069 30 1067 15 1068 31 1068 16 1064

REFUELING INFORMATION l

DOCKET NO. RL526 UNIT NAME Mb!2&1 DATE QZQZLK COMPLETED BY ~hklUEKl Scheduled date for next refueling shutdown.

The 5th refueling outage is tentatively scheduled for 03/13/95.

Scheduled date for restart following refueling.

06/01/95.

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. ~og 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. g}-ggQ UNIT NAME E~~~

DATE 92QZLR4 COMPLETED BY MMal<JJl IHRIBSBM 12/01 0000 Unit began the month in Mode 1, 69% RX power. Post refueling power ascension testing was in progress.

12/02 1530 Commenced increasing RX power to approximately 98%.

12/03 0137 RX power stabilized at 90% and holding for performance of surveillance testing.

12/03 1015 RX power stabilized at 97.8% for post refueling outage power ascension testing.

12/06 2205 Commenced RX power reduction to 85%.

12/07 0059 Stabilized RX power at 85%.

12/07 0100 Commenced Tcold reduction to 556' for SG preservation.

12/07 0400 RCS temperature stabilized at 556'.

12/31 2400 Unit ended the month in Mode 1, 85% RX power.

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SHUTDOWNS AND POWER REDUCTIONS December 1993 DOCKET NO UNIT NAME ~Vi~

DATE ELZLK COMPLETED BY ~B'~+~

ISZ2kSH Outage Method of Duration Shutting Down System Component Cause and Corrective Action No. Date Type" Hours Reason2 Reactor3 LER No. Code4 Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of December, 1993.

1F Forced Reason: 3Method: 4Exhibit F - Instructions for Preparation S-Scheduled A-Equipment Failure(Explain) 1-Manual of the Data Entry Sheets for Licensee B-Maintenance or Test 2-Manual Scram Event Report (LER) File (NUREG0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from Previous Month E-Operator Training & License 5-Reduction of 20% or Greater in the Exhibit H-Same Source Examination Past 24 Hours F-Administrative 9-Other-(Explain)

G-Operational Error H-Other (Explain)

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. 5M22 UNIT NAME 22HGR2 DATE 93IQZLR4 COMPLETED BY ~~9k!LEE(

MONTH: December 1993 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 1060 17 1057 1062 18 1057 1063 19 1057 1061 20 1059 1060 21 1059 1059 22 1059 1059 23 1058 1059 24 1060 1056 25 1059 10 1059 26 1060 1057 27 '063 12 1057 28 1066 13 1059 29 1066 14 1057 30 1065 15 1057 31 1064 16 1056

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REFUELING INFORMATION DOCKET NO. QL529 UNIT NAME ~59.~

DATE Q2QZLR4 COMPLETED BY Scheduled date for next refueling shutdown.

The 5th refueling outage is tentatively scheduled for 09/17/94, however, it is more likely to take place in the first quarter of 1995.

Scheduled date for restart following refueling.

12/06/94, or 80 days following the new refueling shutdown date.

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

A change ~ 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 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 20' is currently planned.

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The number of fuel assemblies.

e) tn the core.

b) In the spent fuel storage pool.

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).

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

UNIT NAME EVHGR2 DATE 920ZLRC COMPLETED BY R '~NIUKl 12/01 0000 Unit began the month in Mode 1, 85% RX power.

12/31 2400 Unit ended the month in Mode 1, 85% RX power.

SHUTDOWNS AND POWER REDUCTIONS December 1993 DOCKET NO ~RQ UNIT NAME ~PV DATE Q1/(~/4 COMPLETED BY B F~~kl Outage Method of Duration Shutting Down System Component Cause and Corrective Action No. Date Type" Hours Reason2 Reactor3 LER No. Code4 Code5 to Prevent Occurrence No reactor shutdowns or significant power reductions occurred during the month of December, 1993.

"F-Forced Reason: 3Method: 4Exhibit F - Instructions for Preparation S-Scheduled A-Equipment Failure(Explain) 1-Manual of the Data Entry Sheets for Licensee B-Maintenance or Test 2-Manual Scram Event Report (LER) File (NUREG0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from Previous Month E-Operator Training 8 License 5-Reduction of 20% or Greater in the Exhibit H-Same Source Examination Past 24 Hours F-Administrative 9-Other-(Explain)

G-Operational Error H-Other (Explain)

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AVERAGE DAILYUNIT POWER LEVEL DOCKET NO. K=HO UNIT NAME EkbK~~-

DATE 92QZLR4 COMPLETED BY ~MQklLEEf MONTH: December 1993 DAY AVERAGE DAILYPOWER LEVEL DAY AVERAGE DAILYPOWER LEVEL 17 18 19 20 21 22 23 24 25 10 26 246 27 1014 12 28 1078 13 29 1077 14 30 1077 15 31 1077 16

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REFUELING INFORMATION DOCKET NO. K='5K UNIT NAME @VVI'~

DATE Q2lQZLK COMPLETED BY J~G~

ER18$ t6M 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 4.30w/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.

Scheduled date for submitting proposed licensing action and supporting information.

January 1994,if necessary.

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 4.30w/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 Zircaloy<) in two fuel assemblies during Unit 3 Cycles 4, 5, and 6 for in-reactor

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performance evaluation. Date of issuance was July 20, 1992.

The number of fuel assemblies.

a) In the core. ~~

b) In the spent fuel storage pool.

ly.

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).

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SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 59-'j39 UNIT NAME ~gg~

DATE ELQZLK COMPLETED BY ~~Qdlazf 12/01 0000 Unit began the month in Mode 4. RCS cooldown in progress for planned mid-cycle SG tube eddy current inspection.

12/01 0203 RCS temperature at 210'. Entered Mode 5.

12/01 0555 RCS temperature reached 114'. Stopped the cooldown. RCS pressure at 238 psia.

12/22 1920 Entered Mode 4.

12/23 0344 Entered Mode 3.

12/25 1347 RX critical. Entered Mode 2.

12/25 1749 " Entered Mode 1, increasing RX power to 11-12%.

12/26 0113 Synchronized the Main Turbine/Generator to the grid.

12/26 0306 Stopped RX power increase at 19%.

12/26 1252 Commenced RX power increase to 85% power at a target rate of 8% per hour.

12/26 1545 Suspended RX power increase at 36% to perform surveillance test, 12/26 1810 Recommenced increasing RX power to 85%.

12/26 2035 RX power at 50%. Reduction of Tcold to 556.5+/- 0.5' in progress.

12/26 2300 Tcold stabilized at 557'.

12/27 0118 Recommenced RX power increase to 85%.

12/27 0610 Stabilized RX power increase at 85%.

12/31 2400 Unit ended the month in Mode 1, 85% RX power.

SHUTDOWNS AND POWER REDUCTIONS December 1993 DOCKET NO K=539 UNIT NAME 22HGR2 DATE EL9ZlR4 COMPLETED BY ~B'MRIRK4 IKIIBHM Outage Method of Duration Shutting Down System Component Cause and Corrective Action No. Date Type" Hours Reason2 Reactor3 LER No. Code4 Code5 to Prevent Occurrence 93-08 11/29/93 S 601.2 N/A N/A N/A Continuation from previous month, planned mid-cycle SG tube eddy current inspection.

"F-Forced Reason: 3Method: 4Exhibit F - Instructions for Preparation S-Scheduled A-Equipment Failure(Explain) 1-Manual of the Data Entry Sheets for Licensee B-Maintenance or Test 2-Manual Scram Event Report (LER) File (NUREG0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from Previous Month E-Operator Training 8 License 5-Reduction of 20% or Greater in the Exhibit H-Same Source Examination Past 24 Hours F-Administrative 9-Other-(Explain)

G-Operational Error H-Other (Explain)