ML17306A389

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Monthly Operating Repts for Dec 1991 for Palo Verde Nuclear Generating Station
ML17306A389
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 12/31/1991
From: Chavet K, James M. Levine
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
254-01878-JML-K, 254-1878-JML-K, NUDOCS 9201150137
Download: ML17306A389 (33)


Text

ACCELERATED DISjgUBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9201150137 DOC.DATE: 91/12/3 FACIL:STN-50-528 Palo Verde Nuclear Station, STN-50-529 Palo Verde Nuclear Station, STN-50-530 Palo Verde Nuclear Station, AUTH.NAME AUTHOR AFFILIATION CHAVET,K.A.

Arizona Public Service Co.

LEVINE,J.M.

Arizona Public Service Co.

RECIP.NAME RECIPIENT AFFILIATION 1

NOTARIZED:

NO DOCKET Unit 1, Arizona Publi 05000528 Unit 2, Arizona Publi 05000529 Unit 3, Arizona Publi 05000530 (formerly Arizona Nuclear Power (formerly Arizona Nuclear Power I

SUBJECT:

Monthly operating repts for Dec 1991 for Palo Verde Nuclear Generating Station.W/920113 ltr.

DISTRIBUTION CODE:

XE24D COPIES RECEIVED:LTR ENCL SIZE TITLE: Monthly Operating Report (per Tech Specs)

D NOTES:STANDARDIZED PLANT Standardized plant.

Standardized plant.

RECIPIENT ID CODE/NAME PD5 LA TRAMMELL,C INTERNAL: ACRS AEOD/DSP/TPAB NRR/DOEA/OEAB RGN5 EXTERNAL: EGGG BRYCE,J.H NSIC NOTES COPIES LTTR ENCL 3

3 1

1 10 10 1

1 1

1 1

1 1

1 1

1 1

1 RECIPIENT XD CODE/NAME PD5 PD THOMPSON,M AEOD/DOA NRR/DL~/&PER.0

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05 NRC PDR COPIES LTTR ENCL 1

1 1

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05000528A 05000529 05000530 D D

NOTE TO ALL"RIDS" RECIPIENTS:

D D

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 26 ENCL 26

I

c.

Arizona Public Service Company PALO VERDE NUCLEAR GENERATING STATION P.O. BOX52034

~

PHOENIX, ARIZONA85072-2034 JAMES M. LEVINE VICE PRESIDENT NUCLEAR PRODUCTION 254-01878-JML/KAC January 13, 1992 Docket Nos.

STN 50-528/529/530 U.

S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-37 Washington, D.C.

20555

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2,

and 3

Monthly Operating Reports for December 1991 File:

92-024-404; 92-056-026 Attached are the Monthly Operating Reports for December.

1991, 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 Mr. Kent A. Chavet at (602) 340-4718.

Very truly yours, JML/KAC/kac Attachments cc:

J.

B. Martin D.

H.

Coe A. C. Gehr A. H. Gutterman INPO Records Center Utility Data Institute (all w/attachments)

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NRC MONTHLY OPERATING REPORT DOCKET NO.

50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY K.A Chavet OPERATING STATUS 1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

Unit Name:

Palo Verde Nuclear Generatin Station Unit 1 Reporting Period:

December 1991 Licensed Thermal Power (MWt):

3800 Nameplate Rating (Gross MWe):

1403 Design Electrical Rating (Net MWe):

1220 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.

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~g',Uni<>>;",.'Ca'j'i'i'i$j~:;:FiiCii",,";:(Ui,:in'j~,"'.MDC:.;.',.

Pj:.Vn'it!!'Po'i,'c:e'O',.:; Outa'i;::';l'Ra 744 744.0 0.0 744.0 0.0 2,822,439 980,400 928,678 100.0%

100.0%

102.2%

98.3S 0.0s 8,760 7,598.9 0.0 7,568.5 0 '

28,470,155 9,876,100 9,312,140 86.4a 86.4s 87.la 83.7S 2.8s

"'..';'.;:,.Cmul'at'i v'el.";'.;

51,936 29,059.1 0.0 28,322.1 0.0 103,864,256 36,048,700 33,824,792 54.5%

54.5%

53.3%

51.3%

20.2%

24.

Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): Refuelin outa e

Februar 15 1992 70 da s

25.

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

N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast

~05 85 06 85 11 85 Achieved 05/525 85 06 10 85 01 28 86 1

I AC

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY K.A. Chavet MONTH:

December 1991 DAY AVERAGE DAILY POWER LEVEL I

DAY AVERAGE DAILY POWER LEVEL 1245 1251 1246 18 1249 1246 19 1250 1244 20 1250 1252 21 1242 1254 22 1248 1253 23 1248 1252 24 1248 1251 25 1249 10 1248 26 1251 1250 27 1241 12 1252 28 1220 13 1252 29 1248 14 1250 30 1249 15 1251 31 1250 16 1251 2

f v

REFUELING INFORMATION DOCKET NO.

50-528 UNIT NAME PVNGS-1 DATE COMPLETED BY K.A. Chavet Scheduled date for next refueling shutdown.

02/15/92, 3rd refueling Scheduled date for restart following refueling.

04/26/92 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes.

Figures 3.2-2 and 3.2-2A of the Technical Specifications will require revision to reflect different DNBR margin limits.

Scheduled date for submitting proposed licensing action and supporting information.

Information to support the revision to Figures 3.2-2 and 3.2-2A was submitted on 12/24/91.

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 Unit 1 Cycle 4 nuclear design was performed using the DIT, ROCS, and MC computer codes described in Topical Report CENPD-266-P-A with the improvements in anisotropic scattering, higher order interface

currents, nodal expansion
method, and assembly discontinuity factors.

Biases and uncertainties used in the Unit 1 Cycle 4 analysis were established by comparing results obtained from analytical calculation with measured data to insure that 95/95 confidence limits are maintained in the safety analysis.

The number of fuel assemblies.

a)

In the core.

241 b)

In the spent fuel storage pool.

188 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.

2004 (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'OMPLETED BY K A Chavet December 1991 12/01 12/31 0000 2400 4

Unit began the month in Mode 1, 100%

RX power.

Ended the month in Mode 1, 100%

RX power.

4

g

SHUTDOWNS AND POWER REDUCTIONS December 1991 DOCKET NO 50-528 UNIT NAME PVNGS-1 DATE CV

'OMPLETED BY K.A. Chavet No.

Outage Method of Duration Shutting System Date Type Hours Reason Down Reactor LER No. Code'ause and Corrective Component Action to Codes Prevent Recurrence No reactor shutdowns or significant power reductions occurred during the month.

~F-Forced S-Scheduled

~Reason:

A-Equipment Failure(Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & 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 Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

~Exhibit H-Same Source 5

~

C

0 NRC MONTHLY OPERATING REPORT DOCKET NO.

50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY K.A. Chavet OPERATING STATUS 1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

Unit Name:

Palo Verde Nuclear Generatin Station Unit 2 Reporting Period:

December 1991 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

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0.0 0.0 0.0 0

0 0

0.0%

0.0s 0.0%

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74.3s 3.5s 0

30,714.3 0

112,946,218 39,406/070 36,890,215 66.3a 66.3s 65.2e 62.7s 7.4s 24.

Shutdowns Scheduled Over Next 6 Months (Type, Date and Duration of Each): Unit was shut down for refuelin outa e on October 17 1991.

25.

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

Refuelin outa e ended on 1

8 92.

INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast

~03 86

~06 86

~11 86 Achieved Ok/618 86 05 20 86 09 19 86 6

0 f

I

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY K A Chavet MONTH:

December 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 17 18 19 20 21 22 23 24 25 10 26 27 12 28 13 29 14 30 15 16 7

REFUELING INFORMATION DOCKET NO.

50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY K.A. Chavet Scheduled date for next refueling shutdown.

Unit was shut down on 10/17/91 for refueling.

Scheduled date for restart following refueling.

The refueling outage ended on 1/8/92.

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

No.

Analyses indicate that no proposed Technical Specification change or other license amendment will be required as a result of the next refueling.

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 Unit 2 Cycle 4 nuclear design was performed using the DIT, ROCS and MC computer codes described in Topical Report CENPD-266-P-A with improvements in anisotropic scattering, higher order interface

currents, nodal expansion method and assembly discontinuity factors.

The increased accuracy of the improved methodology was not credited in the safety analysis, as the larger of the uncertainties associated with the previous code versions and improved code versions was used.

This approach yielded the most conservative results.

The Unit 2 Cycle 4 reload is otherwise typical of other PVNGS cycles.

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.

2004 (18 Month reloads and full core discharge capability).

8

I

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH UNIT NAME PVNGS-2 DATE COMPLETED BY K A Chavet December 1991 12/01 12/12 12/31 12/31 0000 1831 0501 2400 Began the month in Mode 6 with core reload in progress.

Entered Mode 5.

Entered Mode 4.

Unit ended the month in Mode 4 with RCS heat-up to Mode 3 in progress.

9

I P

SHUTDOWNS AND POWER REDUCTIONS December 1991 DOCKET NO 50-529 UNIT NAME PVNGS-2 DATE COMPLETED BY K.A, Chavet No.

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

Code Cause and Corrective Component Action to Code~

Prevent Recurrence 91-06 10/17/91 S

744.0 N/A N/A N/A Unit shut down for scheduled refueling outage.

~F-Forced S-Scheduled

~Reason:

A-Equipment Failure(Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & 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) 4Exhibit F-Ins truetions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

~Exhibit H-Same Source 10-

NRC MONTHLY OPERATING REPORT DOCKET NO.

50-530 UNIT NAME PVNGS-3 DATE

  • K OPERATING STATUS 1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

Unit Name:

Palo Verde Nuclear Generatin Station Unit 3 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

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744 744.0 0.0 744.0 0.0 2,813,447 992,700 938,700 100.0%

100.0%

103.3%

99.3%

0.0%

.::.~j~Yx:",',:.">>,':to~<<'Ba,te>'..,

8,760 6,418.0 0.0 6,276.2 0.0 22,905,182 8,010,400 7,518,450 71 '%

71.6%

70.3%

67.6%

10.4%

g~~':qj,CUBI'a52v8:":::;-'4,896 23,997.7 0.0 23,599.4 0.0 86,511,409 30,318,700 28,517,925 67.6%

67.6%

66.9%

64.3%

9.2%

25.

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

N A INITIALCRITICALITY INITIALELECTRICITY COMMERCIAL OPERATION Forecast

~07 8

~07 87

~09 87 Achieved

~10 25 8

11 28 87 01 08 88 11

t I

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY K A Chavet MONTH:

December 1991 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1109 17 1268 1262 18 1266 12 0

19 1269 2

1 20 1271 1270 1269 1269 22 1269 1269 23 1270 26 24 68 1265 25 1269 10 1264 26 1269 1266 27 1260 12 1270 28 1241 13 1271 29 1267 14 15 1272 1270 30 31 1268 1271 16 1268

It E>>

~

~

~

~

~

REFUELING INFORMATION DOCKET NO.

50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY K A Chavet Scheduled date for next refueling shutdown.

09/15/92, 3rd refueling Scheduled date for restart following refueling.

11/14/92 Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

The need for a Technical Specification change or other license amendment has not yet been determined.

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.

A Technical Specification change request was submitted to the NRC on December 20, 1991 to allow the use of advanced zircaloy-based cladding alloys instead of Zircaloy-4 on up to 80 fuel rods in two fuel assemblies.

The number of fuel assemblies.

a)

In the core.

241 b)

In the spent fuel storage pool.

192 Licensed spent fuel storage capacity.

13 9

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

~

~

L

~

t I

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.

50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY K A. Chavet December 1991 12/01 12/01 12/31 0000 1709 2400 Unit began the month in Mode 1; 70%

RX power.

RX power at 100%.

Ended the month in Mode 1; 100%

RX power.

14

~

~

SHUTDOWNS AND POWER REDUCTIONS December 1991 DOCKET NO 50-530 UNIT NAME PVNGS-3 DATE COMPLETED BY K.A. Chavet No.

Outage Method of Duration Shutting System Date Type Hours Reason Down Reactor LER No. Code'ause and Corrective Component Action to Code~

Prevent Recurrence No reactor shutdowns or significant power reductions occurred during the month.

~F-Forced S-Scheduled

~Reason:

A-Equipment Failure(Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & 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) 4Exhibit F-Instructions for Preparation of the Data Entry Sheets for Licensee Event Report (LER) File (NUREG 0161)

~Exhibit H-Same Source

- 15