ML20141F237

Monthly Operating Rept for Oct 1985

ML20141F237
Person / Time
Site:	Palo Verde
Issue date:	10/31/1985
From:	Richardson M, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
ANPP-34034-EEVB, NUDOCS 8601090051
Download: ML20141F237 (7)

Text

e NRC MONTHLY OPERATING REPORT DOCKET NO. 50:52@

UNIT NAME PVNG@;l DATE 1140ZZ@5 COMPLETED BY M. P t Bichgedsgo TELEPHONE 602-932:5300 Ext. 6523 OEER911NG SIBIU@

1. Unit Name: Palg Verdg Nucigar Ggnerating Statiget Unit 1

2. Reporting Period:Qctgbgr 19@5

3. Licensed Thermal Power (MWt): 3@00

4. Nameplate Rating (Gross MWe): 1304

5. Design Electrical Rating (Net MWe): 12Z0

6. Maximum Dependable Capacity (Gross MWe):Ig be detgrmingd

7. Maximum Dependable Capacity (Net MWe): Tg bg dgtgrmingd

8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:__________________

______________________NLB________________________________

9. Power Level To Which Restricted, If Any (Net MWe):_NQNE____

10. Reasons For Restrictions, If Any: __________________________

This Month Yr.-to-Date Cumulative i

11. Hours In Reporting Period ___744____ ___3434___ __7296____

12. Number Of Hours Reactor Was Critical _ __3 86 . 3 ' _ _ ___18 4 5.3 _ __18 4 6.3 __

13. Reactor Reserve Shutdown Hours _____0____ _____0____ ____0____

14. Hours Generator On-Line ___394.3__ ___1602.3_ __1602.3_

15. Unit Reserve Shutdown Hours _____0____ _____0____ ____0____

16. Gross. Thermal Energy Generated _962,630__ 2,933,266_ 2,933,266_

(MWH)

17. Gross Electrical Energy Generated _321,700__ _858,100__ _858,100_

W (MWH)

Nm anA 18. Net Electrical Enerav Generated -279,267-- -696,869-- -696,869-88'

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(MwH) n 19. Unit Service Factor ___N/R____ ___N/A____ __N/A____

L~) 20. Unit Availability Factor ___N/A____ ___N/A____ __N/A____

-g 21. Unit Capacity Factor (Using MDC ___N/A____ ___N/A____ __N/A____

no Net) 00 00 22. Unit Capacity Factor (Using DER ___N/A____ ___N/A____ __N/A____

o Net) gg 23. Unit Forced Outage Rate ___N/A____ ___N/A____ __N/A____

ao 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and G'"

Duration of Each):__@utvgillgneg Tgst Qutagg - 34@6 t 49 days ______

25. If Shutdown At End Of Report Period, Estimated Date of Startup ______

11/ZS.f@Q______

26. Units In Test Status (Prior To Commercial Operation):

Forecast Achieved INITIAL CRITICALITY ___5/85_____ ___5/25/85___

INITIAL ELECTRICITY ___6/85_____ ___6/10/85___ gf COMMERCIAL OPERATION __11/85_____ _____N/A_____ [

17 ' }

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4 AVERAGE DAILY UNIT. POWER LEVEL DOCKET NO. 50:52@__

UNIT __PVN@@;1________

L 1

DATE _11/0ZZ@g COMPLETED BY_McP t Richardson 4'

TELEPHONE _602:932:3300

_Entt 6523_____

i c

JMONTH: October.1985

. DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

! (MWe-Net) (MWe-Net)

J 4

____886 17

~

1 _

561 __

2 734 _ _ _ '18._ _ 575_

3 380___ _

19 __702 _ _

1 4~ 0 20 _ 919___

5 e_______=_ _

21.__________937___

i 6 _0_ __ ___ 22 __ _ _ _ __ __ _ 9 22. _______

j 7 _ 0_ __ 23 ___912_ ___ __ __

8 _ ___O__ _

__ 24 _ _380_ __

9 _

0 _______ 25 _ _ O____ __ ____

le = - = O__ 26 ____ 0 ___________

j 11 _____ O_ _ _ _ ____ 27 _ ______0_ __

12L 239 - 28 __0______________

i

! 13 ' 893_ _ __ __ 29 _______0 _

__ =___-

14 _ _919________ 30 _ _ _ _ _;_0______________

15' -930. _ _.

31 ___________0. _ _ _ _ _ _ ____

16. _ __ _7 4 9__ _ _ _ __ _

( i

-. .. . ._- . . - . ~ . . - - - . - . - . - .- .=__ .- - _ _ - -

,8 T

, @UMMegy gE gEEBBIIN@ EXEE81gNCE EQB ISE MONId DOCKET. NO. ___50-58@ __. ________

UNIT ___ EVN@@-1 . _ . __

I DATE_=___ _ _ _ 11LOZLQ5 ___ ,

1 l COMPLETED'BY_McEu Bichardsgn__

TELEPHONE __60g-93g-5300

]

1 j Ext. 6593 i-

10/01/85_- 0700 Reactor power at-82%

10/02/85 - 1337 Decreasing power to 50% due to S/G chemistry, condenser tube' leak.  :

10/03/85 -- 1644 Reactor / turbine trip, _ lost S/U transformer feed to S05,506 13.8 KV buses resulting in loss of all non-class '

IE power with rated voltage )125V.

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. 10/03/85 '1658 Declared Notification of Unusual Event.

i 10/03/85'- 2035 Terminated Notification of Unusual Event, loss of power to SD5, 506 was plant, multiplexer malfunction.

10/07/85 - 1958 Loss of offsite power trip. Cause was technicians f

replacing microprocessor on local multiplexer terminal.

SO5 and SO6 were lost as on 10/03/85.

4 10/07/85.- 2003 Declared Notification of Unusual Event.

t i 10/07/85 - 2044 Terminated Notification of Unusual Event.

10/11/85 - 2241 Entered Mode 2.

10/12/85 --0016 Reactor critical.

10/12/85--'0113 ' Entered Mode 1, reactor power at '6%.

i- .

10/12/85' 1232 Synchronized main generator on line.-

10/12/85 - 1707 Reactor: power at 44%.

20/13/85.- 0108 Completed power, ascension to 80%, main generator at j 975 MWe.

I 10/16/85 - 1200 Began power decrease to-*50% power for testing.

L i 10/19/85 0900: ' Commenced power ascension.

a

. _ - - . -._,- _. _ u . ,u . . . . . _ _ _ . _ . _ , , _ _ . _ . _ . . . _ , _ _ .,_..._.,_._...... _ .,_ . ~ . _ . _ , _ . . . . . . . . .

NRC Monthly Report for October 10/19/85 - 1640 Reactor power at 70% power, main generator at 892 MWe.

10/20/85 - 0007 Reactor at 85% power, main generator at 1113 MWe.

10/24/85 - 0841 Switched from Aux. transformer to startup transformers in preparation for large load reject test.

10/24/85 - 1610 Manually tripped generator, to initiate large load reject reactor trip.

10/24/85 - 1011 MSIS, SIAS, CIAS, tripped 2B and 2A RCPs.

Reactor trip first out was S/G #2 low level. Notification of unusual Event declared at 1020 and terminated at 1111.

10/24/85 - 1011 Atmospheric Dump Valves being used for temperature control as required by MSIS.

10/24/85 - 1031 Broke condenser vacuum due to-MSIS.

10/29/85 - 1320 Started 2A RCp. Suffered a loss of power due to lockout on the SO3 to SO1 cross-tie breaker. It appears the actual tie bus between SO3B and SO1A caught fire and exploded.

10/29/85 - 2208 Entered Mode 4.

10/30/85 - 0657 Entered Mode 5.

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_ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ __ _-__ _ s' ~~ u

• , UNIT SHUTDOWNS AND POWER REDUCTIONS +

DOCKET NO Mn-99A

• UNIT NAME DATE PVNGS-I 11/U6/n)

. *'. k *

. j ,

COMPLETED BY M . I' . Ri c hn reinnn TELEPl10NC ' 4 U-Slun * +-

Fve A%O1 I

• Hethod of

• Shutting Down System Component Cause & Corrective 1 Duration 2

• 3 f.ER 4 5 Action to No. Date Type (11ou rs ) Reason Reactor No. Code Code Prevent Recurrence 13 10/02/85 F 27 H 5 SJ N/A Decrease in power 'due to S/G

. chemistry / condenser tube leak. .

14 10/03/85 F A 3' 1-85-058-00 EA MPi( Plant Multiplexer malfunction.

211.3 ,

15 10/07/85 F A 3 1-85-076-00 EA MPX Plant multiplexer replaced with hardwire.

16 10/16/85 S 82 ; B 5- ,

Testiny, for Reactor." Engineering.

10/24/85 F 17 183 B' 3 1-85-071-00 SB LE Instrumentation spike caused by l a shock wave. Increased delay time for reactor trip actuation to filter j the spike.

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• Chemistry out of specification.

8 1 2 3 4 F-Fo rced Reason Hethod:

S-Schoduled A-toulpment re f luro (Explain) 1-Hanual Exhibit F = Instructions for Properation of Data D-Haf ntenance or Test 2-Hanual Scram. Entry Sheets for Licensee -

C-Rcrueling J-Automa tic Scram. Event Report (LER) rile D-Regulatory Restrlction 4-Continuation from- * .

E-Opera tor Training A License Examination (NUREC 0161)

Previous Month r- Admini s t ra t ive 5-Reduction or 20% 5 C-ope ra t iona l Error (Explain) * , or creator In the Exhibit H-Same Source

! H-Other (Explain) rest 2:a flours serenee * *

. 9-other (ExpleIn)

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1 REFUELING INFORMATION DOCKET NO._g0:528__________

UNIT _ _ PMNGS1_____

DATE_______11LOZl85_____

COMPLETED BY_Mupu Richardsgn TELEPHONE __60g-938-5300____

__ Ext._ 6ggg_______

1. Scheduled date for next refueling shutdown.

03/01/87

2. Scheduled date for restart following refueling.

04/19/87

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

Not Yet Determined What will these be?

Not Yet Determined

4. Scheduled.date for submitting proposed licensing action and supporting information.

Not Yet Determined

5. Important Licensing considerations associated with refueling,

e. g. new or different fuel design or supplier, unreviewed design or performance analysis methods, sigrificant changes in fuel design, new operating procedures.

Not Yet Determined

6. The number of fuel assemblies.

a) In the core._241___________

b) In the spent fuel storage pool._____0 __

7. Licensed spent fuel storage capacity. _13GQ_ __

Intended change ~ in spent fuel storage capacity.__Ngne______

8. projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

2002 (w/ annual reloads and full core discharge capability).

l- ,,

Arizona Nuclear Power Project P.O. BOX 52034 e PHOENIX, ARIZONA 85072-2034 November 18, 1985 ANPP 34034 EEVB/GEC Mr. Ronald M.' Scroggins, Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528, License No. NPF-41 October Monthly Operating Report File: 85-056-026; 85-004-404

Dear Mr. Scroggins:

Attached please find the October, 1985, Monthly Operating Report prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the Palo Verde Nuclear Generating Station, Unit 1 Operating License. By copy of this letter, we are also forwarding a copy of the Monthly Operating Report to the Regional Administrator of the Regien V office.

If you have any questions, please contact me.

Very truly ours CLLL GL h l

E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/GEC/rw Attachments cc: J. B. Martin (all w/a)

R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center

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