ML20154S548

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Dec 1985
ML20154S548
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 12/31/1985
From: Richardson M, Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Scroggins R
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
ANPP-34656-EEVB, NUDOCS 8604010316
Download: ML20154S548 (8)


Text

. -

NRC MONTHLY OPERATING REPORT DOCKET'NO. 50-528 UNIT NAME PVNGS-1 DATE 01/08/86 COMPLETED BY M. P.. Richardson TELEPHONE 602-932-5300 Ext. 6593 OPERATING STATUS

1. Unit Name Palo Verde Nuclear Generating Station, Unit 1 2.: Reporting Period December 1985
3. Licensed Thermal Power (MWt): 3800
4. Nameplate Rating (Gross MWe): 1304
5. Design Electrical Rating (Net MWe): 1270
6. Maximum Dependable Capacity (Gross MWe):To be determined
7. Maximum Dependable Capacity (Net MWe): To be determined
8. If Changes Occur Above Since Last Report, Give Reasons: ___ _ ___

_ _ - - =_ ____-_--_ N / A _ _ _ _ _ _ _ _ __

9. Power Level To Which Restricted, If Any (Net MWe):____N/A________
10. Reasons for Restrictions, If Any:________N/A________________ _ _ _ _ _ _

_____ _____- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ = _ --__ ----- _ _ = _ _ _ _ _

Month Year Cumulative

11. Report Period Hrs _______744__ _____4898__ _____8760__
12. Hours Reactor Crit ical _____583.8__ _____2427__ _____2427__
13. Rx Reserve Shtdwn Hrs _______,,_0__ __ ___0__ _ _ _ _ _

__ _ O__

14. Hrs Generator On-Line _____465.3__ ___2019.8__ ___2019.8__
15. Unit Reserve Shtdwn Hrs _ _ _ _ _ _ ___0__ ________0__ _ ____ _ 0__
16. Gross Therm Ener (MWH) _1,460,729__ 4,394,189__ 4,394,189__
17. Gross Elec Ener ( MWH .) ___478,600__ 1,336,700__ 1,336,700__
18. Net Elec Ener (MWH) ___430,781__ 1,127,650__ 1,127,650__
19. Unit Service Factor _______N/A__ ______N/A__ __N/A__
20. Unit Avail Factor _______N/A__ ______N/A__ _

_N/A__

. 21. Unit Cao Factor (MDC Net) _______N/A__ ______N/A__ ______N/A__

22. Unit Cap Factor (DER Net) __

_ _ _ __N/A__ ______N/A__ = __ N/A__

23. Unit Forced Outage Rate _______N/A__ ______N/A__ ______N/A__
24. Shutdowns Sched Over Next 6 Months (Tyou,Date, Duration): __ __

SurveillaDer Tesi 991ese : JZaSt 49 dayn_______________________

25. If Shutdown At End Of Report Period, Est imat ed Date of Startuos____
26. uni E ii. Tesi siains iE Isr TE E;;;; EI;i 5pe aii;Eii-- -----

Forecast Achieved INITIAL CRITICALITY 5/85 5/25/85 INITIAL ELECTRICITY 6/85 6/10/85 COMMERCIAL OPERATION 11/85 N/A

),e 4

g 8604010316 851231 h[

PDR ADOCM 05000528 R PDR

REFUELING INFORMATION DOCKET NO._g@-Qgg__________

UNIT _______PVNGH-1_____

DATE_"______0140gfg@_____

COMPLEiED BY_McPt Richandsgo

+

TELEPHONE __@0g-Egg-gge0_

__Ent-_ 6223__

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, significant changes in fuel design, new operating procedures.

Not Yet Determined S. The number of fuel assemblies, a) In the core._g41___________

b) In the spent fuel storage pool._____0_______

7. Licensed spent-fuel storage capacity.____18@H______ ,

Intended change in spent fuel storage capacity. Ngge______

8. projected date of last refueling tha't can be discharged to spent fuel storage pool assur6ing present capacity. -

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

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. @0-Qg@ ___

UNIT ______EMNQ@ 1________

DATE______0140@L@@________

COMPLETED BY_Mu2n Righandggn TELEPHONE _60g-23@-D300

_ggi._ @Q23 __

MONTH: December 19E5 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 =-

0 - _ - ____- 17 _

_0 ______________

2 ___ ___596___ 18 _____ ____ _

0___ ________

3 __ 7 8 0 _ _ __ __

19 _319___ _

4 _ __ _ __ ___6 0 4_ _ ___ _ 20 ____ _ _ __.___ 4 1 _ _ _ _ _ _ _ _ _ _ _ _ _

5 _ _ _ _

_0 - _____ 21 __________124_ __ ___

6 = _ _ _ _ _ __ __ 6 4 _ ____ _ _ _ _ _____

22 _ _ _ _7 4 3____ _ _

7 __ __ __ __,,4 73 __

23 __ ___1,166_ _ _ _____

8 _.- _964_ _ _

24 ____ _1,174_ __ ______

9 -

_900_ _ _ - _ 25 - --_ - - - - - __1, 17 4 10 _______1,136_ ___ _ _ _ _ _ 26 ________1,174_ _ _ _ _ _ _

11 _________468______________ 27 _ _ _ _

__1,133_____ ____

12 ______ O_ _________ 28 _ _1,114_

13 __ . __ _ _0 __ _ _ _ _ _ _== 29 ___ 1,118 ___________

14 __ z _ _ __ __

0 __ __ 30 -

__ _ 1 , 1 4 8 __ _ _ f _ _

15 == _____ _ 0 _ _ _ 31 ________1,170.. - - =

16 _________368____-- . ==

g. /

(

" N

EWM50BX QE QEEBBIINE EKEEBigNQg EQB IMg [QNIH DOCKET NO.___@0-Eg@__ ___

UNIT ______ PVNQg-1_ _

_ DATE_ ___014@@4g6 _ __

COMPLETED BY_Mtpu Bichandsgn TELEPHONE __6Qg-23g-3300 _ _ _ _ _

__Entt 6523__________

12/01 0048 - Increased Rx power to 5%, entered Mode 1.

12/01 2309 - Syne Main Generator on line.

12/02- 9108 - Increased Main Generator load to 164 MWe, Reactor power at 18.5%.

12/02 1250 - Reactor power at 80%, Main Generator at 1027 MWe.

12/04 1430 - Initiated Load Reject Test, satisfactory.-

12/04 1700 - Reactor power at 25%, Main Generator at 250 MWe.

12/04 1627 - Syne Main Generator on line at 60~MWe.

12/04 1996 - Reactor trip at 56% power. Trip due to a high penalty factor being inserted by the CEACs due to dropping ,

Subgroup 12 (part lengtn CEAs).- All equipment functioned as designed.

12/05 0143 - plant in Mode 3.

12/05 2107.- Reactor is critical, entered Mode 2.

12/05 2247 - Entered Mode 1.

12/06 0433 - Sync Main Generator.

12/06 0458 - Main Generator tripped due to high vibration.

12/06 0653 - Sync Main Generator.

12/06 1158 - Main Turbine trip due to a generator exciter trip.

12/07 0521 - Syne Main Generator.

. 12/07 1543 - Reactor power at '80% power. ,

12/07 2220 - Commenced power ascension to 90% power. ~'

1 6

+=a v y- 4-

-.,yv- yw<w y--.-,--e w y y- ,-y , - - -,.,,,w a- , , .- p,,- - , , ,-,,r c - , , -% w.w- --ry -.yw,w.4, - -

NRC Monthly Report - December Page 2 12/10 0025 - Reactor power at 90% power.

12/10 1408 - Comeenced power ascension to 100% power.

12/10 1743 - Reactor power at 100% power.

12/11 0754 - Borated to reduce reactor power to '70% due to suspected condenser tube leak.

12/11 1105 - Entered Mode E 12/11 1108 - Main Ger.orater of f line.

12/11 1630 - Reactor power at *1% power.

12/12 1545 - Plant in Mode 3.

12/12 1559 - Reactor is in a shutdown condition due to ammonia concentration chemistry in the primary.

12/15 0340 - Reactor critical, entered Mode 2.

12/15 2224 - Entered Mode 1, reactor at 9 5% power.

12/16 0310 -- Main generator on line.

12/16 1533 - Reactor at 52.2% power, Main generator 552 MWe.

12/16 2315 - Main turbine trip.

12/16 2332 - Reactor trip due to Lo S/G 1evel on all~4 channels, entered Mode 3.

12/18 2152 - Reactor is critical, entered Mode 2.

12/19 0156 - Entered Mode 1.

12/19 0407 --Main generator on line.

12/20 0243 - Reactor trip from 40% 'ower p on high pressurizer pressure after a reactor power cutback signal initiated a turbine runback and SBCS auick open i

block. plant response was normal no ESFAS ,

actuations.

12/21 0630 - Reactor critical, entered Mode 2.

12/21 1028 - Entered Mode 1. .

12/21 1415 - Main generator on line.

l 12/22 2055 - Began 100 hour0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> run at 95% power er greater.

1 E

NRC Monthly Operating Report page 3 12/23 9845 - Reactor power at 100%.

12/25 9800 - Plant in Mode 1, reactor power at 99.6%, rnain generator at 1312 MWe.

12/27 0153 - Completed 190 hour0.0022 days <br />0.0528 hours <br />3.141534e-4 weeks <br />7.2295e-5 months <br /> run ct ) 95% power.

12/38 9415 - Rearctor power at 100%.

1 I

d e

e-S 9

er

- ,m-- , y, , m _ , - . ,. , .., - - - - , ,-y.,,,, , - ~ , , . - , - - - - , - , - - - , _, -

.- ,_,r,. ,. , ,. , , ,

8 * -

' . 'g.

. . . ,*,, +' UNIT SHUTDOWNS AND POWER REDUCTIENS- DOCKET NO.k, ' Mn-49A *

~,

+

. I UNIT MANC ~PVHG9-1 DATE - 0I110/86

\*

  • COMPLETED BY __ H. t' . Kachardenn

. rve Asni Hethod of g

a Shutting Down /' System Component Cause & Corrective 1 Duration 2

  • 3 1.ER I: 5 Action to No. Dsto Type lifours) Resson Roactor No. Code Code Prevent Recurrence .

20 12/04/85 S 0 B N/A Load. reject test. -

21 12/04/85 F 26' ,

A . 3 1-85-088-00 AA 25 liigh pena'It'y factor being inserted by the

~

CEACs.duetto. dropping subgroup 12 (part

. length)., Rep 1' ace phase synchronizer card.

22 ,12/06/85 F D A N/A - -

liigh .vi.br a t f or). Reset.

23 0

' }2/06/85 F A N/'A Generator exciter trip. , Vented nornal chilled water to co11petor housing.

, 24 12/11/85 F -

0 A ,5 Reduction in power due to suspected

s -

condenser tube 1e.ik.' Plugged tubes.

,42/12/85 F 25 60 A 1 Reactor shutdown due to ammonia

. I con, centration chemistry in primary.

26 ~12/16/85 F 0 11 N/A i 083-00 BOP ESFAS sequencer failed, entered Tech. Spec. LCO 3.0.3 27 12/16/8,5 F 46 A 3 1-85-090-00 JK LIC Low steam generator level on all 4 channels. Revised setpoints to FWCS.

28 '12/20 /65 F 28- A 3 1-85-O tiO-00 JI PMC liigh pressurizer pressure af ter turbine

, runback. Revised setpoints.

e s ,

. . ~ . ...

1 2 T-Forced . 3 4 '

Reasont S-schoduled A-Coulptncnt railuro (Expla in) Method: Exhibit T - Instructions 1-nanssa l i

D-Naintenance or Test 2=Hanpal Scram.

for Prnparation or Data C-Rcrucilng 3-Automati: Sc ra m,

[ntry Sliccts for Licensee

, D-negulatory nostriction twent Report (LCR) File E-Opera tor Tra ining k l.icense Examina tion ts-Continus t lan f rom- (NURCC 0161)

'e d

.g T-Administrativo Prnvious Month e

,C-opo ra t iona _l Error (Explain) ' 5-nedvetion or 20% 5 or creerne en enn r~ M M * " * = - - * - - - -

2.

Arizona Nuclear Power Project P.O. Box $2034 e PHOENIX, ARIZONA 85072-2034 January 15, 1986 ANPP-34656-EEVB/LJM/98.07 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 NPF-41)

December Monthly Operating Report File: 86-024-404

Dear Mr. Scroggins:

Attached please find the December, 1985, Monthly Operating Report prepcred and submit-ted 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 alsa forwarding a copy of the Monthly Operating Report to the Regional Administrator of the Region V office.

If you have any. questions, please contact me.

Very truly yours, l%

E. E. Van Brunt, Jr.

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

R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center 8

I