ML20203E028

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Jan 1986
ML20203E028
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 01/31/1986
From: Richardson M, Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Scroggins R
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
ANPP-35132-EEVB, NUDOCS 8604240064
Download: ML20203E028 (8)


Text

&

1 NRC MONTHLY OPE 9ATING REPORT I DOCKET NO. 50:52@ t sl UNIT NAME PVN@@-1 .

DATE 0 2 / 0 _8 _/ _8_6 L. -

COMPLETED BY _--_ Richardsgg M up u ,

TELEPHONE @02-232-5300 l Ent u 6523 QEEBBIING SIBIUS

1. Unit Name: Palg Vgtdg Nuglgar Ggegrating Station t Unit 1
2. Reporting Period:Jaguary 19@6
3. Licensed Thermal Power (MWt): 3@00
4. Nameplate Rating (Gross MWe): 1403
5. Design Electrical Rating (Net MWe): 1220
6. Maximum Dependable Capacity (Gross MWe) :Tg bg dgtgrra ingd
7. Maximum Dependable Capacity (Net MWe): Tg bg dgtgrmingd 1 O. If Changes Occur In Capacity Ratings (Items Number 3 1 Through 7) Since Last Report, Give Reasons: _____ __________

________________ Recalculated According to definition _ _ _ _ 1

9. Power Level To Which Restricted, If Any (Net MWe):_NgNE l
10. Reasons For Restrictions, If Any: _ _ _ _ _ _ _ _ _ __

i 1

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

=-

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period ___744____ ____744___ __9504____  ;
12. Number Of Hours Reactor Was I Critical ___385.5__ ___2812.5_ __2812.5_
13. Reactor Reserve Shutdown Hours _____0____ _____0____ ____0____ l 14 Hours Generator On-Line ___363.8__ __2383.6__ __2383.6_ )
15. Unit Reserve Shutdown Hours _____0____ _____0____ ____0_ l
16. Gross Thermal Energy Generated 1,265,571_ 5,659,760_ 5,659,760_ -

(MWH)

17. Gross Electrical Energy Generated __428,000_ 1,764.700_ 1,764,700_

(MWH)

10. Net Electrical Energy Generated __413,700_ 1,541,250_ 1,541,350_ l (MWH) I
19. Unit Service Factor ___N/A____ ___N/A____ __N/A____
23. Unit Availability Factor ___N/A____ ___N/A____ __N/A____ ,
21. Unit Capacity Factor (Using MDC ___N/A____ ___N/A____ [_N/A_.,__ l Net)
22. Unit Capacity Factor (Using DER ___N/A____ ___N/A____ __N/A____

Net) -

23. Unit Forced Outage Rate ___N/A____ ___N/A____ __N/A____

24 Shutdowns Scheduled Over Next 6 Months (Tvoe, Date, and Duration of Each): __Sgtvgillaneg Tgst Qgtagg - 3/@@u 39 days ______

l

25. I f Shutdown At End Of Reoort Period, Estimated Date of Startup:______
26. Units In Test Status (Priot- To Commercial Ooeration):

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

INITIAL ELECTRICITY ___6/85_____ ___6/10/85___

COMMERCIAL OPERATION __11/85_____ _____N/A_____

O h .

R

}\

t s,

REFUELING INFORMATION DOCKET NO._QO QRQ_ _ _

UNIT _______pyNGE 1_____

DATE_______0g20@fg@_____

COMPLETED BY_Mu pu Richardson TELEPHONE __60@23R:5300____

__Ent._ 6523_______

1. Scheduled date for next refueling shutdown.

03/01/87

2. Scheduled date for restart following refueling.

04/19/87

3. Will refueling or resumotion of operation thereafter recuire a Technical Soecification 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

6. The number of fuel assemblies.

a) In the core._241___________

b) In the scent fuel storage pool. 0

7. Licensed soent fuel storage capacity.____1329______

Intended change in spent fuel storage caoacity.__None______

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

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

?-

AVERAGE DRILY UNIT POWER LEVEL DOCKET NO. 50-5gg_______ _

UNIT ______PVNGQ-1________

DATE______0gfegfg6___ _ _ _ _

COMPLETED BY_M u p._ Ricbardson 3 T E L E P H O N E _ 6_ _0 _2 _- 9 _3 _2 _ _5 _3 _0 0

_Estu 6523_____

MQNTU: January 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 __ ____1,253_

  • 17 (72) 2 __ ___1,256__ 18 _ (72) 3 1,180___ _ _ _ _ _ 19

_ _ (_ 66) __

4 _1,263_ 20 _ _

___855__ __

5 ___

__1,266______ 21 1,122_ _

6 1,161______ 22 _ __ _ _ 1 , 2 2 1 _ __ __ _

7 _ _ _ ___1,147____

23 _ _1, 19 9_

t O 1,236________ 24 _

564_ _____;_

9 /

__658_____ _ _ _ _ _ 25 __ _

_ _ (74) __

10 __( 75) __ _ _ _ 26 ___________(74) _ ________

11 (77) _ _ _ 27 ________( 61) =_

_ _ _ __ =

12 _ =_ ___ (79) ______ _ _ _ 28 (55) '

___ _ _ _ _ _ ___________ n 13 __ (76) _

29 ___________(63) _

14 ______ (72) _____ _ _ _ ___ 30_______ __581 s

15 __________(72) ____________ 31 _________1,078____________

16 __________(72) ____________ -

O

"a"* BuddOBY 9E OPERSIING gfpg31ENCE EQR IME MONIH

.); DOCKET NO. 50-5gg__ _

'N '

~

~

UNIT - - - _ = _ _ _ pV_NGS-1 Lii, DATE_. 02/@Bf BS___ _ _ _ _

?.ss .

<@S y

.. COMPLETED BY_McP t Richardson __

e.<

1, .]{. ,; TELEPHONE __602:23grg300_______

c

__Egt s 6523__________

C1/01 0000 - Reactor power at 100%, main turbine 1307 MWe.

C1/03 1126 - Commenced power decrease for surveillance testing.

01/03 1132 - Reactor power at 85%.

G1/03 1202 - Reactor power at 71%

. 01/03 1219 - Commenced power increase to 95%

C1/03 1320 - Reactor power at 94.9%, main turbine 1245 MWe.

01/06 1026 - Transferred house loads from auxiliary transformers to startup transformers in preparation for loss of feedwater pump test.

01/06 1238 - Reactor power at 60% power.

01/06 1314 - Transferred house loads from startup transformers to auxiliary transformers in recovery from loss of feedwater pump test.

01/06 1455 - Reactor power at *100%.

01/07 1538 - performed reactor power cutback test for load

/, reject. Tripped main generator.

01/07 1546 - placed main generator on line.

01/G7 1656 - Reactor power at 47% due to gas strioper malfunction.

01/97 1850 - Reactor power at 96%.

01/09 1325 - Initiated Load Reject Test, main turbine trip via master trio. Reactor trio on lo DNBR caused by Reactor Coolant pumo coastdown on 13.8 KV load shed due to failure of fast transfer. One main steam safety valve l i f t ed.

~

4,.

NRC Monthly Operating Report Prge 2

'l ..-

,Rd.-

,01/09 1327 - MSIS on low Steam Generator pressure.

.01/09 1329 - Started opening Steam Generator atmospheric dump-

', valves.

.l.

01/09 1930 - Plant in Mode 3.

01/14 0205 - Comoleted plant cooldown/depressurization to approximately 400 degrees F/500 psia to allow repairs to the isolation valves to the pressurizer spray valves.

01/19 0130 - Plant in Mode 2.

01/19 0804 - Reactor is critical, 01/19 1042 - Entered Mode 1.

01/19 2247 - Main Turbine on line.

01/19 2250 - Commenced raising Rx power to 19%.

01/21 0700 - Plant in Mode 1, Rx power at 90%, main turbine at 1167 MWe.

01/22 1930 ,Rx power at 9 9 . 5 /., main turbine at 1289 MWe.

01/24 1130 - Performed Loss of Load without Reactor Power Cutback System, Rx trioped on Hi cressurizer pressure. All four RCPs tripped for Natural Circulation Cooldown Test. During this test a secondary safety lifted.

01/24 2225 Entered Mode 4.

01/25 0115 - A steam void was inter.tionally drawn in the Rx vessel head during RCS deoressurination. The steam void was collaosed with use of the reactor coolant gas vent system venting from the vessel head to the RDT.

01/29 0050 - Entered Mode 3.

01/29 1508 - Entered' Mode 2.

01/29 1526 - Reactor critical.

01/29 1950 - Entered Mode 1.

m n

NRC Monthly Operating Report page 3 01/29 ~ 2213 - Main Turbine on line at 40 MWe.

.;iO1/30 0700 - Mode 1, Reactor power at 40%, Main generator at 438 MWe.

- r- .

61/30 1520 - Reactor power at 69%.

01/31 0425 - Stabilized Reactor power at 99%.

01/31 0822 - Started the 180 hour0.00208 days <br />0.05 hours <br />2.97619e-4 weeks <br />6.849e-5 months <br /> continuous run for the Arizona Corporation Commission.

01/31 1520 - Started borating to '60% power due to Hi Vibration on B FWPT.

01/31 1555 - Stopped power decrease at '70%.

01/31 1928 - Mode 1, Reactor power at 72%, Main Generator at 911 MWe.

1 1

6=

e O l

s . .

, #' ' UNIT SHUTDOWNS AND POWER REDUCTIONS ..'

  • DOCKET NO. Mn-99A **

'g .'

8 UNIT NAHC PVNChi , l j

DATC b b. 10. 1986 . *

  • COMPLETED SY Pl . t' . Richa rrf nnn /*

' TELEPil0NE - Q U-5 31)O .

I:'v e 6 4 0 't

  • Hethod of
  • Shutting *
  • Down System Component . Cause & Corrective 1 Dura t ion 2
  • 3 f.ER 4 5 Action to No. Date Type (frours) Reason Rosctor No. Code Code ' Prevent Recurrence .

29 01/03/86 S 0 B 5 e

Survei11anch testing, 01/06/86 S 30 0 B 5

~

Loss o.f feedwater p6mp test.

j 31 01/07/86 S ,0 S N/A

  • Reactor power ' cutback test.

32 01/07/86 F 0 A N/A CB DGS Gas stripper malfunction.

33 01/09/86 S 234.5 B 3' 1-86-006 EA 78 Load

  • Reject T'est.'

34 01/24/86 S 124 B 3 1-86-015 *

' Performed Loss of Load without Reactor Power Cutback System.

) 35 01/31/86 F 0 A 5 SJ P Decrease power due to Hi vibration on B FWPT. Fixed pump.

4 1

i 1

I 1

s

'.,i . _ _ ._ . - -

1 2 * -

F-Fo rced 3 4 i

Reason: Method:

! S-Scheduled A-Eculpment Fellpro (Explain) l-Hanual Exhibit for Prnparation of Data F - Instructions D-Haintenaneo or Test 2-Hanual Scram.

C-Acructing Entry Slincts for Licensee -

D-Regulatory Restriction J-Aistoma tic Scram. Event Report E-Dnnrator Training h License Examination ti-enntinuation from- (HUREC C161) (LER) FI,le .

F-Admini s t ra t ive Provfous Month c-Dporational Error (Explain)

  • 5-Reduction or 20% 5 H-Other (Explain) , , or creator in the Exhibit H-Seme Source n rast 2ta llours

o 7 Arizona Nuclear Power Project P o. Box 52034

  • PHOENIX, ARIZONA 85072-2034 February 14, 1986 ANPP-35132-EEVB/LJM/98.05 Mr. Ronald M. Scroggins, Director Office of Resource Mar.agement U.S. Nuclear Regulatory Comission Bashington, D.C. 20555 l l

1

Subject:

Palo Verde Nuclear Generating Station (PVNGS) l Unit 1  !

Docket No. STN 50-528 (License NPF-41) l January Monthly Operating Report l File: 86-024-404

Dear Mr. Scroggins:

1 Attached please find the January,1986, Monthly Operating Report prepared and sub- I mitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) I 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 Region V office. l l

If you have any questions, please contact me.

Very truly yours,

~

$5hh t t E. E. Van Brunt, Jr.

Executive Vice President Project Director l l

EEVB/LJM/rw Attachments cc: J. B. Martin (all w/a) l R. P. Zimmerman l E. A. Licitra A. C. Gehr INPO Records Center .g 7 ((

ced1Si

<f*> r

\