ML20214L563

Monthly Operating Rept for June 1986

ML20214L563
Person / Time
Site:	Palo Verde
Issue date:	06/30/1986
From:	Colville J, Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
ANPP-37405-JGH, NUDOCS 8609100272
Download: ML20214L563 (7)

Text

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NRC MONTHLY OPERATING REPORT DOCKET NO. 5_0 - 5 2 9_

UNIT NAME Phlps,-2 2DATE OJ/9pf35 COMPLETED BY J.M.3 _9olyilly TELEPHONE 592-932-3300 E331_6D93 99 ERB 11N9_ SIBluS .

1. Unit' Nane : P_a_1 o__V_e_td e _N u_c l_e a_n _Ge_ne r a t_i_ng._S t_a_t_i_onu _U_n 1_t_,_2_

2. Re port i ng Period: J_u ne__19,86_

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

4. Nameplate Rating (Gross MWe): 1403 0

5. Design Electrical Rating (Net MWe): J23J 6 '. Maximum Dependable Capacity _ (Gross MWe) : . Tso_ bg_ d et ermired e

'7. Maximum Dependable Capacity (Net MWe): To_be_determiped e

8. If Changes Occur.In Capacity Ratings (It ems Number 3 Through 7)

Since Last Re port , Give Reasons:

9. Power Level to Which Restricted, If.Any (Net MWe): _ N O,N_E,_ _ _ _ _ _ _ _ _

10. Reasons For: Restrictions, If Any -

This Month Yr. -t o-Dat e Cumulative

11. Hours in Reporting Period .__Z20__.___ __j]SjzgD_,_ _54093 25__ 5

12. Number of Hours Reactor Was Critical __5 31._8 _ _ _ _ _ _ 9 6_4_._ 5 _ _ _ _ _ 9 6,4 ._ 5 _ _ _

13. Reactor-Reserve Shutdown Hours _____0___ _____0_____ _____0____

14. Hours Generator On-Line __483._3___ _ _ .6 7.,6 ._ 4 ,_ _, __,,6_Z6._4____

15. Unit Reserve Shutdown Hours _ ,.,_ _ _ 0 _ _ _ _ __.__0_____ _____0___

16. Gross Thermal Energy Generated .(MWH) _148 .,Z9_4__

s _9_2Zs_252___ _92Zu252___

17. Gross Electrical Energy Generated ( MWH) _ 2 1_4_ 8 t _0 0 _,_ _245 dOO____ _ 2_4_ 5 d O_ 0 _ _

18. Net E lect rica l Energy Generated (MWH) _1_Z3,_239__, _1,7Z,.,196_,, __ _1 ZZo296___

19. Unit Service Factor _ _ __N/_8__ _ _ _,_ _N_(Q _ _ __ _ NLA___

20. Unit Availabi1ity Factor __ _ _N_(A _ _ _ _ _ _ _N (A _ _, __ __ __N LA __ _

21. Unit Capacit y Factor (Using MDC Nit) _ _ _ _N_(A _ _ _ ____NLQ____ ____NLA___

22. Unit Capacity Factor (Using DER Net ) ____N(@___ ____N(@____ ____Nf@___

23. . Unit Forced Outage Rate ___ N_(A___ _ _ _ _N_(A _ _ __ __ _, _N_(A __ _

j 24. Shutdowns Schedu!cd Over Next 6 Months (Type, Date, and Durat ion of Each): flo_ o s i_go i f i cppt_ o ut a_g e_.pl pnred_ e untfj_ a f t er_ warrppty_rur_

25. If Shutdown At End of Reoort Period, Estimated Date of Startup:

____BIL8__________________________________.___________________________

, 26. Units in Test St at us (Prior To Commercial Operat ion) :

Forecast Achieved INITIAL CRITICALITY __3/36__ _4/jpf#b_

INITIAL ELECTRICITY __b/#6__ 5/20/96_

COMMERCIAL OPERATION _J1195__ _ _ _ _ _ _ _ _ _ _

i

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8609100272 860630 PDR R

ADOCK 0500052*/

PDR $c-/] Cv I

i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-529 UNIT ---------- ------------ PVNGS-2 DATE 07/06/86 COMPLETED BY J. M. Colville~~

TELEPHONE ------------ EEE~93E~5,500 -----

Ext. 6593 T

MOllTil: June.1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 0 17 -------------------------- 484 2 0 18 395 3 __-_-----_266_--------_-----

19 --_----------_1 54 -----_------

4 236 20 -------------------------- 367 5 - _ - _ --- _ -_3 2-----_-----_----

1 21 --_----------------------- 416 6 173 22 --------------- _

541 _ _ _

7 143 23 ----------------

541 -----

8 ------------------

369 . - - 24 ---- ------- _4 9 4 --------------

9 426 25 -------------------------- 149 10 439

---

--------------- 26 ----_= -----------------

0 11 0 --------

27 -----------------------

0 12 0 28 ----------------- __

0 . _ . .-

13 213 29 ----------------

0 - - - - - -

14 108 30 0 15 -___----__5_4_8__._-----_----

16 523

+-%, y .-_.p-_.7 m

9 REFUELING INFORMATION DOCKET NO. 50-529________

UNIT PyNjS-2______

DATE 07/05/86_____

COMPLETED BY J.M.__Qolyillg TELEPHONE 0 3 502-932--5_300_

Ertz b@31----

1. Scheduled date for next refueling shutdown.

01/02/88

2. Scheduled date for restart following ref.ueling.

02/20/88

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

Not Yet Determined Wh at will these be?

Not Yet Determined

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

Not Yet Determined

5. Im port ant Licensing considerat ions associated with refueling,

e. g. new or dif ferent fuel design or supolier, unreviewed design or performance analysis methods, significant enanges in fuel design, new operating procedures.

Not Yet Det ermi ned

6. The number of fuel assemblies.

a) In the core. ____241____

b) In the spent fuel st orage pool. ______0______

7. Licensed spent fuel storage capacity. ___1329___

I nt end ed change in spent fuel storage capacity. ___Nopp___

8. Project ed date of last refueling t hat can be discharged to scent fuel storage pool assuming present capacity.

2003 (w/ annual reloads and full core discharge capability) .

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-529_______

e UNIT PyNDSrg______

DATE 0]/05/j5_____

COMPLETED BY J.M3 _Colyjjle TELEPHONE 502-933--5300_

0 Eytz_b59}____

06/01 0000 Plant in Mode 3.

06/02 1634 Reactor Crit ical - Mode 2.

06/03 0015 Plant in Moon 1 - Reactor Power at 5%.

06/03 0317 Synchroniced Main Generator to grid.

06/03 0515 . Reactor power raised to 25%.

06/04 0652 React or power at 50%.

06/04 0900 Reactor power lowered to 25% due to Steam Generator chemintry.

06/05 1340 Reactor power at 50%.

06/06 0202 React or power reduced to 25% due to chemistry problems in SG's #1 and #2.

06/08 1403 React or power at 50%.

06/10 0420 Turbine trip due to Excitat ion Protective Trip.

React or trio on high pressurizer pressure - Mode 3.

Li f t ed Main Steam Safety Valves.

06/11 0232 React or Cr it ica l - Mode 2.

06/11 1022 Entered Mode 1.

06/11 2340 Synchroniced Main Generator to grid.

06/13 1700 Stabilized reactor power at 50%.

06/20 1750 Shutdown due to inability to recover drooped part Length Control Rod (CEA) #48 within Technical Spec i fi cat ion 3.1. 3.1 act ion req uirement s.

Entered Mode 3.

L.

a 5

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH (Continued)

DOCKET NO. 50-529 UNIT PytJSS-2 ___

DATE 01/05/36_____

COMPLETED BY- J. M3 _Colyilj e

' TELEPHONE- 2

' #02-933--j_300_

E.2!.

t . 6593 1

06/20 2312. Reactor critical - Mode 2.

06/21 0033 Entered-Mode 1.

06/21 0305 Synch roni z ed Main Generator to grid.

06/21 0623 React or power at - 50%.

06/25 1110 Tripped Main Turbine for Load Rejection Test.

React or trio on Low DNBR - Entered Mode 3.

-, Lif t ed a Main Steam Safety Valve.

106/30 0514 Reactor crit ical - Mode 2.-

06/30 1541 Entered Mode 1.

3 1.

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' UNIT SNUTDOWNS AND F0WER ACDUCTl!NS - DOCKET NO.90-99R -  !

' UNIT NAHC ~ PVNCS-2 .

} DATE 7-R-86 ._

COMPLETED DY .T M cnivilia , ,

TELEPit0NC ~ 9 U-s mo

• re  :  !

A rA 3 Hethod or Shutting Down System Component Cause Ir Corrective 1 Du ra t ion 2

• 3 f.ER 4 5 Action to No. Date Type (llou rs ) Reason Roactor No. Code Code Prevent Recurrence . $

I

.3 6-l-86 F 40.5 A 4 2-86-027 EL 51 High pressurizer pre'ssure, 3

Negative se.quence trip on the .

. . main generator caused a turbine trip,, Turbine , bypass valves did ,

not fuick l open.resulting in a j reactor trip on high pressurizer pressure, .

4 6-4-86 F 0 F 5 N/A Reduction in power due to Steam Generator chemistry, 5 6-6-86 F 0 F 5 N/A Reduction in power due to Steam Generator chemistry, 6 6-10-86 F 0 A N/A 2-86-034 EL RJX Main Turbine trip due to Excitation Protection Trip.

7 6-10-86 F 22.2 A 3 2-86-034 JI Reactor trip on high pressurizer pressure.,

8 6-20-86 F 5.5 A 9 2-86-36 AA TMR Shutdown due to inability to recover dropped Part Length Control Rod (CEA)

1. 48 within Tech. Spec, 3.1,3.1 action requirements.

9 6-25-86 S 0 B N/A N/A , Main Turbine trip due to Load Rejection Test.

10 6-25-86 S 114 B. _ ,3 N/A._ - Reactor trip on Lo DNBR. , ,_

1 2 ,

3 T-rorced 4 Renson: Hethod: Exhibit T - Instructions S-Schoduled A-Eauipment re f luro (Expla in) 1-Manual for Prnparation or Data n-ttaintenance or Test 2-Hanual Scram. Entry sheets for Licensoo C-Itc rue l ing -

D-neguintory Restriction 3-Automa tic Scram. Event Report (LER) File E-Opnrator training & License Examination 4-Continuation from- (NUREC 0161)

• T- Adm i n i s t ra t ivo rrnvious Month c-oporational Error (Explain)

• 5-neduction or 20% 5 if-Other (Explain)

, or Creator in the Exhibit H-Some source Past 28 Hours 9 0 thor (Explain) 9 a t.n. .

• g.

W Arizona Nuclear Power Project P.O. box 52034 e PHOENIX, ARIZONA 85072-2034 L

-June 15,1986 ANPP-37405-JGH/PGN/98.05 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 2 Docket No. STN 50-529 (License NPF-51)

June Monthly Operating Report File: 86-024-404

Dear Mr. Scroggins:

Attached please find the June, 1986, Monthly Operating Report prepared and sub-mitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the Palo Verde Nuclear Generating Station, Unit 2 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.

If you have any questions, please contact me.

Very truly yours, T.C.,i 3 qy J. G. Haynes Vice President Nuclear Production JGH/PGN/rw Attachment cc: J. B. Martin (all w/a)

R. P. Zimmerman E. A. Licitra A. C. Gehr E. E. Van Brunt, Jr.

INPO Records Center I