ML20135B446

Monthly Operating Rept for June 1985

ML20135B446
Person / Time
Site:	Palo Verde
Issue date:	06/30/1985
From:	Richardson M, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Barry L NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
ANPP-33016-EEVB, NUDOCS 8509110059
Download: ML20135B446 (9)

Text

a 4 O~

NRC MONTHLY OPERATING REPORT DOCKET NO.50:528 UNIT NAMEPVNGS 1 DATE748/85 COMPLETED BYM.P. Righardson TELEPHONE 602:932:5300 Egt e 6593 OPEg@IING SIBIUS

1. Unit Name: Palg Verde Nuclear Gegeogting Statign t Unit 1

2. Reporting Period: June 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):Tg be cetermiged

7. Maximum Dependable Capacity (Net MWe): Tg be detgrmiged

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

______________________Nf6________________________________

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

10. Reasons For Restrictions, If Any: __________________________

This Month Yr.-to-Date Cumulative i

11. Hours In Reporting Period ___720____ ___4344___ _4344___

12. Number Of Hours Reactor Was Critical ___695____ ____839___ __839___

13. Reactor Reserve Shutdown Hours _____0____ ______0____ ____0___

14 Hours Generator On-Line ___375.52_ ___375.52_ _375.52_

15. Unit Reserve Shutdown Hours ____0_.___ _____0____ ____0___

16. Gross Thermal Eneroy Generated _.128820.8_ _328820.8_ _328820.8 (MWH)

17. Gross Electrical Energy Ger;-ite 8 __60,200__ __60,200__ _CO,200_

(MWH)

18. Net Electrical Energy Generatad __16,292__ __16,292__ _16,292_

(MWH)

19. Unit Service Factor ___N/A____ ___N/A____ __N/A___

20. Unit Availability Factor ___N/A____ ___N/A____ __N/A___

21. Unit Cacacity Factor (Usino MDC _. . _ N / A _ _ _ _ ___N/A____ __N/A___

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 (Type, Date, and _

Duration of Each): __________________________________________________

25. If Shutdown At End Of Reoort Period, Estimated Date of Startuo: _____

__N/A_______________

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___

COMMERCIAL OPERATION __11/85_____ _ _._ _ _ N / A _ _ _ _._

8509110059 850630 'ERAGE DAILY UNIT POWER LEVEL fg2y PDR ADOCK 05000528 R PDR 1,l1

4 e - w I

.v s

[

DOCKET NO. - 50>-52-------------

PVNGS-1 UNIT-------------.-----_--

7/08/85 DATE---------------------

COMPLETED BY M_.P s _R i chard s.on TELEPHONE -------------602-932-5300

- Ext.

- - - - .9.. 3-----

4 M

-QNTH:

June 1985-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 =_ ---0 -------------- 17 ----------800'-------------

2 ----------- --------------

0 18 ---------3700------..------

3 0 19 __ --_3600 ----_--_-_---

4 ----------- ---------.---- .

0 o20 ---------

3000 --------_----

5 0

- ------__--_--- 21 ___--____4200 .-_-_--__-

i 6 ----------- 0-------------- 22 --------- 3800 -------------

7 ----------- -------.------ 0 23 ----- -

<4300 ----------

8 -----_-----

0 --------_...---n 24 ---------2400-------------

i s

9 ----- -----0 -------------- 25 --------- 1500---- . 7 1

10 ----

100 -------------- 26 -- ----2800~-------------

t 11 ------_--

500 -------------- 27 ---------

4300 - - .---------

12 -~----- 3100 ---------- n-- 28 -. ---- 4100 -------------

13 -------.3300_ - --. - ----_-- C --_---_-- 4700- - - . _--___-_ ,

-14 -------- 1800 ---= .---

30 ---------6600 -------- . - -

, .., 15 ----------- --------------

--O A 16 -------- 200 -

?

F l

4 Y

l l

.s ,

E 1 s

1

~ - . _ . , ,, ,,-

g =

REFUELING INFORMATION DCCKET NO._g0:525__________

UNIT _______pyNGS;1_____

DATE_______Z(0848Q_____

COMPLETED BY_McE. Richardson 3 TELEPHONE __602:932:53Q0____

__Egts 6553_______

1. Scheduled date for next refueling shutdown.

03/01/87

2. Scheduled date for restart following refuelina.

04/19/87

3. Will refueling or resumption of ooeration thereafter recuire 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

6. The number of fuel assemblies.

a) In the core._?di___________

b) In the scent fuel storage pool._____0_______

7. Licensed spent fuel storage capacity,____13sg______

i Intended change in , pent fuel storage acity._,None______

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

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

~ - - ~ ~ . - ,- , ,, , , , .nw .,,

l 1

. l 595d881 QE QEEgeIIN@.EKEESIENGE EQB IHE MQNIU  ;

l i

DOCKET NO.___50:52@___________  ;

UNIT _________PVNG@-I__________ i DATE_________ZLO8485__________

COMPLETED BY_M.P._ Richardson __

TELEPHONE __602-232:5300_______

! __ Ext._ 6523 ----------

6/1 Unit in Mode 2

, 6/1 Continued with CEA worth measurements by exchange.

6/1 Completed low power physics testing.

6/2 Began CpC' verification test and COLSS initialization.

6/5 Completed Mode change checklist for Mode 1, entered Mode 1.

6/7 1327 - Completed shell warming for the turbine, closed main steam stop valve #2 bypass.

6/8 Continued turbine generator startup.

6/8. 1532 - Turbine at rated speed of 1800 rpm.

6/8 1650 - Turbine was at 1800 rpm for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and 20 minutes and then tripped on Hi vibration on the #8 bearing.

6/9 1150 - Turbine at rated soeed of'1800 rom.

6/9 1433 - Tripoed. Main Turbine manually due to Hi vibration on

1. 7 bearing.

6/10 2226 - Approximately 20 min after the main generator was loaded CPC D DNBR started cycling causing a channel D trip. During.the investigation, the main' turbine had to be tricoed on high vibration. When the turbine was unloaded and tricoed, the DNBR cycling on CPC D

. stopped.

6/10 1149 ~ A; set speed of 1800 rpm on Turbine.

6/10 1850'- Reactor power at 12*A 6/10 2226 - Tripped Main Generator due'to high vibration on bearing #7

~

6/11 0630 - Main turbine.st 3800 rom.

6/11 0651.- Tripoed Main' Turbine rather th'an having it spin unloaded during LPC testir.g.

r ---et'

• c- -+'Wtv--- - t-t--p y ?---+e y sev<-e--mey

3 6/12 1600 - Reactor at 20% cower.

6/14 1156 - FWpT "B" tripoed on low suction pressure, tricoed Main Turbine, Reactor tripped on high Local Power Density (LpD). NO7E: On further investigation it was found the reactor trio was due-to hi oressurizer cressure.

6/16 1323 - Criticality achieved on Unit i reactor.

6/17 Main turbine generator trio caused by oscillations in the feedwater control system. This caused a main feedwater pumo tria.

6/18 1215 - Lowered turbine generator load down to 101 MW to cycle Atmospheric dump valve ADV SGA-184 6/18 1259 - Raised turbine generator load to 175 MW SGA-184 cycled 5 times (sat).

6/22 1611 - Increased surveillance frecuency on CEA positions oue to reouirements of T.S. 4.1.3.6 with the PDIL auctioneer circuit inocerable.

6/23 Inserted Group 5 rods to 12" withdrawn for Rx Engineering in preparation for delta temperature and delta power testino.

6/24 1404 - Tricoed turbine, began reducing power to 13% cower Note: The turbine shutdown was required because pressure point isolation valves MTN-V243 and MTN-V244 were blown off the main steam lines downstream of MTN-UV2002 causing a 1" hole in the steam line.

6/24 1610 - Rx power 11%.

6/25 0250 - Steam line break recaired, reset main turbine, commence:1 chest-warming.

6/25 2338 - Rx cower 14.9%

6/26 1255 - Performed Automatic Economizer /Downcomer feedwater control valve transfer, transferred at 16.5% power.

Initial test results are satisfactory.

6/27 Completed final economizer /downcomer valve testing, returned reactor cower to 19.8% cower.

6/27_1258 - Entered action statement on pressurizer safety valve position indication (3.3.3.6). for removal o? temporary test eouioment, 6/27 1430 - Exit ed action statement for pressurizer safety valve position indication.

6/28 RRS auto CEA insertion and withdrawal were tested satisfactory, (at low rate), following CEDMCS repairs.

6/29 2340 - Rx power 22%

.. +

6/29 0300 - Tavg dropped low due to inadvertant boration of the RCS.

This boration was due to makeup mode selector switch in dilute position causing a boration vice dilution.

Attemoted to duplicate, problem could not be duplicated.

6/30 0356 - COLSS (CMC) ceclared operable 6/30 0430 - Began oower ascension to 30% F.P.

6/30 2206 - Rx at 40% power generator load at 405 MWe.

1 1

4

auf

e. 6, .

UNIT SNUTDOWNS AND POWER REDUCTIONS DOCKET NO. 90A?A .'

UNIT NANC PVN L I .

DATE //0 4/85 . *,,

COMPLETED BY M . I' . Richardqng T[t.[ Pit 0NC ~ 9 U-5 300 Pye A%n3 Hathod or

• Shutting Down System Component Cause & Corrective 1.ER 5 Action to .

Duration

, Reactor 3 1 88 No. Date Type ( flou rs ) Reason2 No. Codo Code Prevent Recurrence 1 6/14/85 F 25 A 3 85-019 HBG Valvo;. See Attached' 3 4 I 2 T-Fo rced Reason: Hethod: Exhibit F = Instructions A-Equipment re f luro (Explain) 1- Ha nisa l for Prnparation of Data S-Scheduled 2-Hanost Scram. [ntry Shcots for Licensee n-Maintenance or Test [ vent Report (LER) File C-Rc resc l ing 3-Automa t ic Scrain. ,

D-Regula tory Rest riction 14-Continua tion f rom (NUREC 0161)

E-Opnra tor T ra ining & t.lconse Examina tion Prnvious Month F- Admi n i s t ra t ive 5-neduction or 20% 5 C-Ope ra t i ona l Error (Explain) or creator in the Exhibit H-Seme Source H-Other (Explain) Past 2fs llours 6-Other (Explain) 2960u .

4 O .

• ( .NRC Monthly Raport - Juns t

W The "A" Main Feedwater Pump Mini-Flow Control Valve did not control properly, allowing excessive condensate flow back to.the condenser.

This in conjunction with improper operation of Condensate Pump Mini-Flow Control Valves caused a low suction pressure trip of the "B" Main Feedwater Pumo at 1155. The reactor operators manually i tripped the turbine-generator, started auxiliary feedwater and began manually reducing reactor power by insertion of CEA's attempting to reduce. power to within the capability of the Auxiliary a ~^

feedwater System. At 1156 the reactor tripped on high pressurizer pressure, i . .

i

.Carse of the. trip was improper operation of the "A". Main Feedwater Pump Mini-Flow Control Valve.

a 4

l 6

.,7

Z ,

%-#' e Arizona Nuclear Power Project P.O. BOX $2034 e PHOENIX, ARIZONA 85072-2034 Learned W. Barry, Director ANPP-33016-EEVB/GEC Office of Resource Management July 15, 1985 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 June Monthly Operating Report File: 85-056-026; C.I.01.10

Dear Mr. Barry:

Attached please find the June 1985 Monthly Operating Report prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) zo 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.

If you have any questions or concerns, pleae contact me.

Very truly yours, ErwFM/rgE E. E. Van Brunt, Jr.

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

R. P. Zimmerman E. A. Licitra A. C. Gehr d

$ V T I

)1