ML20132G884

Monthly Operating Rept for Jul 1985

ML20132G884
Person / Time
Site:	Palo Verde
Issue date:	07/31/1985
From:	Richardson M, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	Barry L NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
ANPP-33220-EEVB, NUDOCS 8510010651
Download: ML20132G884 (8)

Text

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NRC MONTHLY OPERATING REPORT DOCKET NO. 50-52@

UNIT NAME PVNGS 1 DATE 8f8(85 COMPLETED BY M t Pt Richardsgn TELEPHONE 602:932:5300 Ent t 6593 OEEgeIING SI@lyS

1. Unit Name: Palo Verde Nuclear GeDeCating btgtign t Unit 1

2. Reporting period: July 1985

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

4. Nameolate Rating (Gross MWe): 1304

5. Design Electrical Rating (Net MWe): 1270

6. Maximum Deoendable Capacity (Gross MWe):Tg bg detgtmingd

7. Maximum Dependable Capacity (Net MWe): Tg bg dgtgrrJ i ngd

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

N LB-------_----_-------------------

__-_________-_____~___-______-____-_-________-__-_______--_--

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

10. Reasonc For Restrictions. If Any: __________________________

This Mo nt h Yr.-to-Date Cumulative

11. Hours In Reporting Period ___744____ ___5088___ _5088____

12. Number Of Hours Reactor Was Critical ___397____ ___1092___ _1092____

13. Reactor Reserve Shutdown Hours _____0____ _____0____ ____0____

14. Hours Generator On-Line ___293 668 .

668

15. Unit Reserve Shutdown Hours _____0____ _____0____ ____0____

16. Gross Thermal Energy Generated _488786.9_ _817607.7_ _817607.7_

(MWH)

17. Gross Electrical Energy Generated _135,000__ _195,200__ _195,200_

(MWH)

18. Net Electrical Energy Generated __95,869__ _126,661__ _126,661_

(MWH)

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

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

21. Unit Capacity Factor (Using 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 Report period. Estimated Date of Startuo: ______

-_8/27/85_--_______.

26. Units In Test St at us (Prior To Commercial Operation):

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

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

l COMMERCIAL OPERATION --11/85----- ---__N/A i 8510010651 850731 -rm/.

PDR R

ADOCK 05000528 PDR / L l}/

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 5 ,0 _- 5_-----____

- 28 UN I T _ _ _ _ _ _ _PV_ N GS

---_- .1_ _ _-_ _ _ _

DATE - _--- 8/08 -_/8Q.________

I _R_i gh _a rd _ son COMPLETED BY M_ _P - _L _ __ -

TELEPHONE ----_9__33__5300 602- _--

_-t xt 6_5_93 __--

3 M_ O_ _N T_ H :

July 1985 DAY AVERAGE DAILY-POWER LEVEL DAY AVERAGE DAILY POWER LEVEL i (MWe-Net) (MWe-Net) t t

i 1 __-_-____228______________ 17 __________266__ _______--

1

, 2 ___-_______'O'_-___-______--

18 ----------- ------____----

0 i

3 __-____--195___----_______- 19 __________148 - _______--___

4 _-_-_____-- -__-___--. 3 ____

20 ---___--__397_______-_____

5 __________36______________ 21 __________402_____________

4 6 ____-____293___-----__--__ 22 __________151_-_____---__._ ,

i.

7 -----____405__-- =--__-- 23 -----__---- ________-__---

0 8 --- - _ _ _ _ _1 5 1_ _ _ - -- -- -

.-_ 24 _________- 0 _____________ -

9 ___-_-___352_-__-_________ -25 -_____--___0___ _________

, 10 __-______397_--_-__-_____- 26 _______-___0___-- __-__

11 __-__--__207 - __-__---_____ 27 --___

- - - -0______________

i

- 12 _-_____-___0___---________ 28 ___________0____--________

4 13 -----______0 - ___--_ _--- 29 ___________0______________

14 _ _ _ _- _ _ _ __ _0_- -____________ -30 ________-__0__________--__

, ' 15 _________~30____------ -- 31 ___-_______0___-__________

L 16 -_-._-____335___----______-

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SUMMARY

QE QpgRATINQ g!2E81gNCE EQ8 ISE MQNId-DOCKET NO. 50-5?@

UNIT pVNGS-1 ..

DATE ._8,400/85 l

{ _ ___ __

COMPLETED BY __UtE._ Bichstdsgg_____ i

TELEPHONE ____,602-2}{-5300 i

__ EnttEG23 7/1 0000 - Reactor at'40.11% power.

7/1 1815 - Reactor tripped on hi pressurizer pressure resulting froe loss of main feed pump "A" on low suction pressure.

~

7/2 1500 - Commenced CEA withdrawal to criticality, Reactor is critical.

, 7/2 1537 - Reactor power at 10-4%, plant in Mode 3.

7/3 0547 Began power ascension to above 20%.

7/3 1939 - Reactor power at 35% generator at 358 MWe.

l 6

7/4 0058 - Shutdown sain turbine and placed on turning gear per GE recommendation due to sustained hi vibration on several j bearings following load reduction from 35% to 11% Reactor power.

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7/5 1240 - paralleled Main Gen. w/ grid, picked up load to *40 MW. >

7/6 0910 - Stabilized Reactor power '42% power and turbine load

• 455 MWe. E 7/6 1138 - Reactor power at 50% power, 535 MWe, 7/8 6850.- EHC leak on #1 control valve, started reducing turbine

load and Reactor power.

1 7/8 0930 - Tripped main turbine

7/8 0945 - Reactor power approximately 13.5%

. 7/8 1835 - EHC leak resolved, reset Main Turbine 7/8 2130 - Main Turbine at 1800 rpm.

7/9 2325 - Reactor at 19.1% power 7/9 0219 - Increasing Reactor power at.10%/hr to 50% power. ~

, 7/9 0519 - Reactor power at 50%. '

l

NRC Monthly Report July 7/11 0400 - Entered Action Statement concerning RCS leak.

7/11 1124 - Commenced reducing turbine load 7/11 1308 - Tripped Main Turbine 7/11 1331 - Entered Mode 3 7/12 RCS in ecoldown at 400F, 1950 PSIA; all CEAs fully inserted.

7/12 1730 - Stopped RCS cooldown, stabilized plant at 360F-370F to repressurize for RCS leak diagnosis.

7/13 Plant in Mode 3, four hour RCS leak rate test in process.

7/13 0848 - Abnormal RCS leak rate, troubleshooting to find source of leak.

7/13 NRC granted a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> extension for RCS leakage.

7/14 1552 - Exited Action Statement for unidentified RCS leakage greater than igpm.

7/14 Informed NRC via ENS that we were exiting 72 hr extension granted for RCS leakage.

7/14 2200 - Reactor critical 7/15 1635 - Plant in Mode.2 at 2% power.

7/15 1720 - Reactor power )5%; entered Mode 1.

7/15 1818 - Main Turbine at 1800 rpm.

7/15 2217 - Reactor power raised to

• 25%

7/16 0615 - Started power ascension to 50%

7/16 1015 - Leveled Reactor power at 50%.

7/17 1540 - Reactor trip. Trio due to a hardware failure in CEAC 2 which resulted in random erroneous penalty factors being sent to the CPCs for DNDR and LPD.

7/18 0400 - CEAC 2 declared operable-following replacement of a faulty memory board and satisfactory retest.

7/18 2105 - Commenced Reactor startup.

[ 7/18 2210 - Reactor critical, entered Mode 2.

i 7/18 2250 - Increased Reactor power to 2%.

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NRC Monthly Report July l

7/19 0407 - Entered Mode 1 7/19 0756 - Received main turbine trip on high exhaust hood temperature.

7/19 0816 - Reset main turbine.

7/19 1152 - Synchronized main generator, commenced increase to 18% power.

7/19 1730 - Reactor power at 50%

7/22 0748 - Shutdown Circulating Water pumps C&D for suspected leakage of circulating water into condensate system.

7/22 0830 - Commenced reducing reactor power 7/22 1016 - Maintaining Reactor power at '3%.

7/23 0534 - Started Reactor shutdown 7/23 0550 - Broke vacuum in condenser.

7/23 Investigating cause of high UNIDENTIFIED. LEAKAGE from RCS 7/23 Reactor trip breakers open, heat removal on Atmospheric Dump Valves, nonessential AFW for S/G feed, draining condenser hotwells.

7/24 0143 - Entered Mode 4.

7/24 0654 - Entered Mode 5 7/24 0705 - Stabilizing RCS temp at 200-205F.

7/25 1243 - Isolated "A" charging pump suction. RCS leakage from VCT stopped. Observed water leaking back into the seal lube tank when the suction was re-opened. Leak rate approx. 1 gpm. This.is postulated to be the cause of the *1 gpm unidentified RCS' leakage.

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' UNIT SHUTDOWNS AN) POWER REDUCfl0NS DOCKET NO. kn 'i? A -t UNIT NAHC PVrH:M-I .

1 DATC M/UM/M4 .

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C0HrLETED By f l . I' Richardnna .

TELEPfl0NC ~ W-VHO F re A 9 n 't

- Method or

• Shutting Down System Component Cause & Corrective 1 Duration 2 3 1.ER 4 5 Action to N r. Date Type ( flou rs ) Reason Rosctor No. Code Code Prevent Recurrence 2 7/01/85 F 22 A 3 1-85-043-00 llBG N/A Small mesh suction strainers on FW pumps used for startup were blocked causing a high pressure drop. Proper strainers were installed.

3 7/04/85 F 27. G 5.

• Due to excessive rate of cooldown there was a high vibration on several bearings on the MT 4 7/08/85 F 10 A 1 Weld was leaking. Rewelded electrohydraulic

~

1. 1 contrbi valve.

5 7/11/85 F 125 A 1 1-85-042-00 PCF Pump Unidentified RCS leakrate over Tech Spec limit during performance of procedure.

Procedure reperformed for different time intervals leakrate was then within Tech Spec' limits.

6 7/17/85 F 43 A 3 1-85-049-00 IBD INTCPM Faulty memory board on CEAC. Replaced memory board.

7 7/22/85 F 232 A 1 _ Leak was from charging pump packing.

! Replaced packing on charging pump.

1 2 3 is F-Fo rced Reasont Methodt [whlblt T - Instructions S-Schoduled A-Couf pment re f luro (Expla in) 1-Hanpal for Prnparation of Data n-Maintenance or Test 2-Hanval Sernm. Entry sheets for Lleenseo C-nerueling 3-Antoma tic scram, twent Report (LCR) Tile .

D-Regulatory itestrletion ts-Cnntinuation from (Nun [C 0161)

E-Operator Training h I.lcense Examination rrovious Month T-Adm ini s t ra t ivo 5-Reduction or 207, 5 C-Ope ra t i ona l Error (Explaln) , or Grentor in the Exhibit H-Seme Source H-Other (Expla in) rnst 24 Ilours ,

6-Other ([wplain)

REFUELING INFORMATION i

DOCKET NO._QO-D20 UNIT _ _ _

_pyNGS:1__

DATE_ _._@l06/@5_____

COMPLETED BY_gtp s Richardson TELEPHONE __60@-232-g300_

__Ent o 6D23_______

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?

j Not Yet Determined What will these be?

l i Not Yet Determined

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

1 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 i

, b) In the spent fuel storage pool._____0

7. Licens.ed ' spent fuel storage capacity. ____13g9 _____

Intended change in spent fuel storage capacity.__Ngge__

! 8. projected date of last refueling that can be discharged to e

-spent fuel storage pool assuming present capacity.

1 2002 (w/ annual reloads and full core discharge capability).  !

i l-r i

.,._._..- _ _-._ _ _l

1' Arizona Nuclear Power Project P.O BOX 52034 e PHOENIX, ARIZONA 85072-2034 ANPP-33220-EEVB/GEC August 15, 1985 Learned W. Barry, Director j Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20;55

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528, License No. NPF-41 July Month'y l Operating Report File: 85-056-026; G.1.01.10

Dear Mr. Barry:

Attached please find the July 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 ] Op> rating License. By copy of this letter, we are also forwarding a copy of the h .hly Operating Report to the Regional Administrator of the Region V Office.

If you have an questions or concerns, please contact me.

Very truly yours, f +t M 4 E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVBJr/GEC/sih Attach.nents cc: J. B. Martin R. P. Zimmerman E. A. Licitra A. C. Gehr l

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