ML20132G884
| 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
.
NRC MONTHLY OPERATING REPORT DOCKET NO.
50-52@
UNIT NAME PVNGS 1 DATE 8f8(85 COMPLETED BY M P Richardsgn t t TELEPHONE 602:932:5300 Ent 6593 t
OEEgeIING SI@lyS 1.
Unit Name: Palo Verde Nuclear GeDeCating btgtign Unit 1 t
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 ngd i
8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)~Since Last Report, Give Reasons: __________________
LB-------_----_-------------------
N
__-_________-_____~___-______-____-_-________-__-_______--_--
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
-rm/.
/ L l}/
i 8510010651 850731 PDR ADOCK 05000528
}
R PDR
_. ~. -..
i M
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
5,0 _- 5_ 2 8 UN I T _ _ _ _ _ _ _PV_ N G S
.1_ _ _-_ _ _ _
DATE
-_/8Q.________
8/08 -
I
_R_i gh _a rd _ son COMPLETED BY M_ _P
_L
_9__33__5300 TELEPHONE 602-xt 6_5_93 __--
_-t M_ O_ _N T_ H : July 1985 3
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_-__-_________ _____--___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___----______-
s T
I l
i
i
SUMMARY
QE QpgRATINQ g!2E81gNCE EQ8 ISE MQNId-DOCKET NO.
50-5?@
UNIT pVNGS-1
{
l DATE
._8,400/85 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.
i 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%.
l l
NRC Monthly Report July 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.
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.
k
e i
4 e
' UNIT SHUTDOWNS AN) POWER REDUCfl0NS DOCKET NO.
kn 'i? A
-t UNIT NAHC PVrH:M-I 1
DATC M/UM/M4
'~
~
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 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 _ _
_ _ yNGS:1__
_p DATE_
_._@l06/@5_____
COMPLETED BY_gtp Richardson s
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
-spent fuel storage pool assuming present capacity.
e 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 Operating Report l
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
_