ML20199D847
| ML20199D847 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde |
| Issue date: | 03/31/1986 |
| From: | Barkdoll J, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-36148-EEVB, NUDOCS 8606230091 | |
| Download: ML20199D847 (6) | |
Text
.
NRC MONTHLY OPERATING REPORT DOCKET NO.
50-528 UNIT NAME PyNGB-1 DATE 94490486 COMPLETED BY J M eathdgil t t TELEPHONE 60g-932-53@g Egit 6523 OREE9I1NG SIBIUS 1.
Unit Name: Palo Metde Nuclear Generating Statign Unit i t
2.
Reporting Period: March 1966 3.
Licensed Thermal Power (MWt): 3809 4.
Nameplate Rating (Gross MWe): 1403 5.
Design Electrical Rating (Net MWe):
127@
6.
Maximum Dependable Capacity (Gross MWe):
ISBS 7.
Maximum Dependable Capacity (Net MWe):
18@@
8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Re port, Give Reasons: _ _ _ _ _ _ ___ __
9.
Power Level To Which Restricted, If Any (Net MWe): _NONE______
- 10. Reasons For Restrictions, If Any:
=-_________-____
This Month Yr.-to-Date Cumulativ
- 11. Hours In Reporting Period
___744____
__1128___
1128__
- 12. Number Of Hours Reactor Was Critical
___163____
___547___
- ___547__,
- 13. Reactor Reserve Shutdown Hours O____
____0____
- ____0___,
- 14. Hours Generator On-Line 163____
___547___
- ___547s_,
- 15. Unit Reserve Shutdown Hours
_0____
____0____
____0___,
- 16. Gross Thermal Energy Generated
__566,400_
2,012,800 2,012,803 (MWH)
- 17. Gross Electrical Energy Generated
__189,700_
__689,400_
_689,400 (MWH)
- 18. Net Electrical Energy Generated
__172,288_
__642,752_
_642,752_i (MWH)
- 19. Unit dervice Factor 21.91__
___48.49__
__48.49_,
- 20. Unit Availability Factor
___21.91__
___48.49__
__48.49_j
- 21. Unit Cacacity Factor (Using MDC
___19.30__
___47.48__
__47.48__
Net)
- 22. Unit Capacity Factor (Using DER
___18.23__
___44.87__
__44.87,,
Net)
- 23. Unit Forced Outage Rate
_____0____
__0____
____0___
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): __ Surveillance Test Qutage - 3L86s 49 days ______
- 25. If Shutdown At End Of Report Period, Estimated Date of Startup: _5/86J
- 26. Units In Test Status (Petor To Commercial Operation):
1 Forecast Achieved INITIAL CRITICALITY
___5/85_____
___5/25/85___
INITIAL ELECTRICITY
___6/85_____
___6/10/85___
COMMERCIAL OPERATION
__11/85_____
___2/13/86___
8606230091 860331 DR ADOCK 05000528 IE$
PDR I l
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
5_ 0_ _ 5_ 2_ 8_ = - - - -. _
4 UNIT _
__PVNGS-1________
DATE______04LO8286_
COMPLETED BY_JuMn Barkdoll TELEPHONE _602-232-5300
_Egi._ 6523_____
L40_NTL4:
March 1986 DAY AVERABE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-Net) 1 812 17 (12) 2
__ _953. - - _ ______
18 - _ _ _
_._ (12) 3 1,220_
19 _________(12)
_ - - 1,224_____________
20 _________(12) j 4
T 5
_1,228 _
21 _________ (12) _
6
___-___1,245_
22 _ __.
___(12) 7
-__-_-__-_783 23 _ __
___(12)
B (12) 24 _________(12)
- =_ __ ___
9 (12) 25
_______(12) 10
. - _ _ _ (12)
_- -=
26 __
___(12) 11 ------___ 12) 27 _______ _(12)
(
12 _ _-
== (12) __
28 _________(12) _ _ _ _ _ _ _ - _
13 ___
(12) ______,_______
14 - - -
== (12) ___
15 _ __ _ _
__ 12)
(
16 --
_ _ _ _ - (12)
,,-r
-..,y w
-e
i*
REFUELING INFORMATION DOCKET NO._50-528___ _ _ _ __ ___ _ _ _
UNIT _______EMNGS1_____
I D A T E _ ______
_'044082@6_____
COMPLETED BY_JuM gargdoll u
TELEPHONE __603-932-5300____
f
__Ent._ 652}_______
1.
Scheduled date for next refueling shutdown.
03/13/87 2.
Scheduled date for restart following refueling.
04/19/87 3.
Will refueling or resumption of operation thereafter require a J
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.
hbt 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.
i a) In the cure._g41___________
J b) In the spent fuel st ora ge poo l. _____0_______
7.
Licensed spent fuel storage capacity.____1332______
Intended change in spent fuel storage capacity.__Noge______
2 8.
Projected date of last refueling that can be discharged.to spent fuel storage pool assuming present capacity.
2002 (w/ annual reloads and full core discharge capability).
j l
l
SUMM95Y DE 9EgROIING EZEERIENCg Egg IHg MgNIS DOCKET NO.___50-528________
UNIT _
______pVNGS-1__________
DATE_________0440gfg6_________
COMPLETED BY_J M._ Bathdoll____
t TELEPHONE __602-932-5300_______
__gxt 6523__________
s C3/01 0700 Rx power at 94% Main Generator at 1254 MWe.
03/01 1200 Commenced power reduction to 40% due to Steam Generator Chemistry.
03/01 1415 Rx power 40%.
03/02 0545 Commenced power increase to 65%.
03/02 0622 Rx power at 65%.
03/02 0935 Rx power at 94.5% and Main Generator at 1210 MWe.
03/02 1225 Rx power at 99.5%.
C3/04 0730 Rx power reached 108% on CPCs and 103% on Excore Power.
Turbine load dropped 300 MWe, both Feedpump Lo Suction Pressure Trip Alarms were received.
Cause is suspected to be the shorting of the 15VDC Power Supply on the #1 Steam Generator Steam Flow / Feed Flow Recorder while sliding Recorder into the Control Board.
The transient was terminated shortly after the short occurred when a fuse blew isolating the short from the instrumentation buss.
03/06 0849 Rx power at 99.46% Main Generator at 1311 MWe.
03/07 Commenced planned Unit sh ut down.
03/07 1856 Tripped Main Turbine manually to reduce power.
03/07 1857 Rx trip on low Steam Generator level.
03/09 1807 Entered Mode 4.
03/10 0316 Entered Mode 5.
03/10}
Plant is shutdown due to Surveillance Test Outage.
a
' ' ' UNIT $NUTDouNS AND POWER RCDUCTIONS DOCKCT No,
- ns1R UNIT NANC ~ PVNCS-l I
6 DATE COHrLEffD Dy M7 W2rkdol E
'a
~
TELEPit0NE ~ 4i 7-5 mn Fve A iq 1_
Hethod or Shutting Down System Component Cause se Correctivo 1
Duration 2
3 f.[R 4
5 Action to No.
Date Type IHours)
Reason Roactor tio.
Code Code Prevent necurrence 1
03/01/86 F
0 11 5
N/A S.J N/A Reduction in power 'due to Steam Generator Chemist;ry.
2 03/07/86 F
581 A
3' l-86-018-00' SJ PMC.
Reactor. trip on low S/G level.
~
l I
e 1
2 3
is F-Fo rced Reason:
Hethod:
Exhibit F - Instructions l
S-Scheduled A-Eauipment railuro (Explain) 1-itanua l for l'rnparation or Data D-ttaintenance or Test 2-tianua l Screm.
Entry Sticots for Licensee C-neructing 3-Automa tic Scram.
Event neport (LCR) File D-negula tory Restriction Is cnntinuation from-(NORCC 0161)
E-oporn tor t ra ining h I.icense Examina tion Previous Nonth r-Admi n i s t ra t Ivn 5-Dcduction or 20%
5 C-oporntlonal Error (Explain) or creator in the Exhibit H-Seme Source if-Other (Explain)
Past 284 Hours 9.other (Expisin)
=
n,, a..
h Arizona Nuclear Power Project P.o. Box 50034
- PHOENIX, ARIZONA 85072-2034 April 15, 1986 ANPP-36148-EEVB/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 1 Docket No. STN 50-528 (License NPF-41)
March Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the March, 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 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, please contact me.
Very truly yours, CtL(
q LLL E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/PGN/rw Attachments cc:
J. B. Martin (all w/a)
R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center 55 i i