ML20133G762
| ML20133G762 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 05/31/1985 |
| From: | Richardson M, Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Barry L NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-32829-EEVB, NUDOCS 8508090066 | |
| Download: ML20133G762 (6) | |
Text
.
NRC MONTHLY OPERATING REPORT DOCKET NO.50:528 UNIT NAMEPVNGS 1 DATE6/10285 COMPLETED BYM._P.
Richardsgn TELEPHONE 602r932:5300 Egt. 6593 OPEROIING SIBIUS 1.
Unit Name: Palo Verde Nuclear Generating Statign Unit 1 o
2.
Reporting Period: May 12@5 3.
Licensed Thermal Power (MWt): 3800 4.
Nameolate Rating (Gross MWe): 1304 5.
Design Electrical Rating (Net MWe): 1870 6.
Maximum Dependable Capacity (Gross MWe):Tg be determined 7.
Maximum Dependable Capacity (Net MWe):
Tg be d et errnined 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons: __________________
______________________Nf9________________________________
9.
Power Level To Which Restricted, If Any (Nct MWe):190 MWt 10 MWe)
- 10. Reasons For Restrictions, If Any:Lgw Pgwer Operating License This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Period
___744____
__3624____
_3624___
- 12. Number Of Hours Reactor Was Critical
___166____
___166____
__166___
12 Reactor Reserve Shutdown Hours
_____0____
_____0____
____0___
- 14. Hours Generator On-Line 0
0 0
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated
___288____
___288____
__288___
(MWH)
- 17. Gross Electrical Energy Generated 0
0 0
(MWH)
- 18. Net Electracal Energy Generated 0
0 0
(MWH)
- 19. Unit Service Factor
___N/A____
___N/A____
__N/A___
- 20. Unit Availaoility Factor
___N/A____
___N/A____
__N/A___
- 21. Unit Capacity Factor (Usino MDC
___N/A____
___N/A____
__N/A___
Net)
- 22. Unit Capacity Factor (Usino 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: _____
__N/A_______________
- 26. Units In Test Status (Prior To Commercial Doeration):
Forecast Achieved INITIAL CRITICALITY
___5/85_____
___5/25/85___
INITIAL ELECTRICITY
___6/85_____
_____N/A_____
COMMERCIAL OPERATION
__11/85_____
_____N/A_____
AVERAGE DAILY UNIT POWER LEVEL
[( c p.
8508090066 850531 e
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DOCKET NO.
5 0_ _- 5_ 2 8 _ _ _ _ _ _ _
i U N I T _ _ _ _
P _V N G S_ _ _1 _ _ _ _ _ ___ _
D A T E __ __ __6_ / _10_./ 8 5_ _- _ _ __ _
l COM PLETED BY M_. _P._
.R..i.c._h_a_ rd_s_o__n.
- - 2_ 9.3.2. 5 3. 0 0 TELEPHONE 60
_ E_ _x_ t._ 6_ 5_ 9 3_..- _ _ _ _.
7 I
4 i
M O_ N _T H :
MaY 1985 1
4 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
. (MWe-Net)
(MWe-Net) 4 i
1
-____0 17.-__.____.___.__0___
2 18 _____.__-__ _0 0
3
__________0__-__.___-..___
19 _-
0_-
4
_ 0 2 0 _ _._ _ _ _ _ - - _ _ 0 _ _ __. - _ _ _. _ _ _ -
i 5
______.____0______._____.__.
21 __._______.__0________.__
't i
6
________0 22 0
i 7
-___-______0_______
23 ___-________0_____________
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i 8
_0_
24____._-__0__.--_.--__-
9 0.. -_-
25 _-.______- _. 0_-_
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_0___-.____
26
______0--
11
_.0_
27 ____._._.-_ _ _0_.___.___
a 12___.________.__0_.____.___
2 8 _ _ _._.- _._ _ _.._ _ 0 _ _ _ _ _._ _ _ _ _ _ _
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1 3 _ _ _ _ __
0 29
_____-_0 14.-____. _
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30._.____ _ -.
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15 _ _ ___
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SWdd88Y QE QEE88I1NG Ef8E81ENCE EQB IHE MQNIH DOCKET NO.___50-528___________
UNIT _________PVNGS-1__________
DATE_________6210285__________
COMPLETED BY_M.P Bichardson__
_n TELEPHONE __603-932-5300_______
__Ent 6523__________
t 5/2 - Li f ted Main Steam safety valve on SG #2.
SG #2 pressure indication read (1200 psi.
5/4 - Indication of possible lift on primary safety valve RCE-pSV202.
5/6 - Supported soecial test done on primary safety RCE-PSV202 -
lift functioned satisfactorily and valve reset perfect.
5/7 - CEDM testing.
5/10 - Supoorted and comoleted RCS Heat Loss Test - at completion of RCS Heat Loss Test, main steam line safeties were retested.
5/14 - CEA testing comoleted.
5/15 - Commenced plant shutdown for short term outage to reolace 2 primary safety valves.
5/16 - 0743 - Entered Mode 4 5/16 - 1327 - Entered Mode 5 5/18 - Replacement of safety valves for steam generator #2 is complete.
5/19 - Performed ASME Section XI test on Main Feedwater isolation valves satisfactorily. Completed replacement of 2 primary safety valves.
5/20 - 1901 - Entered Mode 4.
5/20 - CEA Testing performed.
5/23 - 0341 - Entered Mode 3.
5/23 - 1345 - Entered Mode 4.
5/24 - 2047 - Commenced dilution to criticality.
5/24 - 2259 - Entered Mode 2.
5/25 - 0145 - Unit I Crit ical.
e.
g.
UNIT SHUTDOWNS AND POWER RECUCTIONS DOCKET NO.
Mfb 5? R UNIT NAMC PVNCO.I DATE O/85 COMPLETED BY
'. R i c h n rrMnn TELEPHONE 9 D-S mn Fve MO1 Method or Shutting Down System Component Cause & Corrective 3
1.ER 4
5 Action to 1
Duration 2, Reactor No.
Code Code Prevent Recurrence No.
Date Type
( flou rs )
Reason NONE 1
2 3
4 F-Fo rced Renson:
Method:
Exhibit F = Instructions 5-Scheduled A-Equipment Falluro (Explain) 1-Hanual for Prnparation or Data D-Naintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C-Rcrucilng 3-Autorna tic Scram.
Event Report (LER) file D-Reguin to ry Rest riction ts-Continuation from (NUREC 0161)
E-ope ra tor T rn Intng & I.lconse Examina tion Prevloins Month F-Ad m i n i s t ra t i ve 5-neduction or 20%
5 C-Operational Error (Explain) or Creator in the Exhibit H-Some Source H-Other (Explain)
Past 284 Ilours
)
j 6-Other (Emplain) 2940u i
s l
O
.I o
REFUELING INFORMATION DOCKET NO._50:528__________
UNIT _______PVNG@:1_____
DATE_______6410(85_____
COMPLETED BY_MnP._ Richardsgn TELEPHONE __602:232:Q300____
__Egt e 6523_______
1.
Scheduled date for next refueling shutdown.
10/01/87 2.
Scheduled date for restart followino refueling.
11/19/87 3.
Will refueling or resumption of ooeration thereafter reautre a Technical Specification change or other license amendment?
Not Yet Determined What will these be?
Not Yet Determined 4.
Scheduled date for submitting prooosed licensing action and supporting information.
Not Yet Determined 5.
Important Licensing considerations associated with refueling,
- e. g.
new or different fuel design or supolier, 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___________
b) In the spent fuel storage pool._____0_______
7.
Licensed spent fuel storage capacity.____1329______
Intended change in noent fuel storage capacity.__Ngne______
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).
Arizona Nuclear Power Project P.O. box 52034 e PHOENIX, ARIZONA 85072-2034 Learned W. Barry, Director ANPP-32829-EEVB/GEC Office of Resource Management June 14, 1985 U. S. Nuclear Re8ulatory Commission Washington, D. C.
20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528, License No. NPF-34 May Monthly Operating Report File: 85-056-026; G.1.01.10
Dear Mr. Barry:
Attached please find the May, 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 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, please contact me.
Very truly yours, f
k E.
GLLC nt[L ;
E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVBJr/GEC/bg Attachments cc: J. B. Martin w/a R. P. Zimmerman w/a E. A. Licitra w/a A. C. Gehr w/a ik
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