ML20211Q114
| ML20211Q114 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/30/1986 |
| From: | Haynes J, Hull J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-39355-JGH, NUDOCS 8703030019 | |
| Download: ML20211Q114 (6) | |
Text
.
NRC MONTHLY OPERATING REPORT DOCKET NO.
59-52@
UNIT NAME PVNGS;1 DATE 12/gp/g@
COMPLETED BY g.L._ Hull ___
TELEPHONE
@g2;93_2-5399 Ext._@S2@
9EEBoIINg_gIgIUp 1.
Unit Name: Pglg_ Verde _Nuclegr_Genergting_Stgtient_ Unit _1 2.
Reporting Period: November _19@@
3.
Licensed Thermal Power (MWt): 3@gg 4.
Nameplate Rating (Groas MWe): 1493 5.
Design Electrical Rating (Net MWe):
1221 6.
Maximum Dependable Capacity (Gross MWe): 1393 7.
Maximum Dependable Capacity (Net MWe):
1221 8.
If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons: ________________________________
9.
Power Level to Which Restricted, If Any (Net MWe):
_NgNE_________
10.
Reasons For Restrictiona, If Any:
Thin Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
____Z29___
___@9@4____
___@9@4___
12.
Number of Hours Reactor Wac Critical
____@@4.2_
___43GQ.5__
___43@@.5_
13.
Peactor Reserve Shutdown Hours
_____g____
_____g_____
_____g____
14.
Hours Generator On-Line
____@54.2_
___4244.@__
___4244.g_
15.
Unit Reserve Shutdown Hours
_____9____
_____9_____
_____9____
16.
Grona Thermal Energy Generated (MWH) 2 4493@Z@_
15 42Z142g_
15tg2Ztg2g t
t 17.
Grona Electrical Energy Generated (MWH)
__g49 999_
_S 331 igg _
_5 331 199 t
t t
t 1
18.
Net Electrical Energy Generated (MWH)
__gggt722_
_4 949t3g1_
_4 949,391 t
1 19.
Unit Service Factor
___99 8@3_
____qq.Zg3_
____@gtZgy 20.
Unit A"ailability Factor
___99.g@3_
____@g.793_
____@g.Zgg 21.
Unit Capacity Factor (Using MDC Net)
___91 903_
____57.933_
____5Z.933 22.
Unit Capacity Factor O
(Usino DER Net)
_ _ _ 9_ _1 _. 0_ 8_ 5_. _
- _ _ _ 5_ 7_ _. 9_ 3_ %_ _
_ _ _ _5_ _7 _. 9_3_ *._
gg ona 23.
Unit Forced Outage Rate
____9.143_
____17.153_
____17.153 001 24.
Shutcowna Scheduled Over Next 6 Months (Type, Date, and Duration ao of Each): ~~
~~
~
do 25.
If Shutdown At'End Ef~RepSrt-PorISUI~E~ctINated-Ste~$f~5t5rtupI~~
eg
. -u 26.
Units in Tent Status (Prior To Commercial Oceration):
00 00 Q<
Forecast Achloved n
INITIAL CRITICALITY 5/85 5/25/85
'd 0$
INITIAL ELECTRICITY
((h2hh((
[h2[g2gh~_e 'IlI' 3OAC COMMERCIAL OPERATION
_ _1_1_/ 8 5_ _ _
_ 2_ _/ _1 3_ _/ 8_ 6 _
O
_a i c
. -c. _
4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
--_0_-528----__-__--_
5 UNIT _--_--- PVNGS_ _1_-------
d DATE 12/08/86 COMPLETED BY J.L.
Hull T E L E P H O N E. - - _ 6 6_ 2_ 2 5_ 2_ 2 5_ 0_ 6_
9-
_5 MONTH:
November 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL 1
_ t252 17 1
x240___----__-__
1 ---
2 1 257 18 1 244 x-------______-
-_------_ 1 3
1 252 19 ------_-___554------_---_----
x-----_--_-_-_-
4
__---_1z_25_2_--___-----
20 0
5 z2_44---------__-
21
---_---__-__0___------_-___
1 6
-______-__1z_248___---___--
22 ---___-----_665_-------____--
7 1 257 23 ________-1x244________--__
z--_----_--_---
8
---_----_-1_2_57_---____---
24 - - __ _ _ --- 1_2 5_ _2--------___-
1 1
9
--_--_---__11_257_-_--_-__--
25 ---------_12 52-2 i
10 __--_---_-1z25_2_______----
26 ____---__1 1 52____________
2--
11 -___---_--_1 i__52 27 2
x248_--_--_---__ --
12 __-------__1t257____----_-_
28 -------_-_1x248 l
13 1 ---
x244_____--_---
29 --_-_____ 1252 _____---_--
1 t
14 t248__--_-_____
30 1
1 2_-
--_______ 1 48_--____--__-
15 - - - - - - _ - _ - _1t 1 0 2 _ - - - - -.. - - - -
-___~_-_-------_-_-__---__
16 __________1 r-_15___________
2_
t I.
o
-.. ~.., _,. -. _ - - -, _. - -.
s a.
REFUELING INFORMATION DOCKET NO.
5g;52@_______
UNIT PVNGS;1______
DATE ig/gg/gg_____
COMPLETED BY J.L._ Hull ____
TELEPHONE gg2-932;5399_
Ext._g5pg____
1.
Scheduled date for next refueling shutdown, t
09/26/87 2.
Scheduled date for restart following refueling.
12/15/87 3.
Will refueling or resumption or operation thereafter require 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, significent changes in fuel design, new operating procedures.
6 Not Yet Determined 6.
The number of fuel assemblies.
a)
In the core.
____241____
b)
In the spent fuel storage pool.
______g______
7.
Licensed spent fuel storage capacity.
___1329___
Intended change in spent fuel storage capacity.
___None___
8.
Pro]ected date of last refueling that can be dischargad to spent fuel storage pool assuming present capacity.
2002 (w/ annual reloads and full core discharge capability).
L
s.
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
Sg-Q_2@_______
UNIT PVNGS-1______
DATE 12/gg/gg_____
COMPLETED BY J.L._ Hull ____
TELEPHONE 99_2-93_2-5399_
Egt _gggg____
11/01 Reactor Power at 100%
11/19 Reactor Trip on low nteam generator level, main steam safety valven actuated, and ADV were used to remove decay heat due to initiation of a main stean isolation signal.
Mode 3 11/20 Entered action 3.0.3 due to the Main Steam Isolation Valve UV-180 hydraulic presnure on the A and B accumulators decreasing below SOOO psi.
11/21 1858 Reactor Critical Mode 2 11/22 0230 Entered Mode i 11/22 0501 Synchroniced to grid 11/22 1245 Reactor approximately 49%
11/22 1837 Reactor at 100%
11/30 Reactor at 100%
'#UNITSNUTOOWNsANDPOWERREONTIONS.'.e.- DOCKET NO.
En 99A i
UNIT MANC P VN(; 4-1
)nvgg,pg er 08. 1986
}
DATE COMPLETED BY _-
I n11 TELErl10NC ~ 1 T7-WO Fve A R O 't Hethod or Shutting Down System Component Cause & Corrective n
1 Duration 2
- 3 f.ER 4
5 Action to l
No.
Date Type
( flours )
Reason Rosctor No.
Code Code '
Prevent Recurrence i3 11/19 F
65.6 A
3 1-86-061 JB LIT Reactor tripped'on low Steam Generator
~
level, safety valves wer.e lifted.
The' low lev'el'condiEion'was a result of feedwater oscillations which began with t'he' failtiie (low) of both Steam Generator nonclass level transmitters for one S. team Generator.
d t
i i
' t 1
2 3
4
~
F.Fo rced Retson:
Hethod:
Exhibit T - Instructions S-Scheduled A-touipment fellpro (Explain) 1-Hanual for Prnparation of Datn
/
D-Paintenance or Test 2-Hanual Scram.
Entry Sliccts for Licensee C-Acrueling J-Automa tic Scram.
Event Report (LCR) FI,le D-neguintory nostriction 84-Continuation from-(140nCC 0161)-
E-Operator Training h License Examination rrovfous Month F-Administrativo 5-neduction or 20%
5 C-Ope ra t iona l Error (Explain) or Creator in the Exhibit H-Some Source H-Other (Expiqin) rast 24 Ilours i.
9-other (Explain) o n e.n.,
?
3 b
Arizona Nuclear Power Project P o. BOX 52034 e PHOENIX, ARIZONA 85072-2034 December 15, 1986
~
Mr. Ronald M. Scroggins, Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Subj ect:
Palo Verde Nuclear Generating Station (PVNGS)
Unit 1 Docket No. STN 50-528 (License NPF-41)
November Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the November,1986, Monthly Operating Report prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifica-tions) 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.
On November 19, 1986, the Fbin Steam Safety Valves opened following a reactor trip and main steam isolation, and properly reseated.
If you have any questions, please contact me.
Very truly yours, 4t/h J. G. Ibynes Vice President Nuclear Production JGil/PGN/rw Attachment cc:
- 0. M. De Michele (all w/a)
E. E. Van Brunt, Jr.
J. B. Martin R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center
/
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