ML20207F707
| ML20207F707 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 09/30/1986 |
| From: | Haynes J, Hull J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-38674-JGH, NUDOCS 8701060196 | |
| Download: ML20207F707 (5) | |
Text
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.e NRC MONTHLY OPERATING REPORT DOCKET NO.
Sg-52g UNIT NAME PVNGS-1
--_7_69786 16 DATE COMPLETED BY J.L.~
Hull 662 93 ~
---_--_2 5_300 TELEPHONE
_E _x _t _. _ 6_ 5 9 3-_
-_PER_A_T_I_N_G__ STATUS O --
1.
Unit Name: jalo_ Verde _ Nuclear _ Generating _Stationt_ Unit _1 2.-
Reporting. Period: Segtember_19@@
- 3..
Licensed Thermal Power (MWt): 3399 4.
Nameplate Rating (Gross MWe): 1493 5.-
Design Electri'al 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 (Itema Number 3 Through 7)
Since Last Report, Give Reasons: ________________________________
.---_=____-_- __
9.
Power Level to Which Restricted, If Any (Net MWe):
_NgNE_________
10.
Reasons For Restrictions, If Any:
=-----__--_-__-_--___--____---
This Month Yr.-to-Date Cumulative 11.
Hours in Reporting Period
____Z2p___
___55_2p____
___5529___
12.
Number of Hours Reactor Was Critical 569.1_
___3045.5__
___3045.5_
13.
Reactor Reserve Shutdown Houra
_____g____
_____Q_____
_____Q____
14.
Hours Generator On-Line 535.9_
___2936.2__
___2936.2_
15.
Unit Reserve Shutdown Houra
_____Q____
_____Q_____
Q____
16.
Gross Thermal Energy Generated (MWH) 1,929 290_
19,573 S95_
1_Qt_73 5_95 S
t t
t 17.
Gross Electrical Energy Generated (MWH)
__664,80_o_
_3 641_t_QQ_
1
_3 641_t_QQ 1
t t
18.
Net Electrical Energy Generated (MWH) 613 217_
_3 359tg71_
_3 350 O71 t
t t
t 19.
Unit Service Factor
___74.433_
____53.193_
____53.193 20.
Unit Availability Factor
___74.433_
____53.193_
____53.193 21.
Unit Capacity Factor (Using MDC Net)
___@9.753_
____49.7Q3_
____49.7Q3 22.
Unit Capacity Factor (Using DER Net)
___q9 753_
____49.7Q3_
____49.703 t
23.
Unit Forced Outage Rate
___25.573,
____19.763_
____19.763 l
24.
Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration I
of Each):
25.
If Shutdown At End of Report Period, Estimated Date of Startup:
i 26.
Units in Test Status (Prior To Commercial Operation):
Forecast Achieved b
INITIAL CRITICALITY
__5fp5__
_5/25/95_
l INITIAL ELECTRICITY
- - _6 / _8 5---
- - _/ 1 0 _/ _8 5--
6 --
l COMMERCIAL OPERATION
_11/p5__
_2/13fpp_
l 8701060196 861014
{DR ADOCK 0500 8
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y.
i,'
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.50-52G
~~
~~~~~~~~
- --- - - - - _5_ ~ l _- - = _
UNIT PVNG --
DATE --_---------_/_86 10/09 COMPLETED BY J.L.
Hull 565~555-5566~~~
TELEPHONE-Ext. 6593 MONIH:
Septesaber 1986 N
' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL
- =-
11_4_1_----=-
17 --------_ 1244 1
1 1
=_.
2-
- ----- - - - - _8 7------------
18 1 239--
3
1 1 243 3
0 19 --
x---------------
- 4 O
20 - - - - - - - - - x - _4 _4------_-
1 2
1247_--_ -------
5
_=-------------_---
21 0
1 6
547 22 --_------ 1245 1
p:
7
12_3_3 23 --------- 1248 1
1
- --- 1 2 2 7 _ - - - -
24 ---_----- 1253 8
1 1
9 675 25 1 253 x---------------
10 268 26 --------- 1257 1
--- 1177 27 1_2_3_3__------_--_
11 =
1 1
12 -
_==------------_----
0 28 ------_--_1 24_4_---_-------
2--
13 - -
29 --------- 2-_57 0
1 2 14 O
30 --------- 2253 1
15 535 16 _.
-- 1245 _------___
1
~.....
b...,
c REFUELING INFORMATION DOCKET NO.
50-528_______
UNIT PVNGy-1______
DATE 19/99/p3_____
COMPLETED BY J.L._ Hull ____
TELEPHONE 392-932--5309_
Egt _@593____
2 l.
Scheduled date for next refueling shutdown.
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, significant changes in fuel design, new operating procedures.
Not Yet Determined 6.
The niaber 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 spent fuel storage capacity.
___None___
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).
a
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO.
59-523_______
UNIT PVNGS-1______
'DATE 19/99/35_____
COMPLETED BY J.L _Hu11____
2 TELEPHONE pp2-93_2-53pp_
E t _@593____
32 09/01 0000 Reactor Power at 100% - Mode 1.
09/02. 0839 Reactor. Trips on apurious Steam Generator Low RC Flow Mode 3 09/05 1532 Reactor Critical Mode 2 09/05 1657 Entered -' Mode 1 09/06 2050 Synchronize Generator to Grid 09/09 1338 Turbine Trip due to actuation of the Turbine / Generator Auxiliary Trip and Leck-Out - Mode 1 09/10 1129 Synchrontze Generator to Grid 09/11 0236 Reactor Power at 100%
09/11 2334 Reactor Trip on Low S/G pressure due to actuation of Steam Bypass Control. System at 1004 power - MSIS 2'MSSV's lifted.for approximately 3 minutes initiated Mode 3.
'O9/14 2337 Entered Mode 2 09/14 2342 Reactor Critical 09/14 0143 Entered Mode 1 09/14 0553 Synchronize Generator to Grid 09/15 1510 Reactor Power at 70% and increasing to 100%
09/30 Reactor Power 100%
' O ' UNIT SHilT00WNS ANO POWER REDUCTIONS.<;- DOCKET NO.
' 911-9? A
'e
UNIT NAME is - I DATE M6 s
~
' COMPLETED BY
- LL TELEPHONE 9 U 'i100 vve Ase3 4
Nethod or Shutting Down System Component Cause & Corrective 1
Duration 2
- 3 LCR 4
5 Act8cn to 1
No.
Date Type (liou rs )
Reason Rosctor No.
Code Code
- Prevent Accurrence l' 8.
A 10 09/02/86 F
0 3
1-86-044 JC
.PDT Reactor Trip due to Steam Generator. low RC flow.. Trip occurring on RPS Channels 1
B and D.
4 11 09/11/86 F
54.4 H
.3 1-86-053 JI FT Reactor 'frip on-low Steam Generator i
Pressure.and an automatic MSIS occurred.
The event was initiated by loss of Main Steam flow signals on all 4 steam flow inputs; to the SBCS. The loss of all four steam flow channels was caused by a circuit card i
extender. The short circuit occurred-while an_ Instrumentation and Controls l
Technician was performing maintenance on i
the cabinet.. The root cause of this event was a procedural inadequacy.
l i
i j
- t 1
2 3
is T-Forced Reason Hethod:
Exhibit F = Instructions S-Schodufed A-touipment ralluro (Explain) 1-Ha ntia l for Prnparation of Data D-Hiintenanco or Test 2=Hanua l Scram.
Entry Sheets for Licensee C-Reftseling 3-Automatic Scram.
[ vent Report (LCR) file 0-Regulatory Restriction i
8 -Continten tion f rom-(NURCC 0161) 4 i
t-Opera tor Training h I.lconse Examina tion rrnvious Month T-Admin t s t ra t ive 5-Redtsction of 20%
5 C-Ope ra t iona l Error (Explain) or Creator in the Exhibit H-Some Source H.other (Explain) 9-other (Explain)
Past 24 flours 9Rhnee
.E b
Arizona Nuclear Power Project P O. box 52034
- PHOENIX. ARIZONA 85072-2034 October 14, 1986 ANPP-38674-JGH/PGN/98.C5 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)
September Monthly Operating Report File: 86-024-404
Dear Mr. Scroggins:
Attached please find the September, 1986, Monthly Operating Report prepared and submitted pursuant to Specification 6.9.1.6 of Apper/ dix 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 September 11, 1986, two Main Steam Safety Valves lifted for approximately 3 minutes in Mode 3 following a reactor trip on low steam generator pressure.
If you have any questions, please contact me.
Very trul yours, a(7 J. G. Haynes Vice President Nuclear Production JGH/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 S , $
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,