ML20205D387
| ML20205D387 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 01/31/1987 |
| From: | Haynes J, Hull J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | Scroggins R NRC OFFICE OF RESOURCE MANAGEMENT (ORM) |
| References | |
| ANPP-00154-JGH, ANPP-154-JGH, NUDOCS 8703300391 | |
| Download: ML20205D387 (12) | |
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NRC MONTHLY OPERATING REPORT r
DOCKET NO. '3Q-12@
UNIT NAME PVNGg-1
! DATE ggflgggZ COMPLETED BY J.L._ Hull. ,
TELEPHONE @gg-932-Q@gg.__
E_xt_._65_9_3
- O__ P _E _R _A__ _T
_ _I N G ___ S _T _A T _U S p 1. -Unit Name: Palo_ Verde _Nuglear_ Generating _qtationg_ Unit _1
, 2. Reporting Period: January _19qZ
- 3. ' Licensed Th'ermal Power (MWt): g@gg
! 4. Nameplate Rating (Gross MWe): 1493-y 5. Design Electrical Rating (Not MWe): 12Z9
, ' 6. Maximum Dependable Capacity (Gross MWe): 139q l 7. Maximum Dependable Capacity (Not MWe): iggi j _ 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
- Since Last Report, Give Reasons
- ._ Number _5_ghanged_to_12ZQ_to I _rsflgst_griginal_dgsisg_slestrigg1_ rating _____________________
- -9. . Power. Level-to Which Restricted, If Any (Not MWe): _NgNE_________
10 . _ Reasons For Restrictions, If Any: _______ _______________________
____________________________________________ _ =___________
4 1 This Month' Yr.-to-Date Cumulative-
- 11. Hours in Reporting Period ____Z$$___ ____Z$$____ ___83Z2___
j 12. Number of Hours Reactor Was Critical __499 9___ ____499 9__ ___5513.4_
L 13. Reactor-Reserve Shutdown j ,
Hours _____g____ _____g_____ -._____g_
t *
.c 14. ' Hours Generator On-Line 391.9
~~~~~~~~~~ ~~~~~~~~~~~
391.9 5380.7
~~~~~~~~~~
I ' 3'l 15. Unit-Reserve Shutdown Hours _____Q____ _____g_____ _____g____
(,, (, , 16. Gross Thermal Energy Generated (MWH) it 4@2 t qZ4_ _1g4@gg5Z4_ 19 t@5@ggg5
' 17 . Gross Electrical Energy p -Generated CMWH) __qg@gqqq_ ___qg@t@gg_ _@t@gi t igg
- 18. . Net Electrical Energy
/3enerated (MWH) __4Z3t ggq_ ___4Z@ggg@_ _@t 324 @g@ t
. ' 19 . Unit Service Factor ___gg.Z3__ ____qg.Z3__ ____@3.g3_
g.:20s ynit' Availability Factor ,,__52.Z3__ ____Q23Z3__ ____@3.g3_
L Nr.21. Unit Capacity Factor enc n
/ (Using MDC Net) ___gg.13__
~n ga ____52313__ ____@l.1E_
58 222 Unit Capacity Factor
! r_ '(Using DER Net) ___gg.13__ ____gg.13__ ____g@.@$_
,f ' Q$r 23. Unit Forced Outage Rate ___4Zz@$__ ____dZz@$__ ____1@.@M_
24.- Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration QA
!O ' y*mb oo 25. of If Each): ----- - - -=-----=- -- ---------------------------------
Shutdown At End of Report Period, Estimated Date of Startup:
l 04 4
$or -
...__Eskruary_1@,_1987
- 26. sUnit.s in-Tost Status (Prior To Commercial Operation):
_=________________________________________
So mam f ,, Forecast Achieved T' INITIAL CRITICALITY __DZ@@__ _DfgDZgD_
~ ~~ ~ ~
C MMERCI L OP RAT ON
,gg ff g _ _1 _ _ _8 _ _ _ __2_______
,- .a. .,
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. ~~50-528 UNIT ______-_ 5_ N_G_5__2 -~_1_______-
D ATE _ _- _-_ _ _O_2_ _/ _10_ _/ 8_7__-____ _
COMPLETED BY J.L. Hull 2
TELEPHONE ___60_5_2 _9-52 53_0_0__-_
_ MON
-- _T_H: Janua_rY_1987--
DAY AVERAGE DAILY' POWER LEVEL DAY-AVERAGE. DAILY POWER LEVEL t..
1 ___________1z255________ -__
17 ________-_1 4 5_ 2 _1 _ _ _ _ - = ___
2 _ _ _ _ _ _ _ _ _ _ _1 z _2 _4 _7 _ _ _ _ _ _ _ _ _ _ _ 18 __ =___1z_101_-_-______--
1 3 - _ _ _ _ _ _ _ _ _ 212 _ _5 _1 _ _ _ _ _ _ _ _ _ _ _ 19 ____________0_______ ____
i i
4 __________ 1z2_55___ __ _______ 20 __________-_0_-__=--- = - -
5 . - - _ - _"_ _ _ _ _1A2_47____________ 21 __-_________O______________
6 -
1 2
-_____A__4_7____---- __
22 ______-_-_-_0_____________
4 C
7 _ _ _ _ _ _ _ _ _ _ _1 z 2 5_ 5 _ _ _ _ _ _ _ _ - _ _
23 -___________0_-____________
- s 8 ___________1 1_5_ 2 _1_- .-_____ 24 _ ________O________-__-__
9 _ _ _ _ _ _ _ _ _ _ _1 z 2 5 _1 _ _ _ - _ _ _ _ - _ _
25 ____________0__________-__
10 _____________4_3_4_=_ - --- - - -
26 -__-________0______________
- 1 1 _ _ _ _ _ _ _- _ _- _0 _________-
27 ____________O____-_-___---
12 _ _ _ _. '__._ _9_4_3_____- ---
28 ____________O_--____---___
13 ___________1z_247_________-_ __
29 ____________O____--________
14 ___________1 1 251 -
30 0
- ?
15 ___________1 1 _25_1____________ 31 _ _ _ _ __, _____O_______-__--__
g 16 _- _-______1 t 25.1 _ - - - - -_-
h
. t-
, \
, 1 l
l REFUELING INFORMATION DOCKET NO. @g-ggg _ _
l UNIT PVNG@-1______
DATE ggfig/gZ_____
COMPLETED BY J.L._ Hull ____
TELEPHONE @gg-922-@@gg_
Ext._@p9@____
- 1. 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 number of fuel assemblies.
a) In the core. ____241____
b) In the spent fuel storage pool. ______g______
- 7. Licensed spent fuel storage capacity. _ 1@g9___
Intended change in spent fuel storage capacity. ___Ngne___
- 8. Pro 3ected 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).
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. gg-ggg_______
UNIT PVNGg-1______
DATE gg/19/g7_
COMPLETED BY J.L._ Hull ____
TELEPHONE ggg-ggg-gggg_
Egt3 _@ggg____
01/01 0000 Reactor Power at 1004 01/10 0910 Reactor trip occured at 100%, a reactor power cutback occured due to a large load rejection. The loss of load occured when both the generator output breakers opened.
Reactor trip due to increase in steam generator #2 level.
01/11 1601 Reuctor critical / Mode 2 01/11 1803 Entered Mode 1 01/12 0030 Synchronized to Grid 01/12 1106 Reactor power at 100%
01/15 1805 Commenced power reduction to Ok at approximately 20% per hour for maintenance outage to repair steam generator tube leak 01/18 2319 Tripped Main Turbine 01/18 2330 Entered Mode 2 01/18 2345 Entered Mode 3 01/19 1947 Entered Mode 4 01/19 0247 Entered Mode 5
UNIT SIIITfDOWNS AND POWER REDUCTIONS DOCKET NO: 50-528 -
UNIT NAME: PVNGS-1 DATE: 02/10/87 -
COMPLETED BY: J.L. Ilull TELEPfl0NE: 932-5300 ext 6593 Method of Cause and Corrective Duration Shutting System No. Date Type; llours 2 3 4 Ponent 5 Action to Reason Down Reactor LER NO. Code Code Prevent Recurrence 1 1/10 F 39.9 G 3 1-87-003 EL IM Reactor power at 100%, reactor power cutback occurred due to a large load rejection. The loss of load occurred when both the generator output breakers opened. Reactor trip occurred due to increse in steam generator level.
2 1/15 F 390.0 B n/a n/a 1
n/a Power reduction to 0% at approximately 20% per hour for maintenance outage to repair steam generator tube leak.
I F-Forced Reason: Hethod: Exhibit F - Instructions S-Sc heda t ed A-Equipment Failure (Explain) 1-Manual for Preparation of Data D-Maintenance or Test 2-Hanual Scram Entry Sheets for Licensee C-Refueling 3-Automatir Scram Event Report (1.ER) File D-Regulatory Restriction 4-Continuation from (NUREI;0161)
E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20% 5 Exhibit Il-Same Source C-operational Error (Explain) or Creater in the II-Other (Explain) Past 24 Ilours o other (Fvnhire)
NRC MONTHLY OPERATING REPORT DOCKET NO.99-932 UNIT NAME PyNGg-g DATE ggflg/gZ COMPLETED BY J 2 L._Hu11____
TELEPHONE @gg-9@g-gggg Ext _@@9@
O_ _P _E _R _A T _I _N G _ S _T _A T _U S
' 1. Unit Name: Egig_yggde Nuclear' Generating _gtgtignt_ Unit _g
- 2. Reporting Period: Jaguary__198Z
- 3. . Licensed Thermal Power (MWt): @ggg
- 4. Nameplate Rating (Gross MWe): 1492
- 5. Design Electrical Rating (Not MWe): 1229
- 6. Maximum Dependable' Capacity (Gross MWe): 1392
'7 . Maximum Dependable Capacity (Not MWe): 1231
- 8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)
Since Last Report, Give Reasons: __ Number _5_ghegggd_to_12Zg_tg___
_____rsfinst_erisins1_desisn_sinstElss1_Esties___________________
- 9. Power Level to Which Restricted, If Any (Not MWe): _NgNE_________
- 10. Reasons For Restrictions, If Any: _______________________________
This Month Yr.-to-Date Cumulative
- 11. Hours in Reporting Period __Zgs_____ ___Zgs_____ _316Z_____
- 12. Number of Hours Reactor Was Critical __21Zz5___ ___21Zz5___ _242914___
- 13. Reactor Reserve Shutdown Hours _____Q____ _____Q_____ _____g____
- 14. Hours Generator On-Line __21@.@___ __21@z@____ _24193@___
- 15. Unit Reserve Shutdown Hours _____Q____ _____Q_____ _____Q____
- 16. Gross Thermal Energy Generated (MWH) __gi@t@QQ_ __gl@t@g@__ 8 t S@gt9Zg_
- 17. Gross Electrical Energy Generated (MWH) __gg9 t@gg_ __gg9 t @gg__ @t119tigg_
- 18. Not Electrical Energy Generated (MWH) __g@9t92@_ __g69 t 92(__ 21 924 t@g1_
- 19. Unit Service Factor ___g9.13__ ___29.13___ ___Z@313__
- 20. Unit Availability Factor ___g9313__ ___29 3 13___ ___Z@.13,_
- 21. Unit Capacity Factor (Using MDC Net) ___293Z3__ ___g9 3 23___ ___Z@.@g__
- 22. Unit Capacity Factor (Using DER Net) ___2gz@$__ ___2g3@$___ ___Z23Z3__
- 23. Unit Forced Outage Rate ____g393__ ____g.g3___ ____g.Z3__
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): @T_gutggg_ _Cgggggging_1-2-@Z_gnd_ruggigg_fgr_pg_dgys z_
- 25. If Shutdown At End of Report Period, Estimated Date of Startup:
____MsEsh_9Z1 128Z_______________________________________________
- 26. Units in Test Status (Prior To Commercial Operation):
Forecast Achieved INITIAL CRITICALITY __@ fag __ _sfigfag_
INITIAL ELECTRICITY __6 fag __ _Qfgggg@_
COMMERCIAL OPERATION _11/gg__ _9/12 fag _
a AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-522 ~~~~~~
UNIT _P_V_5_5_-E DATE O _2 _/ _1 0 _/ 8 _7 _ _ _ _ _
COMPLETED BY J.L. __ Hull TELEPHONE 56E295325566~
5_ E~~5555_~~~~
M O _N _T _H : J_a_n_u_a_rE__1987_
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 _________1z289 - _ =__=_____
17 ___________O______________
2 _ _ _ _ _ _ _ _ _1 1_2 _8 _3 _ _ _ _ _ _ _ _ _ _ _ _ _ 18 ___________0______________
3 _ _ _ _ _ _ _ _ _1 z _2 _7 _6 _ _ _ _ _ _ _ _ _ _ _ _ _ 19 ___________O_______________
4 _ _ _ _ _ _ _ _ _1 A_2 _7 _6 _ _ _ _ _ _ _ _ _ _ _ _ _ 20 ___________0_______________
5 _________1 L_- 276 ----_-_____
21 ___________O______________
6 _________1A _2 _7 _2 _ _ _ _ _ _ _ _ _ _ _ _ _ 22 ___________0_______________
7 _ _ _ _ _ _ _ _ _1 1_2 _8 _0 _ _ _ _ _ _ _ _ _ _ _ _ _ 23 ___________0______________
8 ________1126_0 _ -________ 24 ___________O______________
9 _________1 A__ 20_1_____________ 25 ____________0______________
10 ___________0_______________ 26 ___________0______________
11 ___________0_______________ 27 ____________0______________
12 __________0_______________ 28 ___________0______________
13 ___________0_______________ 29 ___________O______________
14 ___________0_______________ 30 ___________0______________
15 __________0_______________
31 ___________0______________
16 __________0_______________
REFUELING INFORMATION DOCKET NO. pg-@g9_______
UNIT pVNGg-g______
DATE ggflgf8Z_____
COMPLETED BY J.L._ Hull ____
TELEPHONE $g2-933-9399_
Ext 3 _gg93____
- 1. Scheduled date for next refueling shutdown.
02/20/88
- 2. Scheduled date for restart following refueling.
05/10/88
- 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 number of fuel assemblies, a) In the core. _ ___g41____
b) In the apent fuel storage pool. ______Q______
- 7. Licensed spent fuel storage capacity. ___1339___
Intended change in spent fuel storage capacity. ___Ngne___
- 8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.
2003 (w/ annual reloads and full core discharge capability).
L---_--____ _____-____..__-m__ -_____--__&_-_________m. _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _m_____.__.__ _ _ _ . _ _ _ .. _ - _ _ _ _____m.____m__.;
n
SUMMARY
OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. gg-539_______
UNIT PVNGg-g______
DATE gglig/gZ_____
COMPLETED BY J.L._ Hull ____
TELEPHONE @g3-933-9399_
Egt _@@@@____
2 01/01 0000 Reactor power at 100* / Mode 1.
01/09 1920 Commenced power reduction for planned outage 01/10 0035 Took generator off line 01/10 0040 Entered Mode 2 01/10 0130 Entered Mode 3 01/10 1348 Entered Mode 4 01/11 0500 Entered Mode 5
4
~ '
CIT SilUTDOWNS AND I'0WER REDUCTIONS DOCKET NO: '50-529 -'
UNIT NAME: PVNGS-2 DATE: 02-10-87.
- COMPLETED BY: J.L. Hull TELEPHONE: 932-5300 ext 6593 Method of Cause and Corrective Duration Shutting ystm #Ponent 5 Date 3 2 3 4 AC'I "
- No. Type -Ilours Reason Down Reactor !!'.h NO. Code Code Prevent Recurrence 1 1/10 S 527.5 B 1 n/a n/a n/a Planned Maintenance Outage l
I F-ForccJ
~
Reason: Hethod: Exhibit F - Instructions S-Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Kiintenance or Test 2-Kinual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File B-Regulatory Restriction 4-Continuation from (NUREG 0161)
E-Operator Training & License Examination Previous Month F-Administrative 5-Reduction of 20% 5 Exhibit H-Same Source C-Operational Error (Emplain) or Creater in the
!!-Other (Explain) Past 24 Hours
- " I F' * ' " ' * \ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _
i 2- ~
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Arizona Nuclear Power Project
'Nr&r'
P O. box 52034 e PHOENIX, ARIZONA 85072-2034 fW' ANPP-00154-JGH/TDS-96.03 February 12, 1987 Mr. Ronald M. Scroggins, Director Office of Resource Management U. S. Nuclear Regelatory Commission Washington, D. C. 20555
Subject:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1 and 2 Docket Nos. STN 50-528 and 50-529 (License NPF-41 and NPF-51)
January Monthly Operating Report File: 87-024-404
Dear Mr. Scroggins:
Attached please find the January,1987, Monthly Operating Reports prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical Specifications) to the Palo Verde Nuclear Generating Station, Unit 1 and 2 Operating Licenses. By copy of this letter we are also forwarding a copy of the Monthly Operating Reports to the Regional Administrator of the Region V office.
If you have any questions, please contact me.
Very truly yours, 8^fM J. G. Ilaynes Vice President Nuclear Production JGH/TDS/cid Attachment cc: O. M. DeMichele (all w/a)
E. E. Van Brunt, Jr.
J. B. Martin R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center pen
$,/ i Mr. Ronald M. Scrog81 ns, Director January Monthly Operating Report - Unit 1 and 2 ANPP-00154-JGH/TDS-96.03 Page 2 cc: J. D. Driscoll (all w/a)
J. R. Bynum R. M. Butler
- 0. J. Zeringue J. M. Allen L. G. Papworth W. M. Simko L. L. Henson M. L. Clyde R. E. Younger R. J. Adney R. E. Gouge T. R. Bradish A. C. Rogers M. Bajpai W. E. Ide D. N. Stover J. R. LoCicero M. K. Ilartsig R. Jacobs J. D. Wade W. F. Quinn R. A. Bernier J. E. Drew P. L. Vogt D. R. Canady K. Porter