ML20205D387

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Monthly Operating Repts for Jan 1987
ML20205D387
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
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)


Text

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it 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

. Power. Level-to Which Restricted, If Any (Not MWe): _NgNE_________

_rsflgst_griginal_dgsisg_slestrigg1_ rating _____________________

-9.

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_

.c 14.

' Hours Generator On-Line 391.9 391.9 5380.7 t *

~~~~~~~~~~

~~~~~~~~~~~

~~~~~~~~~~

I ' 3'l 15.

Unit-Reserve Shutdown Hours

_____Q____

_____g_____

_____g____

(,,

(, 16.

Gross Thermal Energy Generated (MWH) i 4@2 qZ4_

_1g4@gg5Z4_

19 @5@ggg5 t

t t

' 17.

Gross Electrical Energy

-Generated CMWH)

__qg@gqqq_

___qg@t@gg_

_@t@gi igg p

t

- 18.

. Net Electrical Energy

/3enerated (MWH)

__4Z3 ggq_

___4Z@ggg@_

_@t324 @g@

t 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

~ ga

/ (Using MDC Net)

___gg.13__

____52313__

____@l.1E_

n 58 222 Unit Capacity Factor

' Q$r r_

'(Using DER Net)

___gg.13__

____gg.13__

____g@.@$_

,f 23.

Unit Forced Outage Rate

___4Zz@$__

____dZz@$__

____1@.@M_

QA ' y*mb 24.-

Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration

!O of Each):

oo

- -=-----=- -- ---------------------------------

l

04 25.

If Shutdown At End of Report Period, Estimated Date of Startup:

...__Eskruary_1@,_1987 4

_=________________________________________

or

26. sUnit.s in-Tost Status (Prior To Commercial Operation):

So mam f,,

Forecast Achieved T'

INITIAL CRITICALITY

__DZ@@__

_DfgDZgD_

,gg ff

~

~~

~

~

C MMERCI L OP RAT ON 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 TELEPHONE ___60_5_2 52 53_0_0__-_

2

_9-

_ MON _T_H:

Janua_rY_1987--

DAY AVERAGE DAILY' POWER LEVEL DAY-AVERAGE. DAILY POWER LEVEL t.

1

___________1z255________

17 ________-_1 4 5_ _1 _ _ _ _ - =

2 2

_ _ _ _ _ _ _ _ _ _ _1 z _2 _4 _7 _ _ _ _ _ _ _ _ _ _ _

18 __

=___1z_101_-_-______--

12 i

3

- _ _ _ _ _ _ _ _ _ 2 _ _5 _1 _ _ _ _ _ _ _ _ _ _ _

19 ____________0_______

i

__________ z2_55___ _______

20 __________-_0_-__=---

= - -

1 __

4 5

. - - _ - _"_ _ _ _ _1A2_47____________

21 __-_________O______________

-_____A__4_7____----

22 ______-_-_-_0_____________

6 1 2 4

C 7

_ _ _ _ _ _ _ _ _ _ _1 z 2 5_ 5 _ _ _ _ _ _ _ _ - _ _

23 -___________0_-____________

  • s 8

___________11_5_ _1_-

24 _

________O________-__-__

2 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 ___________1 251 30 0

1

  • ?

15 ___________1 _25_1___________

31 _ _ _ _ __, _____O_______-__--__

1 _

g t 5.1 16 _- _-______1 2

h

. t-

\\

REFUELING INFORMATION DOCKET NO.

@g-ggg _

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_

Egt _@ggg____

3 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 Ponent Action to No.

Date Type; llours Reason Down Reactor LER NO.

Code Code Prevent Recurrence 2

3 4

5 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

1 n/a n/a 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 L._Hu11____

2 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___

___21Zz ___

_242914___

5 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 S@gt9Zg_

t 17.

Gross Electrical Energy

__gg9 @gg__

@t119tigg_

Generated (MWH)

__gg9 @gg_

t t

18.

Not Electrical Energy 924 @g1_

__g69 92(__

21 Generated (MWH)

__g@9 92@_

t t

t 19.

Unit Service Factor

___g9.13__

___29.13___

___Z@313__

___29 13___

___Z@.13,_

20.

Unit Availability Factor

___g9313__

3 21.

Unit Capacity Factor

___g9 23___

___Z@.@g__

(Using MDC Net)

___29 Z3__

3 3

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 _ _ _ _ _

__ Hull COMPLETED BY J.L.

56E2 5325566~

TELEPHONE 9

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 _2 _8 _3 _ _ _ _ _ _ _ _ _ _ _ _ _

18 ___________0______________

1 3

_ _ _ _ _ _ _ _ _1 z _2 _7 _6 _ _ _ _ _ _ _ _ _ _ _ _ _

19 ___________O_______________

4

_ _ _ _ _ _ _ _ _1 _2 _7 _6 _ _ _ _ _ _ _ _ _ _ _ _ _

20 ___________0_______________

A 5

_________1 276 21 ___________O______________

L_-

6

_________1A _2 _7 _2 _ _ _ _ _ _ _ _ _ _ _ _ _

22 ___________0_______________

7

_ _ _ _ _ _ _ _ _1 _2 _8 _0 _ _ _ _ _ _ _ _ _ _ _ _ _

23 ___________0______________

1 8

________1126_0 24 ___________O______________

9

_________1 20_1_____________

25 ____________0______________

A__

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_______________

w m

REFUELING INFORMATION DOCKET NO.

pg-@g9_______

UNIT pVNGg-g______

DATE ggflgf8Z_____

COMPLETED BY J.L._ Hull ____

TELEPHONE

$g2-933-9399_

Ext _gg93____

3 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

  1. Ponent AC'I "
  • 3 2

3 4

5 No.

Date 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

~

Exhibit F - Instructions F-ForccJ Reason:

Hethod:

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-I f

4 p,

~

b

'Nr&r' Arizona Nuclear Power Project 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. Scrog8 ns, Director 1

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