ML20207F710

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Monthly Operating Rept for Sept 1986
ML20207F710
Person / Time
Site: Palo Verde Arizona Public Service icon.png
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-38675-JGH, NUDOCS 8701060201
Download: ML20207F710 (10)


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NRC MONTHLY OPERATING REPONT i' -

1 DOCKET NO. 50-529 UNIT NAME, PUNG5-2 i i 56/65/E6 i '

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DdTEr[.

COMPLE ED BY 3 LI Eu11

l. .. TEL,EP. HONE 56_ 2__5_5 3__55_0_6 '

% s Ext. 6593_

COMMERCIAL OPERATION \ ,

.I OPERATING ' STATUS 'S ,  !'

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1. Unit Name: Palo Verde Nuclear Generating _Stationt_ Unit _2
2. Reporting",Geriod: September _,,19q6 1,
3. Licensed Thermal Power (MWt): 3800 )  !
4. Nameplate Rating (Gross MWe)7: ,14pg ,

) } ,- ,

5. Design Electrical Rating;(Net'MWe): '
$231; ',
6. Maximum Dependable Capacity (Gross MWeb: 13;tf(

7 Maximum Dependable Capacity (Net MWe) 6 ]339,

8. If. Changes Occur In Capacity Ratings < Items Number 3 Through 7)

. Sinc'e,Last Repckt, Give' Reasons: ___. ._[____j___________.

'p ;______________________,

9. Power Level tof Which Restricted. If Any_-.(Net MUe): _NONE_________
10. R e a n'o,n a \ F o r R e,s t r i c t i o n s , If Any: ____________ __ _ _ _ _ _ _ _ _ _ = _ _

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______\_Y ._ ?

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This Month Yr.-to-Date Cumulative'

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11. Hourn in Reporting Period __21_5____C ____215____ ___215 _

12.f Number of,Houra Reactor 5 J Was Cr(tical __251 1___ __151 2____ _151-1____

13. sReactor Reserve-Shutdown Hours _____O_____ _____O_____- _'____O_____
14. Hours Generator On-Line _ _ 1 3 9 ,._ 7 _ _ _ ___139.7___ .__139.7___
15. gUnit Reserve Shutdown F Hours -

_____O_____ _____O______ _____O_____

16.' Gross Thermal Energy

,- Generated (MWH) ,441t 921__ __441 t921__ __441 t921_

Gross Electrical Energy 17.I Gnherated (MWH) _143 t 409,, __143 t4QQ__ __143 t 4gg_

18. Het Electrical Energy .

Generated (MWH) _139,,508__ __13@t5gq__ __13qt5g8_

19. Utdt Service Factor _ _ _6_4. . 9_8_%_

. _ _ _ _ _ 6_ 4_ _. 9_ 8_ %_ _ _ _ _ _ 6_ 4_ _. 9_ 8_ %_

20. Unit Availability Factor ___64.98%_ ____64.983_ ____64.983 21.* Un14 Capacity Factor (Using MDC het) ,w_Q2.76x_ ____52.763_ ____52.76%

22, Unit Capacity Factor

,=ili (Ustr g DER Net) _ _ _5_2_ _. 7_6_x_ _ _ _ _ _5_2_ _. 7_6_x_ _ ____5_2__.7_6_%_

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> 23. Unit Forced Outage Rate ___35.Q23_ ____35 923_ ____35.Q23 uj , - ,

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

of Each): No_significant_ outage _ planned _until_after_ warranty _run_

25.f If Shutdown At End of Report Period, EsLimated Date of Startup:

____N__/A_______________________________________________-___________

, 26. Units in Test Status (Prior To Commercial Operation):

(/* \ Forecast Achieved INITIAL CRITICALITY _ _ _3 _/ _8 _6 _ _ _ _4 _/ _1 _8 _/ _8 _6 _

q INIT,ALI ELECTRICITY __6/pp__ _5/20/39_

e COMMERCIAL OPERATION 11/86 9/22/86 i

4

.L 8701060201 d PDR ADOCK 050 529 R PDR 4/

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s-NRC MONTHLY OPERATING REPORT DOCKET NO. 50-529 UNIT NAME -------PU G5-2 DATE -10/0

- - - _9 / _8 --6 COMPLETED BY J.L._ Hull ____

TELEPHONE ------------602-932-5300

_E_x_t.------6593 OPER3IJNg_FIbIgp

1. Unit Name: Pa l_o_V_er_d_e _N_u_cl ear _ Genera ting _ Stat _l ont_ Unit __2
2. Reporting Period: S_egt_en_ber__1 M
3. Licensed Thermal Power CMWt): 3399

'4. Nameplate Rating (Gross MWe): 1493

5. Design Electrical Rating (Net MWe): 1221
6. Maximum Dependable Capacity (Gross MWe): 1339
7. Maximum Dependable Capacity CNet MWe): 1335
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 Restrictions, If Any: _______________________________

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

This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period __595_____ __3754.2p__ _@ gyp.25__
12. Number of Hours Reactor Was Critical __461.5___ __2947.5___ _2947.5___
13. Reactor Reserve Shutdown Hours _____Q____ _____g_____ _____g____
14. Hours Generator On-Line __454.3___ __1644.2___ _1644.2___
15. Unit Reserve Shutdown Hours _____g____ _____g_____ _____Q____
16. Gross Thermal Energy Generated (MWH) I t S3pt389_ 3 t429 t433__ 3 t429 t433_
17. Gross Electrical Energy Generated (MWH) _547 t 7Qg__ l tg95t 2QQ__ l tg95 t 2Qg_
18. Net Electrical Energy Generated (MWH) _594t869__ _9'7 t481___ _917 t 4g1__
19. Unit Service Factor ____N/A___ ____NLA____ ____NLA___
20. Unit Availability Factor ____N[A___ ____NLA____ ____NLA___
21. Unit Capacity Factor (Using MDC Net) ____NLA___ ____NLA____ ____NLA___
22. Unit Capacity Factor (Using DER Net) ____NfA___ ____NLA____ ____NLA___
23. Unit Forced Outage Rate ____N{A___ ____NLA____ ____NLA___
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each): No_signif] cant _ outage _ planned _untiJ_after_ warranty _run_
25. If Shutdown At End of Report Period, Estimated Date of Startup:

____NLA__________________________________________________________

26. Units in Test Status (Prior To Commercial Operation):

Forecast Achieved INITIAL CRITICALITY 3/86 4/18/86 INITIAL ELECTRICITY ~~5755~~

~5725755-COMMERCIAL OPERATION _11/pp__ _9/22/p3_

i AVERAGE DAILY UNIT POWER LEVEL I 1

DOCKET NO. ~~50-529 ~~

UNIT _----_- P_V--_55_-2 ------_---

DATE --------10_/09/86 - -------------

i COMPLETED BY J.L. Hull 1 TELEPHONE ___6_65_~9_55_~5_5_66~~~ -

_ - _ E_ x_ t .---6593 -----

_M O N T H : September 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

.1 _ _ _12_O_2_8_ _ _ _ = - __.

17 -------__----_1'____-- 85 - .-

-2 _ --

1 z_0_24---------- 18 ---------

1x-----_--

255 ---

3 --------

1z--------

087 =_-

19 ---------

1x---

251 __-------

4 =- - _1 z 2 _4 _5 - =___ 20 _ ___-----_1 2-2_6_8---- _-

5 = 11----

257 _=_-_---- 21 --------_ 1 1263 --------==

6 ._- __1 1 M_4 __-=-

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7 _ _ _ --1z 2 _2 _8 _ _ _ _ _ - -

8 - 1__z_222-----_ . __-

9 .-_-- _

1x-- 237 -----------

10 -- _-1z242 ------------_-_

11 -_ -- -539 _--- --

12 _

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=_-__-._____ __

13 -- _----

302 _--- . _

14 - _---871 ---------------

i 15 _ _ -_743_------------

16 --_ _------------

835 __ --__

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. __59-529_________

UNIT ________PVNGS-2________

DATE ________1gfg9L86_______

COMPLETED.BY J.L._liull______

T E L E P H O N E _ _ _ 6_ 0_ 2_ _ 9_ 3_ 2_ _ 5_ 3_ 0_ 0_ _ _ _

___Eut._6593______

COMMERCIAL OPERATION nQN_TH_: September-1986 DAY AVERAGE DAILY POWER LEVEL 22 _ _ ___1,915 _____ _ __

23 _ . _ __ 23_5 _ _ ___

24 __ ___g.______________

2s =_ ===g__________=

-26 _ _ _ _ _6 _ _ _ - .____

27 _ _1,015 28 ==11231____ ___

29 _J ,231_____ __

30 _________1,259____________

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REFUELING INFORMATION DOCKET NO. 50-529_______

UNIT pVNGS-2_ _ _ _

DATE 10/09fpp_____

COMPLETED BY L L.._ Hull ____

TELEPHONE pO2-932-53OO_

Ext. 6593

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. ____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. Proyected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

2003 (w/onnual reloads and full core discharge capability).

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-529_______

UtlIT PVNGy -2__ _

DATE 19/09/35_____

COMPLETED BY J.L._ Hull ____

TELEPHONE 0 -932-530p_

502 E3t._@593____

09/01 0000 Reactor Power at 80% - Mode 1 09/03 0351 Reactor Power at 100% - Mode 1 09/11 1045 Turbine Trip / Reactor Trip due to Load Rejection Test Mode 3 09/13 0617 Reactor Critical - Mode 2 09/13 1052 Entered Mode 1

.09/13 1325 Synchronize Generator to Grid 09/13 1700 Reactor Power at 70%

09/13 1840 Reactor Power at 954 09/14 0330 Commenced 100 Hour Run 09/14 0915 Reduction of power to 57% due to Secondary Chemistry 09/17 0045 Reactor power 98%

09/17 0130 Reduction of power to 40% due to Secondary Chemistry 09/17 2100 Commenced 100 Hoar Run 09/22 0100 Completed 100 Hour Ru:t

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SUMMARY

OF OPERATING EXPERIENCE FOR THE. MONTH DOCKET NO. 59-529_ __

UNIT PVNGSb2_______

i DATE 19/99/ps_____

COMPLETED BY J.L._ Hull ____

TELEPHONE 392-932-5399_

E3t._@593____

COMMERCIAL OPERATION 09/22 1758 Reactor Power reduced to 40% due to Condenser Tube Leak

-09/23 1507 Reactor Trips on Low S/G Level due to a Main Feedwater Pump trip on low suction pressure. The low suction pressure was caused by securing heater drain pumps with a low condenser level being maintained due to condenser tube leak -

Mode 3 09/26 0700 Reactor Critical -

Mode 2 09/26 1535 Entered Mode 1 09/26 1824 Synchron1=e Generator To Grid

.09/26 1833 Reactor Power at 20%

09/26 2252 Reactor Power at 40%

09/27 0900 Reactor Power at 95%

09/30 Reactor Power at 100%

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'# UNIT SHUTDOWNS AND POWER REDUCTIONS .. DOCXCT NO. sin s;99' ;I

' UNIT NANC PVfM;S.2 . $

.  ! DATE 09/O 86 _ . *

, COMPLETED BY __ JOY _l.

TELEP310HC 9 0-s wo -

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Hethod or Shutting

  • Down System Component .

. 1 Duration 2

  • 3 1.ER 4 Cause & Corrective No. Date Type 5 Action to (Ifours) Reason Roactor No. Codo code ' Prevent Hecurrence

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'g 20 09/11 F 0

  • A , N/A N/A N/A N/A Turbine trip'on Load Rejection N Test / Fast Buss "Tranfer. Reactor . }

. . . ., Power ati 99% 4 21 09/11 F Sb.7 A 3 '

2-86-017 EA 25 Redct'or Trip *s on Load Rejection '

Test / Fast Btiss Transfer from 99% ,

react,or power.

22 09/14 F N/A 5 N/c[ SC COND. Secondary Chemistry reduces power from 95% to 57% (condenser tube leak) 23 09/17 F N/A A 5 N/A SG .COND Secondary Chemistry reduces power '

from 100% to 40% (condenser tube leak) l 4

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T-Torced Reason; .J 4 .

S-Schoduled A-Couipment railuro (ExplsIn)

Hethod: Exhibit F = Instructions D-itaintenance or Test 1-Manual for Prnparation or Da ta C-fic rose l ing 2-Hanoni Scram. (ntry Sliccts for Licensee ,

  • D-Regulatory nestriction 3-Antoma tic Scra.m. Event Report (LER) File '

[-Onnrator Training h 1.lcense Examination 4-continuation free- (NUREC 0161) * ,

' r-Administrativn Previous Month / '

C-operational Error (ExplsIn)

  • 5 neductlon of 20% 5 if-Other (Explain) , , * *

, or creator in the Pa st 2's afours Exhibit H-Seme Source

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i. 9-other (cxplain) *

' UNIT SHUTDOWNS AND F0WER REDUCTIONS . DOCKET NO.90-999 .s.

  • PVer:Q_

UNIT NAME . \

  • DATE UV/ UI /50 ~ . * ?-
  • COMPLETED BY T II&l I ~

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TELEPHONE ~ 9 U -S m n Fe Aso3 Hethod or * ';

Shetting Down System Componont Cause & Corrective 1 Duration 2

  • 3 f.ER 4 5 Action to No. Date Type IHours) Reason Rosctor No. Code Code ' Prevent Recurrence .

24 09/22 F N/A

  • A 5 N/A SG COND . Secondary. Chemistry. reduces power -

. . . from 100%'to 40% (Condenser Tube Leak) 25 09/23 F 15.5 G 3. 2-86-049 N/A N/A Re' actor Trip on low Steam Generator level, inadequate prodedure.

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b 1 2 3 T-Forced Renton; Method:

la S-Schedulce A-Eauipment refluro (Explain) 1-Hantsa l Exhibit F = Instructions D-itaintenance or Test for Prnparation or Data C-Herueling 2-Hanual Scram. Entry Slicets for Licensee D-Regtsta tory Restriction 3-Automa tic Scram. Event Report la-Continisation from- (NUREC 0161) (LER) File

  • E-Onnra tor TraininD k License Examina tion Prnvious Month

' r-Administrative 5-nedstetton or 20Y, 5 C-Ope ra t iona l Error (Explain) *

,** or Creator in the Exhibit H-Seme Source H-Other (Explain)

  • rest 28a llours onhnee *

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g. 9-Other (Expl In) . -

J, ok Arizona Nuclear Power Project P O. BOX 52034 e PHOENIX, ARIZONA 85072-2034 October 14, 1986 ANPP-38675-JGil/PGN/98.05 Mr. Ronald M. Scro8Ri ns, Director Office of Resource Fbnagement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 2 Docket No. STN 50-529 (License NPF-51)

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 Appendix A (Technical Specifica-tions) to the Palo Verde Nuclear Generating Station, Unit 2 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.

Due to PVNGS Unit 2 being declared commercial on September 22, there are two separate reports for Unit 2.

If you have any questions, please contact me.

Very truly yoters, Y

J. G. Ilayne '

Vice President Nuclear Production JGH/PGN/rw Attachment cc: O. M. De Michele (all w/a)

E. E. Van Brunt, Jr.

J. B. Martin R. P. Zimmerman y E. A. Licitra A. C. Gehr

. INPO Records Center f6

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