ML20137X911

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Revised Monthly Operating Rept for Jan 1986
ML20137X911
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 01/31/1986
From: Richardson M
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML20137X865 List:
References
NUDOCS 8603120036
Download: ML20137X911 (7)
v • d • e


Text

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t NRC MONTHLY OPERATING REPORT DOCKET NO. 50-528 UNIT NAME PVNGS 1 DATE 02200286 COMPLETED BY M. P._ R i ghardggn TELEPHONE 603-93Rr530@

Ent t 6s93 OEEE911NG SIBIUS

1. Unit Name: Palo Verde Nucleat Genergting Stgt iggt Unit 1
2. Reporting Period: January 1286
3. Licensed Thermal Power (MWt): 3800
4. Nameplate Rating (Gross MWe): 1403
3. Design Electrical Rating (Net MWe): 122@
6. Max t raum Dependable Capacity (Gross MWe): Tg be ggtermined
7. Maxitaum Dependable Capacity (Net MWo): To be determined
8. If Changes Occur In Capacity Ratings (I tems Nuraber 3 Throuch 7) Since Last Report, Give Reasons: __________________

________________ Recalculated According to definition _________

9. Power Level To Which Restricted. If Any (Net MWe) _NONE____
10. Reasons For Restrictions, If Any __________________________

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period ___744____ ____744___ __9504____
12. Number Of Hours Reactor Was Critical ___385.5__ ____385.5_ ._ 2812.5
13. Reactor Reserve Shutdown Hours _____0____ _____0____ ____0____

14 Hours Generator On-Line ___363.8__ _.__363.8__ __2383.6_

15. Unit Reserve Shutdown Hours _____0____ _____0____ ____0____
16. Gross Thermal Energy Generated 1,065,571_ 1,065,571_ 5,659,760_

(MWH)

17. Gross Electrical Energy Generated ___428,000, __428,000_ 1,764,700_

(MWH)

18. Net Electrical Energy Generated __413,700_ __413,700_ 1,541,350_

(MWH)

19. Unit Service Factor ___N/A____ ___N/A____ __N/A____
20. Unit Availability Factor ___N/A____ ___N/A____ __N/A____
21. Unit Capacity Facter (:Using MDC ___N/A____ _ _ _ N / A ,_ _ __ _

N/A___,

Not)

22. Unit Ca paci t y Factor (Using DER ___N/A____ ___N/A____ __N/A,_ _

Net)

23. Unit Forced Outage Rate ___N/A____ ___N/A____ ,_N/A____
24. Shutdowns Scheduled Over Next 6 Months (Tyoe, Date, and Duration of Each): __Syrveillance [egt Ogtage : J/85t 42 d3yn,_____

250 If Sh ut down At End Of Report Period, Estimated Date of Startuos______

26. Units In Test Status (Prior To Commeretal Operation):

Forecast Achieved INITIAL CRITICALITY _.,5/85_____ ___5/25/05___

INITIAL ELECTRICITY ___6/85__..__ ___6/10/85.,__

COMMERCIAL OPERATION __11/85_____ _ _,_ _ _ N / A _ _ ._ _ l l

8603120036 860304 PDR ADOCK 05000528 R PDR

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REFb2 LING INFO.9x AT I ON DOCKET NO._QO;533__________

UNIT _______PVNOS;1_____

DATE_______0gf004@@_____

COMPLETED BY_M.P _ n Ric3ardsgn TELEPHONE __60s-23s-5300____

__Entu 6523_______ .

1. Scheduled date fer next refueling shutdown.

03/01/S7

2. Scheduled date for rectart following r e.f u e l i n g .

04/13/S7

3. Will refueling or resumotion of coeration tnereafter recuire a Tecnnical Soecifica: 1cn change or other license amer.cnent?

Not Yet Determinec What will these be?

Not Yet Determinec 4 Scheduled date for s ubtr i t t i ng orococed licensing action and succorting infcrYation.

Not Yet Determinec

5. Important Licensing consicerations associated with refuelir.0,
e. g. new or different fuel design or suco11er, unreviewed design or performance analysic methods, significant c1ar.g e s in fuel cesign, new oceratir.g crocacures.

Not Yet Determinec

6. The number of fuel assenblies.

a) In the core._@41 ____

b) In the scent fue' storage

. cool._____0_______

7. Licensed soor.t fuel storage capacity.____1322______

Intended change in scent fuel ctorace cacacity.__Ngge______

8. Projected date of last refueling that can be discharged to scent fuel storage cool assuming present caoacity.

2002 (w/ annual reloces anc full core discharge capability).

g t

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AVERA3E DAILY UNIT POWER LEVEL DCCKET NO. _5 0_ _- 5_ 2 8_ _ _ _ _ _ _

U N I T _ _ _ _ _ _ _P _V _N G_ S _ _1 _ _ _ _ _ _ _ _

D A TE_ _ ____0_2 / 08_/ 0 6_______ _

COMPLETED B Y _ M _. _D.- _ _R _i__ c h _a r_ d s o _n T E L E P H O N E _ G_ O_w_

  • _9 _3 _2 _ _5 -3_ _? 0

_E_ _x _t _. 6 5_ _9 3 _ _ _ _ _

M_ O_ _ N _T H_ : January 1986 DAY AVERA3E DAILY POWER LEVEL DAY AVERAGE DAILY PCWER LEVEL (MWe-Nat) (MWe-Net) 1 ________1,253_____________ 17 __________(72) ____________

2 ________1,256_____________ 18 __________(72) ____________

3 ________1,180_____________ 19 __________(66) ____________

4 ________1,263_____________ 20 __________055_____________

5 ________1,266__-__-_______ 21 _________1,122____________

6 ________1,161_____________ 22 _________1,221____________

7 ________1,147_____________ 23 _________1,199____________

8 ________1,236_____________ 24 ___________564____________

9 __________658 ---__________

25 _______--_-(74) ----___-__-

10 ____-_____(75) _________ 26 ___-_______(74) ___-____---

11 __________ ( 77) ___-________ 27 _______-___(61) -______-___

12 ___--_____(79) ____________ 28 ___________

(55) _-___-_____

13 _____-__--(76) ____________ 29 ___________(63) _____._____

14 _-___-----(72) _-__________ 30 ___________5G1 -___________

15 __-._____.(72) ____________ 31 _ _ _ _ _ - _ _ _ 1 , 0 7 8 . _ - _ _ _ - - - - - --

16 __________(72) ________,____

ELJMt9Bv GE O2E39Ilhe E3EESIENCE EQB IEg [Q$IS DOCKET NO.___50-52O___________

UNIT _________oVNQS-1__________

DATE_________02fg3405__________

COMPLETED BY_M.P t Richardgog__

TELEPHONE __692-232-5399_______

__Ents 6523__________

01/01 0000 - Reactor ocwer at 100%, main turbine 1307 MWe.

01/03 1126 - Commenced power decrease for surveillance t est i r.p.

01/03 1132 - Reacter power at 85%.

01/03 1202 - Reactor ocwer at 71%

. 01/03 1219 - Commenced power increase to 95%

01/03 1320 - Reactor ocwer at 94.9%, main turbine 1245 MWe.

01/06 1026 - Transferred house loacs from auxiliary trarsformers to startuo trarsformers in crocaration for icss cf feecwater oumo test.

01/06 1238 - Reactor power at 60% cower.

01/06 1314 - Transferred house leacs from startuo trar.sformers to auxiliary trar.sformers in recovery from locs of feedwater oumo test.

01/06 1455 - Reactor power at ** 10 0% .

01/07 1533 - Performed reactor oower cutback test for load reject. Tri s aec raa in generator.

01/07 1546 - Placed main generator on line.

01/07 1656 - Reactor cower at 47% due to can strioter malfur.cticn.

01/07 1850 - Reactor ocwer at 9 6 /. .

01/09 1325 - Initiated Load Reject Test. main turoine trio via master tr:3. R? actor trio en lo DNDR caused by %cactor Coolant Pumo coastdown en 13.8 KV load shed due to failure of fast transfer. O r.e main steam safetv valve liftec.

r .

NRC Porthly Coera: Ing Reo:r:

Page 2 01/09 1327 - MSIS on low Steam Generator cressure.

01/09 1229 - Started ocenirg Steam Generator atmosoherie duma valves.

01/09 1920 - Plant in roce 3.

01/14 0205 - Comoletac clant coolcewn/cearecsurt:ation to accroximately 4C0 ce:rees F/523 osia to allow recairs to the -isolation valves to the pressuri er scray valves.

01/19 3120 - P. ant in Voce 2.

01/19 0834 - Reactor is cr tical.

01/19 1C42 - Enterec roco 1.

01/19 2247 - rain Turoine on l i r.e .

01/19 225? - Cormlencad ra:stre ;x :oser to 19%.

01/21 0700 - Plar: I r. xece 1, Rx ocwor at 90%. main turaire a 1167 M'.,e .

01/22 1930 - Rx cower at 99.5%, rnain t uroine at 1289 MWe.

01/24 1130 - Performed Locs of Load without Reactor Power CutcacW. System. Rx tricoed on H1 oressuri er oressure. All four RCPs tricoec for Natural Circula:lon Coo'.down Test. During this test a seconcary safety lifted.

01/24 2225 - Entercc roce 4 01/25 0115 - A steam vote was intentionally drawn an the Rx vessel heac c ur i r.n RCS deoressurtratior.. The st nara void was co;.a3Gec with use of the reactor coolant gas ven: svst a a ventino from the vessel head to the RDT.

.01/29 0250 - Entered roce 3.

01/29 1508 - Entered Moce 2.

01/29 1526 - Reactor critical.

01/29 1953 - Entered Poce 1.

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NRC Monthly Goera: Ing Seccet Page 3 01/29 2213 - Main Turbine on line a: 40 MWe.

01/30 0700 - Moce 1, Reactor oower at 40%, Main generator at 438 MWo.

G1/30 1520 - Reactor power at 69%.

01/31 0425 - Stabili:ed Reactor power at 99%.

01/31 0822 - Started the 120 hour0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> continuous run for the Art:ona Corooration Commission.

01/31 1520 - Started borating to '60% cower due to Hi Vieration on D FWPT.

01/31 1555 - Stoo=ec power cecrease at ' 7 0Y. .

01/31 1928 - Foce 1, Reactor oewer at 7 2%. . vain Generator at 911 MWo.

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. * . - ' UNIT SHUTDOWNS AN3 POWCR ACDUCTIONS

  • DOCKET No. Mn s9A ,,, .

UNIT CAHC PVfffM-I . g*1

  • ' DATE Ieb. III . 1986 .

COMPLETED BY H.F R i c ha rrimrt *" l TELEPliONC 4 U-51f tfl .?

PvP A%Q3 *

  • Hethcd or
Shutting *

(

Cown Systent Cornponent cause ar Corrective 1 Dura t ion 2 ' ~ 3 1 ER 4 5 Action to No. Date Type (stours) ftesson Rosetor _ rio. . Code Code ' Prevent flecurrence .

/

29 01/03/86 S 0 5

_B -

Surveillance testing.

30 01/06/86 S 0 B 5 Loss of feedwater pdmp test.

31 01/.07/86 S .2 S N/A

  • Reactor power cutback test.

32 01/G7/86 F 0 A N/A CB DGS Cas stripper malfunction.

. *d 33 01/09/S6 S 249.3 B 3' l-86-0006 EA 78

)

Load}ejectTest.' ' -

~

34 01/24/86 S 130.7 8 3 1-86-015 Performed Loss of Load without Reactor Power Cutback System.  !

35 01/31/86 F 0 A 5 SJ ^ '

P Dccrease power due to 111 vibration on 3 FWPT. Fixed pump.

1 1

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's I 2 3 r-rorced ;caton: ta S-Schoculed Hethod: [=hlblt T - Instructions A-to u i pa'en t fallpro (Cwplain) l-tonual for Prnparation or Da ta D-t'a intenance or T est -

2-tunnal Scra9 (ntry slicets for Licensee C-fterveling -

D-Degtst a tory fles t rf etion 3- Aistees t ic Scraw. (vent Report (LCR). file E-opara tor E rm inin't h License twanine tlen ia-continuation from (hun [C 0161) i-Administrative ernwfous Ponth c cporational Error (Explain) 5-Cedvetion or 2c it*Cther (Explain)

, or creator in the ~ 5 Exhibit H-Seme Source o rast 24 Stours

.. . , ,. *Cther (EmpialnD_ _ ________________ _

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