ML20132E318

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Monthly Operating Rept for Apr 1985
ML20132E318
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 04/30/1985
From: Richardson M, Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Barry L
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
ANPP-32612-EEVB, NUDOCS 8507170676
Download: ML20132E318 (6)
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NRC MONTHLY OPERATING REPORT 9

DOOMET NO.50-528 UNIT NAMEPVNGSri DATE5/06/85 COMPLETED BYM.P. Richardsgn TELEPHONE 602-932:5300 Egt, 6523 OEEgellNG SIBIUS

1. Unit Name: Palg Verde Nucigar Generating Statiget Unit 1
2. Reporting Period: Sgtil 1985
3. Licensed Thermal Power (MWt): 3@00
4. Nameplate Rating (Gross MWe): 1304
5. Design Electrical Rating (Net MWe): 12ZO L Maximum Dependable Capacity (Gross MWe):Tg bg determingd
7. Maximum Dependable Capacity (Net MWe): Tg be dgtgrmined
8. If Changes Occur In Capacity Ratings (Items . mber 3 Through 7)-Since Last Report, Give Reasons: __________________

______________________NZ8________________________________

9. Power Level To Which Restricted, If Any (Net MWe):190 MWt 10 3Wg)
10. Reasons For Restrictions, If Any:Lgw Pgwgr Oggrating Liegnsg This Month Yr.-to-Date Cumulative
11. Hours In Reporting Period ___720____ __2880____ _2880___
12. Number Of Hours Reactor Was Critical ----- __--

0 -_-__e____ ____e___

13. Reactor Reserve Shutdown Hours _____0____ _____0____ ____0___
14. Hours Generator On-Line 0 0 0
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated _____0____ _____0____ ____0___

(MWH)

17. Gross Electrical Energy Generated 0 _____0____ ____0___

(MWH)

18. Net Electrical Energy Generated _____0____ _____0____ ____0___

(MWH)

19. Unit Service Factor ___N/A____ ___N/A____ __N/A___
20. Unit Availability Factor ___N/A____ ___N/A____ __N/A___
21. Unit Capacity Factor (Using MDC ___N/A____ ___N/A____ __N/A___

Net)

22. Unit Capacity 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 (Type, Date, and Duration of Each): __________________________________________________
25. If Shutdown At End Of Report Period, Estimated Date of Startup __,,__

__N/A_______________

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

Forecast Achieved INITIAL CRITICALITY ___5/85_____ ___N/A_______

INITIAL ELECTRICITY ___6/85_____ ___N/A_______

COMMERCIAL OPERATION __11/85_____ ___N/A_______

AVERAGE DAILY UNIT POWER LEVEL pg p

= g

W r .

DOCKET NO. 50-528___ __,

U N I T _ _ _ _ _ _ P V N G. S - 1 _ _ - _ _ _ _ _

D A T E _ _ _ _ .. _ 5_ _/_0_ 6,/_ 8_ 5_ _ _ _ _ _ _ _

COMPLETED BY_M__. P. R i c_h a. .rd._ s. o. n T E L E P H O N E ._ 6_ 0._2_ 9_.3_ 2.-.- 5_3. 0. 0

_ E_ _x._t _ 6_ 5.9 3_ _ _

M O..N.T H_ : April 1985

}

l DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) j 1 --- _ _____0__ ____ ____ 17 ________ -

0 --_-_---_ --

2 _ _____0__________ ___ 18 ____ _______0____ ________

- 3 ______.____0________--- 19 ___ ___._____0 -__-__ _ _ _ _ _ _

4 ___ ___ _.__0___. _ __ _ 20 ___ ________0___.__ __ __

5 _____._0_________.___ 21 ____________0__ _ ____ __

6 _ _____ _ _0__________ _

22 _____ _____0_ __ _ ___

7 _______0_________.___ 23 _ _ ________0_____ _ ___

8 ____ ______0 - _ _ _ ____

24 _ __ _____0_____________

9 __ __ __ _0 ___.__ ____ _ 25 ____.__ __. _0 ._______

10 ____ 0____ _

26 __ _ .____0 _ _______

11 __________ 0_ _ _ ___ __ 27 __ _ _0 _____ .._____

12 _____. _ __0 - _ ____ ___ _ 28 _ __. ____ 0__ _ _ ___

13 _.________ _0__ _-__ __ __ 29 __ ______- 0_ _ _____

14 -_- _ 0_ ________ _

30 _ __ __0 __ ____

15 _. . 0_ ___ _____

16 ___________-0__ _____ _ .

J

c:

.EMMM8BY QE OPEBBIING EM8g81ENCE EQB ISE MQNIH DOCKET NO.___QO-52B___________

UNIT PVNGS-1 DATE_________QLehl@$__________

COMPLETED BY_Mc P. Bichardson__

TELEPHONE __602-932-Q300_______

__Ent._ 6593__________

4/05 - Began post core Control Element Drive Mechanism performance.

i 4/21 - 1414 Entered Mode 4, RCS temperature 210 F.

4/22 - Closed Reactor Trip Switch Gear and started CEA Patch Verification.

4/30 - Entered Mode 3, RCS temperature 444.85 F.

Specification 6.9.1.6 requires the documentation of all challenges to the safety valves. No such challenges occurred during the 4 reporting period.

l DOCNET NO. sn_s9n UNIT SHUTDOWNS AND POWER REDUCTIONS PVNC4 1 UNIT MAMC DATE s/06/As .

M . I' . E c hn rri enq COMPLETED BY TEl.EPHONE - 417-5700 vvr Aso1 Method of Shutting Down System Component Cause at Corrective 2 3 1.[R 4 5 Action to 1 Du ra t ion Code Code Prevent Recurrence Type (Hours) Reason Reactor No.

No. Date .

Not applicable - reactor N/A .

has not achieved initial criticality.

3 Is 1 2 Method: Exhibit F - Instructions F-Fo rced Reason: 1-Manual ror Preparation or Data S-Scheduled A-Eauipment re f luro (Expla in) 2-Hanual Scram. Entry Shcots for Licensee D-Maintenanco or Test 3-Automatic scram. Event Report (LER) File C-Refueling 84-Contintea tion f rom (NUREC 0161)

D-Regtsta tory Rest riction Previous Month E-Operator Training h License Examination 5-Reduction of 207, 5 F- Admini st ra t ive or Creator in the Exhibit H-Same Source C-Operational Error (Expla in) Past 2fa Hours H-Other (Explain) ,

6-Other (Explain) 2940u

~

, REFUELING INFORMATION j - l DOCKET NO._Q0:Q28__________

UNIT _______EVNGS-1_____

DATE_______5[0@f8g_____

COMPLETED BY_M.E._ Richardson TELEPHONE __60g-932:5300____

__ ggt._ 6523_______

1. Scheduled date for next refueling shutdown.

10/01/87

2. Scheduled date for restart following refueling.

11/19/87

3. Will refueling or resumpt ion of operat ion thereaf ter 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._2&l___________

b) In the spent fuel' storage pool._____0_______

7. Licensed spent fuel storage capacity.____1332______

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).

9 9

9

P.-

GhE.

Arizona Nuclear Power Project P.O. BOX 52034

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528, License No. NPF-34 April Monthly Operating Report File: 85-056-026; G1.01.10

Dear Mr. Barry:

Attached please find the April,1985 Monthly Operating Report prepared and submitted pursuant to Specification 6.9.1.6 of Appendix A (Technical 3pecifications) 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.

If you have any questions or concerns, please contact me.

Very truly yours, i A-CL R hlU E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/GEC/mkm Attachments- ,

cc: J. B. Martin (all w/a)

R. P. Zimmerman E. A. Licitra A. C. Gehr

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