ML20207F707

Monthly Operating Rept for Sept 1986

ML20207F707
Person / Time
Site:	Palo Verde
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-38674-JGH, NUDOCS 8701060196
Download: ML20207F707 (5)

Text

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.e NRC MONTHLY OPERATING REPORT DOCKET NO. Sg-52g UNIT NAME PVNGS-1 DATE 16

--_7_69786 COMPLETED BY J.L.~ Hull TELEPHONE 662 93 ~ 5_300

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-_PER_A_T_I_N_G__----- STATUS

1. Unit Name: jalo_ Verde _ Nuclear _ Generating _Stationt_ Unit _1 2.- Reporting. Period: Segtember_19@@

3. . Licensed Thermal Power (MWt): 3399

4. Nameplate Rating (Gross MWe): 1493 5.- Design Electri'al Rating (Net MWe): 1221

6. Maximum Dependable Capacity (Gross MWe): 1393

7. Maximum Dependable Capacity (Net MWe): 1221

8. .If Changes Occur In Capacity Ratings (Itema 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: _______________________ ___

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---_ .-----_- =-----__--_-__-_--___--____---

This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period ____Z2p___ ___55_2p____ ___5529___

12. Number of Hours Reactor Was Critical 569.1_ ___3045.5__ ___3045.5_

13. Reactor Reserve Shutdown Houra _____g____ _____Q_____ _____Q____

14. Hours Generator On-Line __ 535.9_ ___2936.2__ ___2936.2_

15. Unit Reserve Shutdown Houra _____Q____ _____Q_____ __ Q____

16. Gross Thermal Energy Generated (MWH) 1,929 t 290_ 19,573 t S95_ 1_Qt_73 S t5_95

17. Gross Electrical Energy Generated (MWH) __664,80_o_ _3 t641_t_QQ_ 1 _3 t641_t_QQ 1

18. Net Electrical Energy Generated (MWH) 613t217_ _3t 359tg71_ _3t350 tO71

19. Unit Service Factor ___74.433_ ____53.193_ ____53.193

20. Unit Availability Factor ___74.433_ ____53.193_ ____53.193

21. Unit Capacity Factor (Using MDC Net) ___@9.753_ ____49.7Q3_ ____49.7Q3

22. Unit Capacity Factor (Using DER Net) ___q9 t 753_ ____49.7Q3_ ____49.703

23. Unit Forced Outage Rate ___25.573, ____19.763_ ____19.763 l 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration I

of Each): ___,,___________________________________________________

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

i

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

Forecast Achieved b INITIAL CRITICALITY __5fp5__ _5/25/95_

l INITIAL ELECTRICITY - - _6 / _8 5---

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0 _/ _8 5--

l COMMERCIAL OPERATION _11/p5__ _2/13fpp_

l 8701060196 861014

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. ~~

50-52G ~~~~~~~~

UNIT - --- - - -PVNG - _5_ ~ -- l _- - = _ .-

DATE --_---------_/_86 10/09 ---------

COMPLETED BY J.L. Hull TELEPHONE- 565~555-5566~~~

Ext. 6593 N

MONIH: Septesaber 1986

' DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1 _ - =-

1 11_4_1_----=- _ 17 --------_ 1 1244 -----=_. --

2- - ----- - - _8 7------------ 18 --------- 1 1 239--

3 --------_-----------------

0 19 -- --_-

1x---------------

243

-4 -- --------------------

O 20 - - - - - - - - - 1x -2_4 _4------_-

5 _ _=-------------_---

0 21 --------- 1 1247_--_ -------

6 --- _--------------_--

547 22 --_------ 1 1245 --------

p:

7 ---------- 12_3_3 1 ------------ 23 --------- 1 1248 ------ _

8 ------ - --- 1 21 2 7 _ - - - - --- _- 24 ---_----- 1 1253 --------------

9 --------------------------

675 25 ---------

1x---------------

253 10 - --------------------

268 26 --------- 1 1257 --------------

11 = --- 1 1177 -------------

27 ---------

1 1_2_3_3__------_--_

12 - _==------------_----

0 28 ------_--_12--24_4_---_-------

13 - - -------------------

0 29 --------- 12-_57 2 -------------

14 ----.---------------------

O 30 --------- 1 2253 --------------

15 --------------------------

535 16 _ . -- 1 1245 _------___ ---

~ . . . . . _ . _____._ . . . . _ _ _ . _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _

b...,

c REFUELING INFORMATION DOCKET NO. 50-528_______

UNIT PVNGy-1______

DATE 19/99/p3_____

COMPLETED BY J.L._ Hull ____

TELEPHONE 392-932--5309_

Egt 2_@593____

l. 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 niaber 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. 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).

a

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 59-523_______

UNIT PVNGS-1______

'DATE 19/99/35_____

COMPLETED BY J.L 2_Hu11____

TELEPHONE pp2-93_2-53pp_

E32 t _@593____

09/01 0000 Reactor Power at 100% - Mode 1.

09/02. 0839 Reactor. Trips on apurious Steam Generator Low RC Flow Mode 3 09/05 1532 Reactor Critical -

Mode 2 09/05 1657 Entered -' Mode 1 09/06 2050 Synchronize Generator to Grid 09/09 1338 Turbine Trip due to actuation of the Turbine / Generator Auxiliary Trip and Leck-Out - Mode 1 09/10 1129 Synchrontze Generator to Grid 09/11 0236 Reactor Power at 100%

09/11 2334 Reactor Trip on Low S/G pressure due to actuation of Steam Bypass Control. System at 1004 power - MSIS initiated -

2'MSSV's lifted.for approximately 3 minutes Mode 3.

'O9/14 2337 Entered Mode 2 09/14 2342 Reactor Critical 09/14 0143 Entered Mode 1 09/14 0553 Synchronize Generator to Grid 09/15 1510 Reactor Power at 70% and increasing to 100%

09/30 Reactor Power 100%

' O ' UNIT SHilT00WNS ANO POWER REDUCTIONS .<;- DOCKET NO. ' 911-9? A 'e

UNIT NAME is - I -

s

. DATE M6 .

LL

~ ' COMPLETED BY . . .

TELEPHONE 9 U 'i100 '

, vve Ase3 4

Nethod or Shutting .

Down System Component Cause & Corrective &

, 1 Duration 2

• 3 LCR 4 5 Act8cn to 1

No. Date Type (liou rs ) Reason Rosctor No. Code Code

• Prevent Accurrence 10 09/02/86 F l'08. A -

3 1-86-044 JC .PDT Reactor Trip due to Steam Generator. low RC flow. . Trip occurring on RPS Channels B and D.

1 4

11 09/11/86 F 54.4 H .3 1-86-053 JI FT Reactor 'frip on- low Steam Generator i

Pressure.and an automatic MSIS occurred.

The event was initiated by loss of Main Steam flow signals on all 4 steam flow inputs; to the SBCS. The loss of all four steam flow channels was caused by a circuit card i extender. The short circuit occurred-

, . while an_ Instrumentation and Controls l Technician was performing maintenance on i the cabinet.. The root cause of this

! , event was a procedural inadequacy.

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T-Forced Reason is S-Schodufed Hethod: Exhibit F = Instructions A-touipment ralluro (Explain) 1-Ha ntia l for Prnparation of Data D-Hiintenanco or Test 2=Hanua l Scram. Entry Sheets for Licensee ,'

C-Reftseling 3-Automatic Scram.

i 0-Regulatory Restriction [ vent Report (LCR) file '

t-Opera tor Training h I.lconse Examina tion 8 -Continten tion f rom-4 (NURCC 0161) i T- Admin t s t ra t ive rrnvious Month C-Ope ra t iona l Error (Explain)

• 5-Redtsction of 20% 5 '

H.other (Explain) , , ,. , or Creator in the Exhibit H-Some Source Past 24 flours 9-other (Explain)

, 9Rhnee *  ;.

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Arizona Nuclear Power Project P O. box 52034

• PHOENIX. ARIZONA 85072-2034 October 14, 1986 ANPP-38674-JGH/PGN/98.C5 Mr. Ronald M. Scroggins, Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 1 Docket No. STN 50-528 (License NPF-41)

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 Apper/ dix A (Technical Specifica-tions) 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.

On September 11, 1986, two Main Steam Safety Valves lifted for approximately 3 minutes in Mode 3 following a reactor trip on low steam generator pressure.

If you have any questions, please contact me.

Very trul yours, a(7 J. G. Haynes Vice President Nuclear Production JGH/PGN/rw Attachment cc: 0. M. De Michele (all w/a)

E. E. Van Brunt, Jr.

J. B. Martin R. P. Zimmerman E. A. Licitra A. C. Gehr INPO Records Center S , $

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