ML20127M658

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Monthly Operating Rept for Jul 1976 for Monticello Nuclear Generating Plant
ML20127M658
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 07/31/1976
From: Mayer L, Shamla W
NORTHERN STATES POWER CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 9211300369
Download: ML20127M658 (5)


Text

.__

e (3 D17-NBED NOMTHEMN 5TATK5 POWEM COMPANY MIN N E A PO LI S. MIN N E SOTA 9 5 40%

August 5, 1976 Q ,, , . . . , , . . . . a 416

., , 4d *

/

Director, Office of  %

Inspection and Enforcement O '

U S Nuclear Regulatory Ccennission 3 Ng A Washington, DC 20555 A

Dear Sir:

M.l'f 10NTICELLO NUCLEAR CENERATING PIANT Docket No. 50-263 License No. DPR-22 Monthly Operating Report i

July 1976 Attached are ten copies of the Monthly Operating Report for July 1976 l for the Monticello Nuclear Generating Plant.

Yours very truly, ,

h, '-

n

/. y/

L 0 Mayer, PE Manager of Nuclear Support Services N -

..(-1 f,f ,

MN*k ], h !dY.

cc: Director, IE-III, USNRC (1) .

~

l .--Director, MIPC, USNRC (2) l ',

1 4 4 GO,. 3

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9211300369 760731 PDR ADOCK 05000263 R PDR

i 3636 .

Rev. 2  !

3/3/76 OPERATING DATA REPORT ,

i DOCKET No. 50 263 _

UNIT 1 ,

l DATE 08/03/76 i

COMPLETED BY W. A. Shamla

{ TELElil0NE 612/295-5151. Ext. 111 a'

OPGATING STATUS

1. Reporting Period: JULY Gross llours in Report Period: 744 3 j

' 30 Currently Authorized Power Level (bMt): 1670 Max. Depend. Capacity (SMe-NET):

538 Design Electrical Rating (hMe-Net): 545.4 l

, 3. Power Level to hhich Restricted (if any) (FMe Net): N/A

4. Reasons for Restriction (if any):

4

! THIS FG ml YR TO DATE CU'fJLATIVE

5. Number ofIlours Reactor Was Critical ........... 744.0 4.842.8__ 34.69L.4
6. Reactor Reserve Shutdown llours ................. 0.0_ 0.0 940_.7,

! 7. Hours Generator On Line ........................ 744.0 4.756.9 31 494 4

, 8. Unit Reserve Shutdown Hours .................... 0.0_ 0.0 QA

9. Gross Themal Energy Generated (FMI) . . . . . . . . . . . 1.215.45L6 _7.354 111L1 57.623dE6.

l 10. Gross Electrical Energy Generated (!1.11) . . . . . . . . 404.950 _ 2.498.320 _16.969.37Q_.

11. Net Electrical Energy Generated (hMI) . . . . . . . . . . _3HJ16 .

2.392.708 16.213AQ0_..

! 12. Reactor Service Factor ......................... 100.0% 94.8( Z.7 2 8.%

13. Reactor Availability Factor .................... 100.0% 94.8%- 7S,R%

{

11. t h ti t Se rvice Fac tor . . . . . . . . . . . . . . . . . . . . . . . . . . . . 100.Q) 93.11.'._ 75.1%

! 15. Unit Availability Factor ....................... 100.0% 91.,11. 75 11

16. Unit Capacity Tactor (Using HDC) . . . . . . . . . . . . . . . -96.2% 17.0%___ _ . 67.6%.

Unit Capacity Factor (Using Design !Me) . . . . . . . . 94.9% 85.8%- 66.7% ;

17 .

1L Unit Forced Outage Rate ........................ . 0.0L qJL __ 9.9)i l'

19. Shutdows Scheduled Over Next 611onths (Type, Date and Duration of hach):

i' NONE

20. If Shutdown at End of Report Period, Estimated Date of Startup: N/A' 9

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3025 >

. Rev. &

3/3/76 ,

l i AVERAGE DAILY UNIT IWIR LLVEL i

DOCKET NO. 50-263 4

UNIT 1 t

I DATE 8/3/76 1 CQ(PLETED BY W. A. 9%l4A TELEPHONE 612/295-5151, Ext. 111 i

e i= yoggy JULY

DAY AVERAGE DAILY TWER LEVEL DAY . AVIRAGE IRILY POWIR LEVEL OMe Net) @We Net) 1 534 17 528 2 537 18 407 3 535 19 524 4 470 20 527 5 506 21 526-6 534 22 527 7 532 23 523 24 512 l 8 J2

' 25 9 534 525 10 528 26 519 27 439 11 _ 506 12 28 524 5_29 _

13 529 29 528 34 525 30 522 15 '527 31 527

16 529-l t

l L

. - - . . _ _ , . ~ . .

PAGE 1 OF 2

'027

.' - :r ' .

,f76 '

DOCKEF M). 50-263 -

UNIT NAE Monticello UNIT SlifTDOWNS AND POWER REDUCTIONS MTE 08/03/76 .

CGtPLETED BY W. A. Shanim JULY TELEP!0NE 612/295-5151 REiw i M M U Ext. 111

.EIHCO OF N SUITING D0hN I F: IU'CED DURATTON DIE REACIM CR REDUCING POWIR (2) CORRBCTIVE ACTIONS /CGMENTS NO. DATE S: SO'IINILEDj OKURS) RIASON (1) 22 760704 S 0 B 4 Power reduced front 100% to 75%

via recire flow reduction for CRD exert:ise, turbine valve testing and due to syst a load requir ment.

23 760705 S 0 H 4 Power reduced frun 100% to 80%

due to syste Ioed requirment.

24 760711 S 0 B 4 Power reduced frost 1001 to' 751 via recire flow reduction for CRD exercise and turbine valve te(1JngNEn1OD (1) REASON 1

A
Equiument Failure (Explain) {

B Maint. or Test 3: Automatic Scram 4: Other (Explain)

D$ gu t ry Restriction

. E: Operator Training and License Examination SlPMARY: F: Adatinistrative G: Operational Error (Explain)

II: Cther (Fxplain)

4 Page 2 of 2 2ag7 .

ner. 0 .

~;/76 i

DOCKET NO. 50-263 s UNIT MME Monticello UNIT StirrDNNS AND P0hTR REDUCTIONS 1RT11 08/03/76 ,

C04PLETED BY W. A. Sisamis REPORT MNH JULY TELEPIONE 612/295-5151 Ext. 111 i

' O MW OF E SifJtTING IDiN F: FORCED iX! RATION TEE REACTOR m S: SOEULED -(IK11RS) REASON (1) REDUCING FOhTR (2) umani.1IVE ACTIONS /CONENTS NO. DATE ,

t --.. -

1 .--

I 760718 S 0 B 4 Power reduced from 100% to 50%

! 25  !

via recirc flow reduction for CRD exercise, turbirm valve testing and imrestigation of  ;

suspected feedwa*er heater tube j-leak.

26 760726 5 0 B 4 Power reduced from 100% to 65% i via recire flow reducticn for CRD exercise, turbine valve test- ,

e ing and investigation of suspect-ed feedwater heater tube leak.

i

! (1) REASON (2) EG 1

ll A: Equipment Failure (Explain) f >

B: naint. or Test .

1

. 3: Autmatic Scra egu ry Restriction 4: Other (Explain)

D$

E: Operatnr Training and -

~

License Examination ,

St# NARY: Operated as a base loaded F: Administrative unit except for load G: Operational Error (Explain)

following on 7/4 and 7/5. II
Other (Explain)

p p e, g a e p- *g. p - - -

m [ - .a % . t l . ,

f NSID NORTHERH STATES POWER COMPANY M IN N e A PO LI S. MIN N E S OTA 8 8 401 C1 A P

b b

August 5, 1976 3 } '9 2 9 1976u :

t- e,s,

- 0 Director, Office of g, Inspection and Enforcement , //

U S Nuclear Regulatory Cccanission  % d I d\

Washington, DC 20555

Dear Sir:

}0NTICELID NUCIIAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Monthly Operating Report July 1976 Attached are ten copies of the Monthly Operating Report for July 1976 for the Monticello Nuclear Generating Plant.

Yours very truly, ,

L 0 Mayer, PE Manager of Nuclear Support Services LOM/*k

..jESTi' cc: Director, IE-III, USNRC (1) .3 s

Director, HIPC, USNRC (2) ( l ;,, :.

y^

A a ,i

\

  • 2026 -

. Rev. 2 3

3/3/76 OPERATING DATA REPORT DOCKET No. 50-263 UNIT 1 -

DATE 08/03/76 i

C(NPIETED BY W. A. Shamla TELEP110NE 612/295-5151, Ext. 111 I

OPERATING STARIS

1. Reporting Period: JULY Gross llours in Report Period: 744
2. Currently Authorized Power Level (FMt): 1670 Max. Depend. Capacity (hMe-hT.T):

538 Design Electrical Rating (FMe-Net): 545.4

3. Power Level to Which Restricted (if any) (FWe-Net): N/A
4. Reasons for Restriction (if any):

2 illIS FO?Ull YR TO DATE CthUlATIVE

5. Number of incurs Reactor Was Critical . . . . . . . . . . . 744.0 4.&42_8__ 34.69L,4
6. Reactor Reserve Shutdown llours ................. 0.0 .0 940_.7,
7. Hours Generator On Line ........................ 744,0 4.756.9 33.4944
8. Unit Reserve Shutdown Hours .................... 0.0- 0.0 __0t0..

l 9. Gross Themal Energy Generated (FfMI) . . . . . . . . . . . 1.215.453.6 7.354.2Zta__ 5L62346Lft

10. Gross Electrical Energy Generated (?MI) . . . . . . 404.950 _

l.498.320 _16.969.3_7.0

11. Net Electrical Energy Generated (FMl) . . . . . . . . . . AJ6 2.392 3708 16.213,300 _ _

j 12. Reactor Service Factor ......................... 100.0% 94.8%. 77 8_%.

t

13. Reactor Availability Factor . . . . . . . . . . . . . . . . . . . . 100.0% 94.8%. 79,9%;

l

14. Ilnit Service Factor ............................ 100.01 93.1%,,_ 7All .
15. Unit Availability Factor ....................... 100.0% 93_,11_ ._ 7!i.1% -
16. Unit Capacity Tactor (Using tDC) ............... 96.2% _87.0% _ _.__s7.6%
17. Unit Capacity F tetor (Using Design !We) . . . . . . . . _ 94.9% 85.8% 66J%
13. Unit Forced Outage Rate ........................ .0.0% ._ 0J1. ___ A9)
19. Shutdowns S-heduled Over Next 611onths (Type, Date and Duration of hach):

}ONE

20. If Shutdown at End of Report Period, Estimated Date of Startup: N/A

- - . - - + - - , - , ,.,,%.,,,,,,,.,._e,.. _ , , . , , ,w w ,,.,,e.w ,, . - - .

. 2025 Rsv. 0-3/3/76 -

AVERAGE DAILY UNIT IGIR IET.L DOCKET NO. 50-263 UNIT 1 DATE 8/3/76 C04P!2TED BY W. A. SHAMLA TELEPHONE 612/295-5151, Ext. 111 m JULY DAY AVERAGE DAILY IWER LEVEL DAY AVERAGE IRILY POWER LEVF1 QMe-Net) owe-Net) 1 534 17 528 2 537 18 407 3 535 19 524 4 470 20 527 5 506 21 526 6 534 ,

22 527 7 532 23 523 8 532 .24 512 9 534 25 525 10 528 26 519 11 27 439

__ 506 _,.

12 529 28 524 13 529- 29 528 14 525 30 522 15 527 31 527 16 529

c PA 2 1 OF 2

:. ? .

. .:i"6 DOCKET NO. 50-263 UNIT NAME Monticello tRJIT StifIl) OWNS AND POWER REDUCTI0tG MTE 08/03/76 COUT.ETED BY W. A. Shamla .

REPORT MI GI JULY TELEH ONE 612/295-5151 Ext. 111 l~ MFIliCO OF i TYPE SHLIITI?E DCMJ F: FORCED DLtn'ATION 111E REW OR NO. DATE S: SOH1ULED (IKURS) REASON (1) RITUCDU FOKER (2) CORRILTIVE ALTIONS/COMENTS

! 22 760704 S 0 B 4 Power reduced fr a 100% to 75%

~

via recire flow reduction for CRD exercise, turbine valve testing and due to system load requirement.

23 760705 S 0 H 4 Power reduced fra 100% to 80%

due to syst m load requirenent.

24 760711 S 0 B 4 Power reduced frm 1001 to 751 -

via recirc flow reduction for CRD exercise and turbine valve (1) REASON te@W A: Equirnent Failure (Explain) 1: Manual B: bhint. or Test 2: Manual Scram C: Refueling 3: Autcoatic Scram D: Regulatory Restriction 4: Other (Explain)

E: Operator Training and License Examination SG M %Y: F: Adninistrative G: Operational Error (Explain) i li: Ctber (Explain)

Page 2 of 2 .

20Z7

  • c.n . 0 .

5/76 DOCKLT 10. 50-263 -

UNIT NUE 2nticello UNIT StrMhNS AND FONER REDULTIN IRTE 08/03/76 C(NPLETED BY W. A. Shanla REPORT MIN'IH JULY TELEPt0NE 612/295-5151 Ext. 111 METIID OF M E" Sf31 TING DOWN F: FORCED DURATION TEE REACIER OR

. REDUCING POWER (2) CORRILTIVE ACTIONS /CGNENTS NO. DATE S: SOIQULED (IMJURS) REASON (1)

O B 4 Power reduced fra 100% to 50%

25 760718 S' via recirc flow reduction for CRD exercise, turbine valve l testing and investigation of l

suspected feedwater heater tube t

leak.

1 0 B 4 Power reduced fra 100% to 651 26 760726 S via recirc flow reduction for CRD exercise, turbine valve test-ing and investigation of suspect-ed feedwater heater tube leak.

(1) REASON (2) EU A: Equipment Failure (Explain)

B: Maint. or Test

{3: Autanatic Scran l

9-4: Other (Explain)

D$ R gulat ry Restriction

! E: Operatnr Training and License Examination

. SUM 4ARY: Operated as a base loaded F: Administrative imit except for load G: Operational Error (Explain) following on 7/4 and 7/5. II: Other (Explain)

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