ML17037B740

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Letter Submitting the August 1978 Report of Operating Statistics, Shutdown Experience, and a Narrative Report of Operating Experience
ML17037B740
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 09/07/1978
From: Schneider R
Niagara Mohawk Power Corp
To:
Office of Nuclear Reactor Regulation
References
Download: ML17037B740 (11)


Text

REGULATORY INFORMATlON DlSTRIBUTIQN SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERlAL 50-220 REC:

NRC GRG:,SCHNEIDER R

R NIAGARA MGIIAWK PWR DQCDATE: 09/07/78 DATE RCVD: 09/12/78 DOCTYPE:

LFTTER NQTARIZED:

NO

SUBJECT:

FORWARDING SUBJECT. F'ACILITY" MONTHLY 1978 PLANT NAME: NINE MILE PT UNIT 1

COPIES RECEIVED LTR 1

ENCL 1

OPFRATING REPT FOR TIRE MONTI.I OF AUGUSTA REVIEWER INITIAL:

XJ DISTF'IBUTOR INITIAL:

I LJ DISTRIBIJTION OF TI.IIS MATERIAL IS AS FOI LPWS +<<+<<~~+w~~~~~wwwww ANNUAI )

SEMI-ANNUAL 8( MONTHLY OPERATING RPTS

<OL STAGE)

(DISTRIBUTION CODE A008)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR I IIEF QRBkt3 BC+~W/6 ENCL RFG FILE,

/ENCL ENCL IIANAUER~~W/ENCL AD FGR SYS 8( PROJ~%W/ENCL REACTOR SAFETY BR~4~W/ENCL EEB4~4< II/ENCI EF,-LUENT TREAT SYSw~W/ENCL LPDR'S

OSWEGO, NY~H~ll/ENCL NATL LAB ANL~~~~W/ENCL TERA<t~EW/ENCL NSIC~~~~W/ENCL ACRS CAT B<<W/15 ENCl NRC PDR~4W/ENCL MIPC<<W/2 ENCL DIRECTOR DOR+4W/ENCL ENGINEERING BR+~W/ENCL PLANT SY TENS BR>>W/ENCL CORE F'ERFORMANCE BR++W/ENCL DISTRIBUTION:

LTR 41 ENCL 41 SI ZE:

1P+9P CONTROL NBR:

782500260

/

TI.IE END

i

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 5'1 Narrative of 0 eratin Ex erience

~b978 The unit operated at 78.4% electrical capacity factor with an availability of 96.9%%d for the month.

The month began with unit derated to 90.5% core thermal power (CTP) due to operation with an isolated reactor recirculation loop.

From September 1 through September 4, unit operated at 84K CTP with an electrical output of approximately 480 MWe.

At 1325 on September 5,

815 Reactor recirc M-G set tripped when water from nearby core drilling leaked into the control cabinet.

Control rods were inserted to maintain thermal limits.

At 1640, 815 recirc pump was restarted and control rods were withdrawn to approximately 80%

CTP and 460 MWe.

On September 6,

control rods were withdrawn to the original rod pattern prior to 815 recirc pump trip.

Until September 9, unit was at approximately 84%

CTP and 480 HWe.

On September 9, the load was reduced to 380 HWe to withdraw shallow control rods.

Pre-conditioning from 390 MWe was initiated and station output of 533 MWe (88Ã CTP) was reached on September 11.

On September 13, unit was reduced to 220 MWe to repair steam leak on bl3 feedwater pump flow control valve.

Control rods were withdrawn on September 14, after leak was repaired until 410 MWe was reached.

Pre-conditioning was initiated and station output of 554 MWe was reached on September 16.

Load was maintained until September 23, when unit was reduced to 450 MWe for control rod withdrawals.

Pre-conditioning was initiated and station output of 548 HWe was reached on September 25.

I ~

Unit maintained load until 2105 on September 29,'hen load re-duction for maintenance outage to replace b'll RRP cooler b'egan.

At 0141 on September 30, the unit was off the line.

At 0251, the reactor scrammed due to upscale spikes in the IRH's.

Cooldown of reactor continued until cold shutodwn was achieved.

OPERATING DATAREPORT OPERATliNG STATUS

1. Unit Name:

Nine Mile Point Unit /t1 Reporthig Period.'. 08 01 78 08 31 78

3. Licensed Thermal Power (ilDVt):
4. Nameplate Rating (Gross NIIVe):

640

5. Design Electrical Rating (Net Mme):
6. i~faximum'Dependable Capacity (Gross liflVe):
7. Maximum Dependable Capacity (Net lfWe):

610 Notes DOCKET NO.

-220 DATE 10 COqfPLETED IIY T.J. Perkins TELEPHONE ~315 ~2110 Ext.1312 S. IfChanges Occur in Capacity Ratings (Ilelil:, a','i.,".." '.i iv",,....".

art.

','.:. Gi"e Reasons:

9. Power Level To IVhich Restricted, IfAny (Net hfh'e):
10. Reasons For Restrictions, lfAny:

SCRAM Reactivit Coast Down 512 Mise Rx recirc pump f311 out This lfonth Yr.-to.Date Cumulative CORRECTION 85.4

24. 0
11. Hours In Reporting Period
12. Number Of Hours Reactor 1Vas Critical
13. Reactor Reserve Shutdown Hours
14. Hours Generator On.Line
15. Unit Reserve Shutdown Hours
16. Gross Thermal Energy Generated (iifIVH)
17. Gross Electrical Energy Generated (iaaf IVH)

IS. Net Electrical Energy Generated (iifh'H)

19. Unit Service Factor
20. Unit AvailabilityFactor
21. Unit Capacity Factor (Using MDC Net)
22. Unit Capacity Factor (Using DER Net)
23. Unit Forced Outage Rate
24. Shutdowns Scheduled Over Next 6 ilfonths (Type, Date. and Duration of Each):

59.

58.3

25. IfShut Down At End Of Report Period. Estimated Date of Startup:
26. Units ln Test Status (Prior to Commercial Operation):

Forecast A el l le red INITIAL CR IT I CA L IT Y IN IT I A L ELECTR ICITY COAfAIERCIALOPERATION

--= (it(77)

0 e

U MOoHAMK NMP-0200 NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 NAe&o/L O)pce o) Management In(o/Imation and Pfmg/Iam Coeteof Uebt'ed S~e6 NueLea/L ReguLatotcy Commcwkon 0las kingston, 8.C.

20555 RE:

'Dock& hlo. 50-220 8PR-69 Sepkembe/L 7,

1978 It p

i1

<<v PQ G~emen:

Sub~ed he/L~ ~ We RepoM o( Ope/u~g S~Wce and S~oxn Expe/u.ence fo/L AugLsk 1978 (o/L Che N~e hKLe Pet NueZea/L S~on Ueit IIl.

AQo ~needed m a Na/I/L~ve RepoM otI Opetcating Exp'.ence tIo/L Che month.

Ve/Ly~y yo~,

R.. Schneide/L V~ce Pce5&eet-ELmttu.c Pmdu~n xcI 17~e&o/L, 0(g.ce o( ISE (10 copra) hIRC Regin I O)pce (1 copy) 782gpp~6

OPERATING DATA REPORT OPERATING STATUS I. Unit Nan>c:

Nine Mile Point Unit ¹1 Rc >ortin Period 08/01/78 - 08/31/78

3. Licensed Thcnnal Power (hf>>Vt):

1850

4. Nan>eplatc 14ting (Gross MKc):

4

5. Design Electrical Rating (Nct hl)Ve):
6. hfaxiniun> Dependable Capacity (Gross hiIVc):
7. hfaxintunt Dependable Capacity (Net hf'Wc):

630 610 Notes DOCKET I40.

DlTE 9

7 78 COAlPLETEI> BY ~J, Perkins JBP

'BLEI'IIONE

~3-343-2110 ext-1312 S. IfChanges Occur in Capacity Ratings (ltcnis Nun>bcr 3 Through 7) Since Last Report, Give Reasons:

8/1 -.8/27

- S61 MVe

9. Povvcr Level To IVhich Restricted, IfAny (Nct hf)Vc):
10. Reasons For Restrictions, IfAny:

561 hffVe - Scram Reactivit 512 hme - Rx Recirc Pum

¹11 out This Month Yr..to.Date 5:,831.0 5, 20.7 744

11. Hours In Reporting Period
12. Number Of Hours Reactor Was Critical
13. Reactor Reserve Shutdown Hours
14. Hours Generator On.Line
15. Unit Reserve Shutdown Hours
16. Gross Thermal Energy Generated (M)VH)
17. Gross Electrical Energy Generated (hf)VH)

IS. Net Electrical Energy Generated (hf)VH)

19. Unit Service Factor
20. Unit Availability Factor
21. Unit Capacity Factor (Using hfDC Net)
22. Unit Capacity Factor (Using DER Net)
23. Unit Forced Outa e Rate
24. Shutdowns Schcdulcd Over Next 6 ihfonths (T 72.3 714.2 5,561.2 1,178,000 9,437,333 380,035 333, 680 3;143,108 3,037>486 95.4 95.9 95.4 9S.9 80.8 88.4 86.9 79.5 4.0 2.1 ype, Date. and Duration of Each):

Ciiinulati'vc 77423.0 5

6 9.

1204 54151.4 20.2 87,891,342 28,924,820 28,014,409 70.1 70.1 61.2 60.3 10.5

25. IfShut Down At End Of Report Period. Estimated Date of Startup:
26. Units ln Test Status (I'riorto Commercial Operation):

Forecast Aoilivred INITIAL CRITICALITY IislTIAL ELECTRICITY COI>ifhfEl(CIAL Ol'I.1(ATION I >/77)

UNITSHUTDOWNS AND POWER REDUCTIONS REPORT MONTH DOCKETNO..

~

TELEPHONE 31S-34 -2 1o Date A>>

~ N Liccnscc Event Repor t.

Cause A Corrective Action to Prevent Rccurrcnce 8-3-.78 F

29.8 Weekly Main Steam Isolation Valve partial closure'est, Main Steam Isolation Valve closed causing scram.

Possibility that operator tested isolation -that was not selected for test 8;11-78 F

12 ll Rx. Feedwater pump removed from service to repair oil leak.

8-17-78 8-27-78 6.6 F

102 H

H Pull Shaping Rods

/Ill Rx Recirc Pump cooler leak I

F: Forced S: Scheduled

(')/77)

Reason:

A-Equipment Failure (Explain)

II-Maintenance or Test C-Refueling D.Regulatory Restriction F.-Operator Training &: Liccnsc Examination F-Administrative G-Operational Error (Explain)

I I-Other (Explain)

Method:

I alan ual 2-Manual Scram.

3 AulolllaticScfaln.

4-Other (Explain)

Exhibit G - Instructions for Preparation of Data Entry Sheets Ior Licensee Event Report (LER) File (NUREG-OI6I) 5 Exhibit I - Satne Source

4

AVERAGE DAILYUNITPOWER LE EL DOCKET NO.

UNIT

'¹I COMPLETED IIY T.J. Perkins TELEPHONE 315-343-2110 ext.

1312 MONTH AUGUST DAY AVERAGE DAILYPOWER LEVEL (MWe.Net) 538 DAY AVERAGE DAILYPOWER LEVEL Qi Wc-Net

)

533 17 10 12 13 14 IS 16 538 26 224 438 466 525 532 536 539 535 499 534 533 532 18 19 20 21 23 24 25 26 27 28 29 30 31 538.

531 493 523 522 525 535 545 541 522 4

3 484 481 INSTRUCTIONS On this format, list the average daily unit power level in M'tVc-Net for each day in the reporting tnonth. Contputc to the nearest whole megawatt.

P)/77 'I