ML17037B735

Letter Submitting the January 1978 Report of Operating Statistics, Shutdown Experience, and Narrative Report of Operating Experience

ML17037B735
Person / Time
Site:	Nine Mile Point
Issue date:	02/07/1978
From:	Schneider R Niagara Mohawk Power Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML17037B735 (12)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS>

DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC:

NRC ORG:

SCHNEIDER R

R NIAGARA MOHAWK PWR DOCDATE: 02/07/78 DATE RCVD: 02/13/78 DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

FORWARDING REPT OF OPERATING STATISTICS AND SHUTDOWN EXPERIENCE FOR JANUARY 1978 AND A NARRATIVE REPT OF OPERATING EXPERIENCE FOR THE MONTH.

PLANT NAME: NINE MILE PT UNIT 1

REVIEWER INITIAL:

XJM DISTRIBUTOR INITIAL:

DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ++++>>>~%>+++>>>++

MONTHLY OPERATING REPORT FOR GRAY BOOK PREPARATION.

(DISTRIBUTION CODE A003)

FOR ACTION:

INTERNAL:

BRANCH CHIEF LEAR44W/2 ENCL EG FILE~~W/EN

++8/2 ENCL NRC PDR+4W/ENCL EXTERNAL:

LPDR S

OSWEGO, NY~~~W/ENCL TIC++W/ENCL NS IC~~W/ENCL.

BNL(NATLAB>++M/ENCL ACRS CAT B44W/O'ENCL DISTRIBUTION: 'TR 10 ENCL 10 SIZE: iP+hP THE END CONTROL NBR:

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V HlASAIRA lN U MajÃIAMK NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 Feb',

1978 0~e&o/L 0)pce o( IHanagement Info/IJII~on and Paogruun Co~ok Unit'ed Situ NueZea/L Regukato/Iy Commieamn 0/mhkngkon, 8.C.

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4g Submitted he/Leech ~ Che RepoM o) Ope/~ng S~Wce and ShutdoI0n Exp.ence tIo/L Janua/Iy 1978 (o/L Che one NLe Pet NueLeur.

~Lon Unit <1.

AQo ~ncZudedLb a na/vcMive /I.epos o( oping expel'.ence Jo/I, Che month.

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V~ce Pauk&nt-NucZea/L Gen~on mtm Enc.

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&neet'o/I. 0)pce of ISE (10 cop~u)

NRC Regin I 0)tIme (1 copy)

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Page 2

Jan.

22 Jan.

23 Jan.

24 Continued'with reactor startup: 0;At,0)iIO, a steam leak was discovered on the steam seal regulator'blocking valve.

Startup continued to rated pressure and scram test of the control rods was performed~.

Unit was then brought to a

hot standby condition to 'repair.'Ithe..steam.seal regulator blocking valve.

At 1030 repairs were compl'eted and rod withdrawals started.

The mode switch was placed in run at 1338 and the Turbo-gegeratoy,'synchronized to the system at 1510.

Continued rod withdrpijvjl,'4>to'pprox. 200 mwe.

At 1813, 5'13 feedwater pump was placed in service.

At 1823, high vibration was experienced in the feedwater system.

At 1830, bl3 feedwater pump was removed from service.

Investigation showed a sheared pin on the control cylinder snubber of the south flow control valve of 5'13 feedwater pump.

Repairs were completed at 0500 and 813 feedwater pump was placed in service at 0620.

At 0630, vibration was again experienced in the feedwater system and 813 feedwater pump was removed from service at 0650.

Load was maintained at 240 mwe while maintenance inspected the north flow control valve.

It was found that the disc had separated from the stem.

Repairs continued for the remainder of the day.

Repairs to 813 feedwater pump's north flow control valve continued during the day.

Unit load at approx.

238 mwe and 775 mwt.

Jan.

25 Jan.

26 Completed repairs to the north flow control valve.

813 feedwater pump placed in service at 0615.

Continued to increase load during the day.

Unit load at 510 mwe and 1522 mwt.

Continued load increases within PCIOMR limits.

Jan.

27 Continued load increases to 590 mwe.

Maintaining load due to problems with condensate demineralizers dP.

At 1348 increased load to 603 mwe.

Jan.

28 Reduced load to 490 mwe to change a condensate demineralizer.

At 0500, load increased to 585 mwe.

Continued with load increases to 602 mwe.

Jan.

29 Reduced load to 500 mwe at 2241 to change a condensate demineralizer.

Jan.

30 Jan.

31 At 0144, started to increase load to 580 mwe.

Continued to increase load to 614 mwe.

Continued steady sta'te'peration at approx.

615 mwe.

RECEIVED OOCUNIIT CO!ITROI. GEST asaKt. 6 ru 9 >t U.S. P,RC GIST RIBUTIOH SERVICES BRANCH

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NINE NILE POINT NUCLEAR STATION UNIT ¹1 NARRATIVE OF OPERATING EXPERIENCE JANUARY 1978 Jan.

1 Jan.

2 Jan.

3 At 0000 after a control rod pattern

change, unit load was 1375 mwt,'45 mwe.

Unit load increased during the remainder of the day as PCIONR limits allowed.

Continued to increase load within PCIONR limits.

Continued to increase load via recirculation flow increases.

At 1450 unit 1'oad was 625 mwe.

At 2202 reduced load to approx.

485 mwe due to icing up of the lake water intake.

At 2305 increased load to 525 mwe following the flow re-versal.

Jan.

4 Jan.

5 Continued load increase to 560 mwe.

At 0505 reduced load to return circulating water flow to normal.

At 0535, the unit was returned to normal flow and load increased during the remainder of the day.

Continued to increase load.

At 1500 obtained maximum recirculation flow, unit at 625 mwe.

Jan.

6 - Jan.

12 Continued steady state operation at approx.

625 mwe, 1840 mwt.

Jan.

13 Jan.

14 Load was reduced at 2205 to adjust rod pattern.

Unit load approx.

515 mwe, 1515 mwt.

Had problems with the TIP machines held load at approx.

1569 mwt.

At 0610 started to increase load as PCIOMR limits allowed.

Jan.

15 Jan.

16 - Jan.

Jan.

20 Jan.

21 Unit load at approx.

1785 mwt, 608 mwe.

Continued load increases during the remainder of the day.

19 Continued steady state operation at 1830 mwt and 624 mwe.

Unit load was 1828 mwt and 624 mwe.

At 1000 reactor level control became erratic.

At 1035 started to reduce load due to a malfunction of ¹13 feedwater pump flow control valves.

At 1058, the reactor was manually scrammed due to continuing rapid reactor water level oscellations.

Investigation showed a broken stem on ¹13 feedwater pump's south flow control valve.

(Also, some rods showed long scram response times.)

The rubber diaphrams on the scram pilot valves for ll CRD's were replaced.

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OPERATING DATAREPORT OPERATING STATUS

1. Unit Name Point Unit //1

2. Reporting Period: '1/01/78 01/31/78

3. Licensed Thermal Power (MIVt):

4. Nameplate Rating (Gross MWe):

5. Design Electrical Rating (Net MWe): 620

6. hlaximum Dependable Capacity (Gross MlVe):

.61a DOCKET NO.

DATE 22/73 COMPLETED IIY T.J. Perkins ext.1312 Notes 4

8. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reasons:

9. Power Level To which Restricted, IfAny (Nct hIWe):

10. Reasons For Restrictions, IfAny:

This Month Yr.-to-Date 744.0 Cumulative

'72 336.0

12. Number Of Hours Reactor Was Critical 709.7

13. Reactor Reserve Shutdown Hours 0

14. Hours Generator On-Line 691.8

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (hiIWH)

~~200

~ 0 392

18. Net Electrical Energy Generated (hIWH)

19. Unit Service Factor 93.0

20. Unit AvailabilityFactor 93.0

21. Unit Capacity Factor (Using MDC Net) 84.0

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 7.0

24. Shutdowns Scheduled Over Next 6 hlonths (Type, Date, and Duntion of Each):.

Ma 28 1978 Snubber Ins ection 709.7 0

691.8 51,778.6 1',204.0

-49,382.0 622. 0 93.0 93.0 84.0 82.0 7.0 25,356',545

~'0

68.0 70.0 5

57.0 11.0 620.0'9 612,480.0 900.0 26 174 612.0

25. IfShut Down At End Of Report Period, Estimated Date of Startup.

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

Forecast Achieved INITIAL CRITICALITY INITIALELECTRICITY COhlhIERCIAL OPERATION

('>/77 )

UNITSHUTDOWNS AND POWER REDUCTIONS REPORT MONTH JANUARY 1978 DOCKET NO 50-220 UNITNAMF Nine Mile Poin Unit fi'1 COMPLETED BY Date Cl 4 Z.

( I EA Cl L

o

~ CA Q

Licensee Event Report O

Eo 0

Cause &, Corrective Action to Prevent Recurrence 0

0 1

1/3/78 1/4/78 1/23/78 F

F

.45 52.2 35.7 H

A A

1 H

1 2

1 Intake Tunnel Ice Reverse Flow 485 MMe Intake To Normal 550 MWe 813 Feedwater Pump F.C.V. Failure.

Held Load At -"240 MWe To Repair

//13 Feedwater Pump FCV.

F: Forced S: Scheduled (9/77)

Reason:

A-Equipment Failure (Explain)

B-Maintenance oi Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

Method:

I-Manual 2-Manual Scram.

3-Automatic Scram.

4-Other (Explain)

Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-016l)

Exhibit I - Sante Source

UNITSHUTDOWNS ANDPOWER REDUCTIONS

~

~

INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition, it should be the source ofexplan-ation of significant dips in average power levels.

Each signi-ficant reduction in power level (greater than 20% reduction in average daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) should be noted, even though the unit may not have been shut down completelyl.

For such reductions in power level, the duration should be listed as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain.

The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction.

NUMBER.

This column should indicate the sequential num-ber assigned to each shutdown orsignificant reduction in power for that calendar year.

When a shutdown or significant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.

Until a unit has achieved its first power generation, no num-ber should be assigned to each entry.

DATE.

This column should indicate the date of the start of each shutdown or significant. power reduction..Report, as year, month, and day.

August 14, 1977 would be reported as 770814. 'When a shutdown or significant power reduction beginsin one report'period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.

TYPE.

Use "F" or "S" to indicate either "Forced" or "Sche-duled," respectively, for each shutdown or significant power reduction.

Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an off-normal condition.

It is recognized that some judg-ment is required in categorizing shutdowns in this way.

In

general, a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.

DURATION.

Self-explanatory.

When a shutdown extends beyond the end of a report period, count only the time to the end of the report period and pick up the ensuing down time in the following report periods.

Report duratibn of outages rounded to the nearest tenth ofan hour to facilitate summation.

The sum of the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting period.

REASON.

Categorize by letter designation in accordance with the table appearing on the report form. Ifcategory H must be used, supply brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INoie that this differs trom the Edison Electric Institute (EEI) definitions of "Forced Partial Outage" and "Sche-duled Partial Outage."

For these terms. EEI uses a <<hange of 30 MW as the break point:. For hrger-power reactors,'30 MW--

is ioo small a <<hange lo warrant explanation.

I' in accordance with the table appearing on the report form.

Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT REPORT

~~.

Reference the applicable reportable occurrence pertaining to the "outage or power reduction.

Enter the first four parts (event year,;sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of D'ata Entry Sheets for Licensee Event Report (LER) File (NUREG-0161).

This information may not be immediately evident for all,such shutdowris, of course; since further investigation may be required to ascertain whether or not a reportable occurrence was involved.)

If'the outage or power reduction will not result in a reportable occurrence, the positive indication of this lack of correlation should be noted as not applicable (N/A).

SYSTEM CODE.

The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G

~ Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.

I'OMPONENT CODE.

Select the most appropriate component from Exhibit I - Instructions for Preparation of Data'ntry Sheets for Licensee Event Report (LER) File (NUREQ4161),

using the followingcritieria:

A. Ifa component failed, use the component directly involved.

B. If not a component failure, use the related component:

e.g., wrong valve operated through error; list valve as component.

C. If a chain of failures occurs,"'he first component to mal ~

function should be listed. The sequence ofevents, includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence column.

Components that do not fit any existing code should be de-signated XXXXXX. The code ZZZZZZ should be used for events where a

component designation is not applicable.

CAUSE k, CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use the column in"'a narrative fashion to amplify or explain the circumstances of the shutdown orpower reduction.

The column should include the specifik cause for each shut-down or significant power reduction and the immediate and contemplated long term corrective action taken, ifappropri-ate.

This column should also be used for a description of the major safety-related corrective maintenance performed during the outage or power reduction including'an identification of the critical path activity and a report of any single release of radioactivity. or single radiation exposure specifically associ-ated with the outage which accounts for more than 10 percent of the allowable annual values.

For long textual reports continue narrative on separate paper and refererice 'tlie shutdown or power redu<<iion for this liarfatlve.

(9/77'

NTAGABA ~~f lL'LMK PoiiE[l COBPOIQLTXO'I AVEIMGL AIL'j+If PQ)~/f ft JPVLf Ui%IT DAfE 8

. PLC fDIIYI TQLQPHPq<<E (315) 343-2110 ext.1312 DAY AVEP~rkGE DAILYPO)VHP~ LEVEL (6 Ice-i%et) 471 DAY AVERA.GEDAILYPOV~FiR LrVEL PDVe-Net)

,611 553 584 608 608 ae 20 610 610 607 192 l3 609 609 608 551 609 23 24 20 27 28 30 3j 218 346 537 573 582