ML17037B596

Letter Regarding Enclosed Report of Operating Statistics and Shutdown Experience for February 1978 and Refueling Information Request

ML17037B596
Person / Time
Site:	Nine Mile Point
Issue date:	03/07/1978
From:	Lempges T, Schneider R Niagara Mohawk Power Corp
To:	Office of Nuclear Reactor Regulation
References
Download: ML17037B596 (16)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-220 REC:

NRC ORG:

LEMPGES T E NIAGARA MOHAWK PWR DOCDATE: 03/07/78 DATE RCVD: 03/13/78 DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

REPORT OF OPERATING STATISTICS AND SHUTDOWN EXPERIENCE FOR THE MONTH OF FEBRUARY 1978.

PLANT NAME: NINE MILE PT UNIT 1

REVIEWER INITIAL:

XRS DISTRIBUTOR INITIAL: 0@I DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS MONTHLY OPERATING REPORT FOR GRAY BOOK PREPARATION.

(DISTRIBUTION CODE A003)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR CHIEF ~

4+W/2 ENCL P

MI R ACTION+4IJ/2 ENCL LPDR S OSWEGO NY++W/ENCL TICI~~W/ENCL NSIC~~~W/ENCL BNL< NATLAB)~~~I J/ENCL ACRS CAT 8++W/0 ENCL NRC PDR++W/ENCL DISTRIBUTION:

LTR 10 ENCL 10 SIZE:

iP+hP THE END CONTR NBR:

780740159

, 0 11 tH I f

((Hl()Nt()III6K((HK.E (loPI NMP-01gg Ma/hach 7, 1978 NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (3IG) 474.ISI I OMecto/L 0$ (Lce o) Management ln(otuII~on and P/Log/Lam Cont1LOL United S~ee NucLea/L ReguLato/Ly CommQ amn Ncukingkon, '0.C.

20555 RE:

Socket No.

50-220 PPR-b9 qfifP~.

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Cy GentLemen:

Submitted he/LeuLth ~ Che RepoM o( Ope/~ng S~WM and Sh&-

doRIn Expetu.ence tIo/L FebtuIa/Ly 1978 Jo/L She N~e hkLe Pok< NucLeaIL

~on Ui~ <l.

ALeo ~cLuded m a n~at~ve /LepoM o) opetuLt~g expel.ence (o/L She month.

ALeo, pLeaee

)hand encLoaed Re(ueDng Info/onation Requu.t, Ivtu'.ch eMt be. dub~ed ae p~ o( Che monthLy /LepoM.

Ve/Ly~g youhA, 1

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T.E.

empg u GeneJmL Supe/u,1Ltendmt NucL~. Genercatian FOR R.R. Schn~e/L V~ce Pcukfent-ELe~c P/I.oductLon EncLoau/Lu xc:

Mtcecto/L, 0(pce o] 78E (10 cop~u)

NRC Regin l OII(me (1 copy)

AVERAGE DAILYUNITPOWER LEVEL DOCKET NO.

9 Nile Pt.

DATE COMPLETED IIY T

J Perkins February 1978 DAY AVERAGEDAILYPOWER LEVEL (hfWe-Net) 598 DAY AVERAGE DAILYPOWER LEVEL (h1We-Net)

608 17 10 12 13 14 15 16 599 564 594 593 161 552 584 604 607 605 604 606 18 19 20 21 22 23 24 25 26 27 28 29 30 31 609 610 610 610 609 609 610 591 609 607 608 INSTRUCTIONS On this format, list the avcragc daily unit power level in h1~Ve.Net for each day in thc reporting month. Compute to the nearest whole megawatt.

(9/77)

~'

UNITSIIU I'I)O'lV)(S AND PO>VEI(, REDUCTIONS I)OCI'Er NO.

s I)AI F.

nit 81 BEUIIKJ978 ext.1312 Xo.

l)J!e col I

C/)

Liccnscc Evcnl Rcport

(.ause B. ('))rrcctivc Aclli)n li)

Pfcvcf)I Rci:1) frc)1cc 0

0 2/3/78 2/6/78 2/25/78 S

20.5 4.4 Reduced load to change condensate demineralizers.

Trying to latch up T.S.V. Bypass Valve.

All T.S.V.s closed causing turbine trip and reactor'cram.

Reduced load to change condensate demineralizers.

I.: I'i)feed S: Sehed<<lcil Rcison:

A-I'Jluipn)cnt Fail<<rc (Explain) 13.M:)if)tcf):)ncc or fest

( Rcl'ucling D-Rcgulati)ry Restriction li-OperJlof TfJining k. Liccnsc Fxafninalion F-Adfninistrativc G-Oper:) lional Err))r (I'.xplain)

I I.Other (Explain) 3

)iicthod:

! -hlaf)ual 2).hlanual Scrafn.

3 Auton1Jtlc Si;ran1.

4-Other (Explain)

I Exhibit G ~ Instructions fl)r PfcpllfJlliln i)l D:It:I Entry Sheets lor I.icensee Event Rcport (LL'R) I'ile (NUREG-OI 6 I )

Exhibit I - San)e Source

OPERATING DATAREPORT DOCKET NO 50-220 DATE COIIPLETEI) IIY ~J.

Perkins 'P TELEPI IONE ~~110 OPERATING STATUS I. Unit Name:

Reporting Period.

02-01-7 8 02-28-7 8

3. Licensed Thermal Popover ())I')Vt):

4. Nameplate Rating (Gross I)fWc):

640

5. Design Electrical Rating (Net MIVc):

6. Maximum Dependable Capacity (Gross f)flVe):

7. Maximum Dependable Capacity (Nct I)IIVe):

630 610 Notes

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

9. Power Level To h'hich Restricted, IfAny (Nct )IIIVe):

10. Reasons For Restrictions, IfAny:

This I)!Ollth Yr.-to.Date

,367.1 343.3

,886 867 185 95 98 87

11. Hours In Reporting Period 672 1

12. Number Of Hours Reactor Was Critical 657.4

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 1

15. Unit Reserve Shutdown Hours 16. Gross Thermal Energy Generated (MNH)

~iERS I.

18. Net Electrical Energy Generated (i)INH)

19. Unit Service Factor 98

20. Unit AvailabilityFactor

22. Unit Capacity Factor (Using DER Nct)

23. Unit Forced Outage Rate 3

24. Shutdowns Scheduled Over Next 6 ilfonths (Type. Date. and Duration of E:)ch):

24 A ril 1978 Snubber Inspection Ctlnlulat)ve 73,008 52,436.0 50,033.5

20. 2 80,781,895 26 573 579 25,742,108 69 58 57

25. IfShut Down Af End Of Rcport Period, Estimated Date of Startup:

26. Units ln Test Status (I'riorto Co)n)ncrcial Oper;)tion):

Force;)st Achieved likfITIAL CRITICALITY liiiITIAL ELECTRICITY CORDI ERCIAI.Ol'ERATION'))/77 I

L

NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT ¹1 NARRATIVE OPERATING REPORT FEBRUARY 1978 The Station operated at 98/ availability and 94% capacity factor for the month.

The daily operating history follows:

Feb.

1-Feb.

4 Feb.

5 Feb.

6 Feb.

7 Feb.

8 Feb.

9 Feb.

10-Feb.

24 Fe.b.

25 Feb.

26-Feb.

28 Operated at 97.5/ thermal power 615 MWe.

Reduced load to 500 MWe for condensate demineralizer resin change and control rod pattern adjustment.

Load increased to 608 MWe, pre-conditioning power level increases after rod pattern adjustment.

Full load reached at 0500 623 MWe.

At 2230, a reactor scram occurred while attempting to relatch ¹13 TSV Bypass valve mechanism.

Failure of a pneumatic operated valve caused all stop valves to shut.

Reactor critical at 1400 and unit synchronized to the line at 1900.

Continued load increases to reach 500 MWe.

Held at this level unti 1 2100 for Xe production; reduced load via recirc flow to 400 MWe for rod withdrawals to obtain 100% control rod pattern.

Continued load increases to 600 MWe by 2200.

Operated continuously at approximately 1840 MWth 623 MWe.

Reduced load to 500 MWe for change of condensate demineralizer.

Load returned to 623 MWe after 6th condensate demineralizer was placed in service.

Steady state power operation at approximately-99/.

REFUELING INFORMATION REQUEST 1.

Name of Facility Nine Mile Point Unit 81 2.

Scheduled Date for Next Refueling Shutdown The next refueling at Nine Mile Point Unit 81 is tentatively scheduled for the Spring of 1979.

However, evaluations to be performed during the Spring of 1978 may reveal a Fall 1978 refueling to be more desirable.

If a Fall 1978 refueling is

utilized, a September 2,

1978 shutdown date is assumed.

3.

Scheduled Date for Restart Following Refueling The refueling outage is scheduled to take approximately eight weeks.

4.

Will refueling or resumption of operation thereafter require a

Technical Specification change or other license amendment?

If answer is yes, what, in general will these be?

It is anticipated that prior to resumption of operation following the next refueling outage, a chnage will be required to the Nine Mile Point Unit tl Technical Specifications.

The next reload at Unit b'1 will.contain redesigned fuel assemblies which will be incorporated into the Technical Specifications (i.e. fuel thermal limits).

5.

Schedule Date(s) for submitting proposed licensing action and supporting information.

In anticipation of a Fall 1978 refuleing, Niagara Mohawk is scheduled to submit a reload licensing document to NRC around June 1, 1978.

Should the cycle be extended to the Spring 1979

period, Niagara Mohawk is scheduled to submit a reload licensing document to NRC around November 15, 1978.

6.

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.

The next reload at Nine Mile Point 81 will contain redesigned fuel assemblies as summarized in General Electric's Generic Reload Fuel Application Licensing Topical Report NEDE 24011-P Revision 2.

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

The Nine Mile Point Unit Pl core contains 532 fuel assemblies, The spent fuel pool contains 660 fuel assemblies.

rk

Page 2

8.

The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or planned in number of fuel assemblies.

The Nine Nile Point Unit ¹1 spent fuel pool is licensed to contain 1,984 fuel assemblies.

9.

The projected date of the last refueling that can be discharged to the present fuel pool assuming the present licensed capacity.

Under normal operating conditions, it is estimated the spent fuel pool can contain all fuel assemblies scheduled to be dis-charged from Unit ¹1 until approximately 1990.

C