ML20087G416

Monthly Operating Repts for Feb 1984

ML20087G416
Person / Time
Site:	Oconee
Issue date:	02/29/1984
From:	Reavis J, Tucker H DUKE POWER CO.
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8403200010
Download: ML20087G416 (17)

Text

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OPERATING DATA REPORT DOCKET NO. 50-269

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DATE 113-15-84 CO31PLETED BY J.

A.

Reavis TELEPHONE 704-373-7567 OPERATING STATUS

1. Unit Name:

Oconee No. 1 Notes

2. Reporting Period: February 1, 1984 - February 29, 1984 Year-to-date and cumulative capacity factors are calcu-

3. Licensed Thermal Power OlFr):

2568 lated using a weighted

4. Nameplate Rating (Gross 3!We s:

934 average tor maximum

5. Design Electrical Rating (Net Stwe):

886

6. Staximum Dependable Capacity (Gross 31Wep:

800

7. 3taximum Dependable Capacity (Net StWe):

860

3. If Changes Occur in Capacity Raiings litems Number 3 Through 7) Sin:e Last Report. Give Reasons:

None None

9. Power Level To Which Restricted. If Any INet alwe):

10. Reasons For Restrictions. If Any:

This Stonth Yr..to.Date Cumulative

11. Hours In Reporting Period 696.0 1 440.0 93 145.0

12. Number Of Hours Reactor Was Critical 696.0 1 440.0 65 980.6

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 696.0 1 440.0 62 829.4

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 1 787 819 3 696 857 149 991 889 17 Gross Electrical Energy Generated (StWH) 62G 220..

1 297 480 52 165 710

's.. Net Electrical Energy Generated (MivH) m9 R2R 1 242 415 49 407 966

19. Umt Service Factor 100 n 100.0 67.5

20. Unit Availability Factor 100.0 100.0 67.5

21. Unit Capacity Factor iUsing SIDC Neti 100.2 100.3 61.5

22. Unit Capacity Factor Using DER Net) 07 9 97.4 59.9

23. Unit Forced Outage Rate 0.0 0.0 17.2

24. Shutdowns Scheduled Over Next 6 Stonths (Type. Date.and Duration of Eachi:

None

25. If Shut Down At End Of Report Period. Estiranted Date of ',:artup:

26. Units in Test Status tPrior to Commercial Operations:

Forecast Achieved.

lNITIAL CRITICALITY INITIAL ELECTRICITY CO315tERCIA L OPER A TION 8403200010 840229 PDR ADOCK 05000269 R

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AVER.tGE D AILY UNIT ?OhER LEVEL 50-269 DCCKIT NO.

Oconee 1

. 3;7 DATE 03-15-84 CONtPLE3D SY J. A. Reavis

- TELEPHONE 704-373-7567 MONTy February 1984 DAY AVERAGE DAILY ?OWER LEVEL DAY AVERAGE DAILY POWER 'IVEL i

(5the-Net) 13the Ner)

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865 19 866 4

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50-269 UNIT NAnf E Oconee 1 l> ATE 3/15/84 R EPORT MONTil February,l984 COMPLETED HY.J.A. Reavis TEl.EPIIONE 704-373-7567 l

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B CC VALVEX PERIODIC TESTS (PT's) - 00NIBOL VALVE AND SIOP VALVE.

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Exhibit C-Instructions S: ' Schetf ulet!

A Etinipinent Failure (Explain) 1 Manual l'or Picparation of D na i

11-Maintenance or Test 2 M snual Scrasn.

linary Sheets for 1.ieensee C. Refueling 1 Automatic Scram.

Event Report (l.ER) File INtlREG.

D Regulatory Restriction

-l Other (lixplain) 01b11

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DOCKET No:

50-269 tRi1T :

Oconee 1 D.tTE.

3/15/84 NAR?aTIVE Sb?0LARY Month: February,1984 Oconee Unit 1 operated at 100% for most of the period except for a dispatcher related reduction on February 13, and a slight re-duction on February 27 to perform control valve and stop valve testing. The unit had 165 days of continuous operation at the end of February.

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MONTHLY REFUELING INFORMATION REQUEST Oconee Unit 1 1.

Facility nama:

2.

Scheduled next refueling shutdown:

February, 1985 3.

Scheduled restart following reft ' ling:

April, 1985 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

Yes If yes, what will these be?

Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

N/A 5.

Scheduled date(s).for submitting proposed licensing action and supporting information:

N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

7.

Number of fuel assemblies (a) in the core:

177 (b) in the spent fuel pool:

1123*

8.

Present licensed fuel pool capacity:

1312 Size of requested or planned increase:

i 9.

Projected date of last refueling which can be accommodated by present licensed capacity.

1 DUKE POWER COMPANY Date:

March 15, 1984 Name of

Contact:

J. A. Reavis Phone: 704-373-7567 i

• Represents the combined total for units 1 and 2.

OPERATING DATA REPORT 1

DOCKET NO.

50-270 DATE 03-15-84 COSIPLETED BY J.

A. Reavis TELEPHONE 704-373-7567 OPERATING STATUS

1. Unit Name:

Oconee No. 2 NOI'5

2. Reporting Period: February 1, 1984-February 29, 1984 Year-to-date and cu:::ulative capacity factors are calcu-

3. Licensed Thermal Power QtWt):

2568 lated using a weighted

4. Nameplate Rating (Grou SIWes:

934 m g e for d e S. Design Electrical Rating (Nec StWe):

886 dependable capacity.

6. Sta.ximum Dependable Capacity (Gross StWe):

800

7. Staximurn Dependable Capacity (Net StWe):

860 S. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Give Reasons:

None None

9. Power Level To Which Restricted. lf Any INet 31Wel:

10. Reasons For Restrictions. If Any:

This 31onth Yr..to.Date Cumulative

!!. Hours In Reporting ?ctiod 69G.0 1 440.0 83 065.0

12. Number Of Hours Reactor Was Critical 696.0 1 440.0 58 753.5

13. Reactor Reserve Shutdown Hours

14. Hours Generator On.Line 698.0 1 440.0 57 600.2

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (>tWH) 1 790 632 3 699 486 136 190 153 17 Gross Electrical Energy Generated (StWH)

A14 900.

1 279 m')

46 384 356

13. Ser Electrical Energy Generated (StWH) 594 378 _

1 227 665 44 039 234

19. Unit Service Factor 100.0 100.0 69.3

20. Unit Avadsbility Factor 100.0 100.0 69.3 l

21. Unit Capacity Factor iUsing SIDC Net) 99.3 99.1 61.5

22. Unit Capacity Factor (Using DER Net) on a 96.2 59.8-j

23. Uni Forced Outage Rate n.n n_n 16.1 l

24. Shutdowns Scheduled Over Next 6 3tonths (Type. Date.and Duration of Eacht:

l None l

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25. If Shut Down At End Of Report Period. Estimated Date of ~,tartup:

26. Units in Test Status IPrior to Commercial Operatical:

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C05tatERCIAL OPER ATION i

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AVERAGE D AILY UNIT ?CWER LEVEL DCCKET NO.

g;7 Oconee 2 D ATE 03-15-84 COMPLEHD BY J. A. Reavis c

TELIPHONE 704-373-7567 s

310 NTH February 1984 DAY AVERAGE DAILY ?OWER LIVEL DAY AVERAGE DAILY PCwER LIVEL (Mhe Net) 1.\\lhe-Net )

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t 854 8M 6

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s 854 10 856 25 854 11 856 855 12 856

3 854 4

13 856

9 854 14 856

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DOCF.ET 140:

50-270 UNIT:

Oconee 2 DATE:

3/15/84

!!ARRATIVE SU}01ARY Month:

February, 1984 Oconee Unit 2 operated throughout the month at 100% power except for one power reduction to perform turbine valve movement tests.

The unit had 81 days of continuous operation at the end of February.

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MONTHI.Y REFUELING INFORMATION REQUEST 1.

Facility name:

Oconee Unit 2 June, 1985 2.

Schedultd next refueling shutdown:

3.

Scheduled restart following refueling:

August, 1985 l

l 4.

Will refu.aling or resumption of operation thereaf ter require a technical Yes specification change or other license amendment?

If yes, what will these be?

Technical Specification Revision l

1 f

j If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

N/A i

5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

-?

4 7.

Number of fuel assemblies (a) in the core:

177 (b) in the spent fuel pool:

1123*

8.

Present licensed fuel pool capacity:

1312 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by present licensed capacity:

DUKE POWER COMPANY Date:

March 15, 1984 i

l Name of

Contact:

J. A. Reavis Phone:

704-373-7567

• Represents the combined total for Units 1 and 2.

1

OPERATING DATA REPORT DOCKET NO.

50-287 DATE 01-1s-R4 CO31PLETED BY J.

A. Reavis TELEPHONE 704-373-7567 OPERATING STATUS N0t*5 Oconee No. 3

1. Unit Name:

Year-to-date and cumulative February 1,1984-February 29, 1984

2. Reporting Period:

capacity factors are calcu-

3. Licensed Thermal Power (}lWt):

2568 lated using a weighted 934

4. Nameplate Rating (Gross alWei:

amp gwm 886 5., Design Electrical Rating (Net alWe):

dependable capacity.

899

6. Staximum Dependable Capacity (Gross 31We):

860

7. Staximum Dependable Capacity (Net StWe):

3. If Changes Occur in Capacity Ratings litems Number 3 Through 7) Since Last Report. Give Reasons:

None l

None

9. Power Level To Which Restricted. If Any (Net 31We):

10. Reasons Fcr Restrictions,if Any:

This. Month Yr. to Dare Cumulative G96.0 1 440.O' 80 712.0

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 691.9 1 438.9 58 148.7

13. Reactor Reserve Shutdown Heurs

14. Hours Generator On.Line 693.0 1 437.0 57 019.6

15. Unit Reserve Shutdown Hours 1 760 898 3 670 368 139 162 932

16. Gross Thermal Energy Genersted (SIWH) 17 Gross Electrical Energy Generated (StWH) 607 200 _,

1 267 370 48 081 9r,1 SR2 478 1 91R R4G as 7R9 ona lb. Net Electrical Energy Generated (StWH) 99.6 09.R 7n.7

19. Unit Service Factor 99.6 99.8 70.7

20. Unit Availability Factor 97 3 9R 2 GB.R

21. Unit Capacity Factor (Using 3tDC Nets 91.5 95.9 g.t o

22. Unit Capacity Factor (Using DER Net) 0.4 n.2

23. Unit Forced Ourage Rate 14.9

24. Shutdowns Scheduled Over Next 6 3tontlis IType. Date.and Duration of Eacht:

Refueling - Harch 8, 1984 - 10 Weeks i

25. If Shut Down At End Of Report Period. Estimated Date of ".,t:rtup:

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

Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COSINtERCIAL OPER ATION am- ;

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AVER.tGE D AILY UNIT PChER LEVEL 5

50-287 DCCKIT NO.

Oconee 3

.yg7 03-15-84 0 ATE COMPLE3D BY J. A. Reavis TELEPHONE 704-373-7567 310 NTH Fohrttary 1984 DAY AVERAGE DAILY POWER LIVEL DAY AVERAGE DAILY ?OWER '.EVEL 13the Nets i31We-Net:

853 g-84 7 2

Aso g3 848 3

852 g9 8 51 4

852

g 853 5

R51 853 6

849 n

853 7

849 853 3

3 849 24 853 9

849 23 gm 10 849 852 gi 841 853 g2 849 3

853 g-851

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.m g4 852 3o 853 3g 16 445

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50-287 UNIT NAh!E Oconee 3 c

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DATE 3/15/84 ItEPOttT MONTil February,1984 CO5fPLETED ny J.A. Reavis TELEPilONE 704-373-7567 l

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' INSTRU REACTOR COOLANT FLOW IDOP "A" FAILUIE 1

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Exhibit G - Lestrnetiiuts Si Sdicif ulet!

A Eilnipsaent failure (Explain) 14tanual for Pacparation of Data II-Maintenance of Test 24lannal Serain.

Entry Sheets for I.seensee C.Itefueling 3 Autoniatic Se:ain.

Eveni Iteport (I.Elli Fi!c INLilli:G-D.Itegulatory itest fielion

-1 Other (Explain) 0161)

I:-Ope 4ator Training & License !!xainination II Adtninistrative 5

g G.Opeiational lie ror (lisplain)

Exhibit I Sanie Sousee (9/77)

Il-Other (Explain) e e

l DOCKET NO: 50-287 m;IT: Oconee 3 3-15-84 DATE:

NARRATIVE SUFC!ARY Month:

February,1984 Oconee Unit 3 tripped off-line on February 16, af ter completing 125 days of continuous operation. A reactor coolant flow trans-mitter failed low causing decreased feedwater flow which tripped the reactor on over pressere. The unit operated the remainder of the month at 100% power with no major problem.

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MONi*HLY REFUELING INFORMATI*N REQUEST 1.

Facility name:

Oconee Unit 3 2.

Scheduled next refueling shutdown:

March 8, 1984 3.

Scheduled restart following refueling; May 18, 1984 4.

Will refueling or resumption of operation thereafter require a technical YC8 specification change or other license amendment?

If y4s, what will these be?

Technical Specification Revision If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions?

N/A 5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

N/A 6.

Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).

7.

Number of fuel assemblies (a) in the core:

177 (b) in the spant fuel pool:

0 8.

Present licensed fuel pool capacity:

82s Size of requected or planned increase:

9.

Projected date of last refueling which can be accommodated by present Itcensed capacity:

March 15, 1984 DUKE POWER COMPANY Date:

Name of

Contact:

J. A. Reavis Phone: 704-373-7567

OCONEE NUCLEAR STATION Operating Status Report 1.

Personnel ExpoGure For the month of January, 1 individual exceeded 10 percent of their allowable annual radiation dose limit with the highest dose being 1.460 rem, which represents approxi-mately 12.2% of that person's allowable annual limit.

2.

The total station liquid release for January has been compared with the Technical Specifications annual value of 15 curies; the total release for January was less than 10 percent of this limit.

The total station gaseous release for January has been compared with the derived Technical Specifications annual value of 15,000 curies; the total release for January was less than 10 percent of this limit.

DUKE POWER GOMPANY P.O. Isox G3180 CIIAHLOTrE, N.n. 28242 liAI. H. TUCKEN TELEPHONE March 15, 1984 (ro4) ara-4mi 344.1845reeaDetTIO4

/

[ Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk Re: Oconee Nuclear Station Docket Nos. 50-269, -270, -287

Dear Sir:

Please find attached information concerning the performance and operating status of the Oconee Nuclear Station for the month of February 1984.

Very truly yours,

ts n ~,,A,,,

Hal B. Tucker JAR:scs Attachments cc: Regional Administrator Mr. J. F. Suermann, Project Manager U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Region II U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Washington, D. C.

20555 Atlanta, Georgia 30303 Mr. Phil Ross INPO Records Center U. S. Nuclear Regulatory Commission Suite 1500 MNBB-5715 1100 Circle 75 Parkway Washington, D. C.

20555 Atlanta, Georgia 30339 Senior Resident Inspector Oconce Nuclear Station g 6-1Y 1ll

.