ML20210L041

Monthly Operating Repts for July 1997 for CNS

ML20210L041
Person / Time
Site:	Catawba
Issue date:	07/31/1997
From:	Dimmery T, Robert Williams DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9708200196
Download: ML20210L041 (13)

Text

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. Duke Power Company A irk twp umpy se lhttry Cernte, Af*kievGa#* l'O. Ikix i006 Charlotte, NC 23201 1006 August 15, 1997 U.S Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

Subject:

Catawba Nuclear Station Docket No. 50-413 and -414

Dear Sir:

Please find attached information concerning the performance and operation status of the Catawba Nuclear Station for the month of July, 1997.

Any questions or comments may be directed to Roger A. Williams at  ;

(704) 382-5346.

Sin erely,

/ i D N err imm+.r anager Nuclear Business Support Attachment  !

L. A. Reyes, Regional Administrator USNRC, Region II p .

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Peter Tam, Project Manager USNRC, ONRR /'

f INPO Records Center

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Ms. Margaret Aucoin Nuclear Assurance Corporation Dottie Sherman, ANI Library American Nuclear Insurers R. J. Freudenberger, Senior Resident Inspector 9708200196 970731 PDR ADOCK 05000413 R PDR 200003 lllli,l!lIIjll14l,$lllll

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i Document Control Desk U.S. NRC - Catawba

-bxc:

J. M. Davis (ON01VP)

K. S. Canady-(EC08H)

T. E. Mooney (EC090) ,

D. J. Horsley (EC12T)

T. E. Hunter (ON0102)

C. N. Green (MG010P)

B. W. Walsh (EC11C)

Jeanette Meares (CN020P)

.G..A. Copp (EC050)

D. R. Groux (ON01VP) l B. T._ Faulkenberry (EC07C)

M. .J.-Johnson (PB02L)

D. A..Harton (EC05P)

! G. R. Peterson (CN01SM) l J. S. Forbes (CN01EG)

E.-G. LaCasse (CN01BM)

M. S. = Kitlan (CN01RC) '

S. F. Hatley (CNO3MC) l J. J. Fisicaro (EC070) l 1

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l

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

b OPERATING DATA REPORT

~

DOCKETlt0 415 DATE Aueust 15. 1997

Egitilt5 SMiih -COMPLETEDB1 R.A. Willines TELEPHONE 704-3B2-5346 l

- 1. Valt liane: Catasha 11-

2. Reporr.ng Period: July 1,1997-July 31,1997

>3. Licensed Thereal Power (MWti 3411 __.

4. Nasepleta Rating (Gross lik):- 1305e Notes e h eeplate Rating

5. Detagn R strical Rating (Nel !IWel .

!!45 (Bresslllelcalculatedas i 6c Muleue Dependable Capacity-(Bross IIWel  !!92 lt.50.000 MVA .90 power -

17. Mulous hpendable Capacity (Net IIWels-  !!29 factor per Page ill,-

g

'8. If Changes Occur in Capacity Ratings (!!ees llueber 3 through 71 Since Last lluREG-0020. -. p

--R: pert. Give Reasons: -

l: 9. Power Level it, lihich Restricted, if Any (Net MWel 10.ReasonForRestrictions,ifany:-

ThisMonth Yr.-to-Date Cueulative

11. Hours in Repor;tng Period :744.0 5067.0- ,105984.0 g

12.- Ikeber Of Hours Reactor Was Critical- 744.0 5087.0- 183320.8

}' -13. Reactor Resene Shutdoun Hours

--0-- - -  :

--14. Hours Generator On-Line Di.0 5007.0 81984,8-

!!.. Unit Reserve Shutdown Hours - - .--0-- --0--

.16. Sress Thereal Energy.6enerated (INiH) 2533210 -17347010 268070471+

17. Gross Electrical Energy Generated (flWH) 897087 :6204426 94823832

18. liet Electrical Energy Generated (llWH1 851134 ~ 5890821- l89244187

=19. Unit Service Factor: 100.0 -100.0 77.4

-20.'UnitAvailabilityfactor. .

100.0 100.0' -77.4

= 21. Unit Capacify Factor. fusing MDC Net 1 101.3 102.6.- 74.4

-22.UnitCapacityFactor(UsingDERNet) 99.9 101.1 L73.5 1 23. Unit Forced Outage Rate; -

0.0 0.0 7.5

24. Shutdown Scheduled Over Next 6 Months (Type, Date, and D: ration of Each):

kefueline '- November 29. 1997'- 38 days -

g

25. If Shut Nun At End Of Report Perloo. Estinated Piti of Startup:

26.Unitsh.TestStatus(FriortoConsercialOperationi Forecast- Achieved INITIALCRITICAlliY INITIALELECTRICliY COMilERCIAL OPERAi!0N g

,

CPERATING DATA REPORT D0CKET ND 50-413 UNIT Eatawba 1 DATE Accust 15. 1997 COMPLETED B) R.A. Willises h

TELEPHONE 704-382-5346 MONTH July 1997 4

1 Q!Al AVERASE DA!LY POWER LEVEL Q11 AVERAGE DAILY POWER LEVEL 4

(MWe-Nett (MWe-Ret) ,

!- 1145 17 1147 2 1145 19 1146 3 1144 19 1144 4 1140 20 IM2

$ 1146 21  !!42 6 1148 _ 22  !!41 7 1140 23 1141 8 1149 24  !!40 9 1148 25 1142 10 .. 1146 26  !!41

!!  !!40 27 1136 12 1151 28 1135 13 1140 -

29 1141 14 1144 30 1147

, 15  !!44 31 1134 16 _.  !!45

_ . . . _a

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-413 -

UN7.T NAME carantsa 1 DATE v6/1d/y/

• REPORT MONTH July 1937 COMPLETED BY x. a.. williams-TELEPHONE (sus)-362-d346 (1) (2) (3) (4) (5)

R MET- .

E HOD T. A OF LICENSE

, Y S SHUT EVENT SYS- CAUSS AND COFRECTIVE O P DURATION O DOWN REPORT TEM COMPONENT ACTION TO

~

. DATE E HOURS N R/?; NO. CODE CGDE PREVENT RECURRENCE 1 NO SHUTDOWNS OR REDUCTION S 4

I (1) (2) (3) (4)

F Forced Reason- Method: Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or test 2-Manual Scram Ent w Sneets For Licensee Event Report (LER C-Refueling 3-Automatic Scram D-Rec,ulatory Restriction 4-Other (Explain) File (NrJREG-0161) )

E- Merator Training & License Examination F-Administrative (5)

G-Operator Error Exhibit I - Same Source H-Other (Explain) (Explain)

4

, MONT111,Y REFUELING INFORMATION REOUEST

1. Facility name: Catawba. Unit 1 -

2. Scheduled next refueling shutdown: November 1997

3. Scheduled restart following tefueling: January 1998 Tile PROJECT MANAGER llAS BEEN ADVISED BY SEPARATE COMMUNICATION OF

- ANY T.S. CilANGE OR LICENSE AMENDMENT. TilEREFORE, QUESTIONS 4 TliROUGil 6 WILL NO LONGER DE MAINTAINED IN Tills REPORT.

l 4. Will refueling or resumption of operation thereafter require a technical specincation change or other license amendment?

If yes, what will these be?

l If no, has reload design and core con 0guration been reviewed by Safety Review Committee regarding unresiewed safety questions?

5. Scheduled date(c) for submitting proposed licensing action and supporting information.

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

7. Number of Fuel assemblics (a) in the core: 19),

(b) in the spent fuel pool: f)31

8. Present licensed fuel pool capacity: 1418 Size of requested or planned increase: =

9. Projected date oflast refueling which can be accommodated by present license capacity:

November 2009 DUKE POWER COMPANY DATE: Aucust 15.1997 Name of

Contact:

R. A. Williams Phone: (7W)- 382-5346 l

l

DOCKET: 50-413  ;

i UNIT: Catawba 1 l

Date: 08/15/97 NARRATIVE

SUMMARY

l MONTil: July,1997 Catawba Unit 1 began the month of July operating at 100% full power. The unit operated at or near 100%

full power for the entire month.

Prepared by: R. A, Williams Telephone: (704)-382 5346

, 0FERAi!NSDATAREPORT DOCKET ND 50-414 DATE Auoust 15. 1997 OPERATING STATUS C0ftPLETED BY R. M illians TELEPHONE 704-302-5346

1. Unit Names Catasha 2 2.ReportingPeriod: July 1,1997-July 31,1997

3. Licensed Theraal Power (MWtli 3411

6. Kaseplate Rating (6tess MWe): 13055 Notes # Nameplate Rating

5. Design Electrical Rating (Net MWe): 1145 (6tess MWel calculated as

6. Marious Dependable Capacity (6ross MWe): 1192 1450.000 MVA .90 power

7. Manteus Dependable Capacity (Net MWel  !!H -factor per Page 111, B. If Changes Occur in Capacity Ratings (Itess Nueber 3 Through 71 Since Last NURES-0020.

Report. Give Reasons:

9. tower Level To Which Restricted, If Any (het MWe):

16. Reason For Restrictions, if any This Month Yr.-to-Date Cuaulative

11. Hours la Reporting Period 744.0 5087.0 96000.0

12. Number Of Hours Reactor Was Critical 714.7 4045.0 76414.1

13. Reactor Reserve Sheldren Hoars --0-- --0-- --0--

14. Hours Generator On-Line 708.8 3997.3 75243.5

15. Unit Reserve Shutdown Hours - - --0--

16, 6ress Thernal Energy Generated (MWH1 2279928 12989150 243701226

17. Gross Electrical Energy Generated (MWH) 836135 4673086 86522519

18. CJt Electrical Eriergy Benerated (MWH 791308 4415671 81561563

19. Unit Service Factor 95.3 78.6 78.4

20. Unit Availability Factor 95.3 78.6 '78.4

21. Unit Capacity Factor (Using MDC Net) 94.2 76.9 75.1

22. Unit Capacity Factor (Using DER Net) 92,9 75.8 74.2

23. Unit Forced Dutage Rate 4,7 g,7 g,g

24. Shutdown Scheduled Over Nsxt 6 Months (Type, Date, and Duration of Each):

None

25. If Shut Down At Er.d Of Report Feriod. Estinated Date of Startop:

24. Units la Test Status (Prior to Coseercial Cperation): Forecast Achieved INITIAL CRITICALITY IN!ilAL ELECTRICITY -

C0!2ERCIAL OPERATION

. _ _ .. .. . .. .. _ l

OPERATIMS DATA REPORT DOCKET N3 50-414 UNIT Catauba2 DATE Auoust 15. 1997 COMPLETED Bf R.A. Willines TELEPHONE 704-382-5346 I

MJNTH July, 1997 l

[R AVERAGE DAILY F0WER LEVEL EH AVERAGE DAILY POWER LEVEL (MWe Nat) (MWe-Net) l t

1-  !!40 17 1144 2 1100 18 1t52 3 980 19 -!!50 6 1151 20 1148 5 1153 21 1146 6 1155 22 1146 7 1155 23 1150 8 1153 24 1118 9 !150 25 1122 10  !!51 26 1069

!!  !!55 27 0 12  !!56 28 142 13 1153 29 1068 14  !!50 30 1151 13 118'd 31 1132 16 1125

T7 NIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-414 '.

UNIT NAME. urnwen 2 DATE ud/1d/y/

REPORT MONTH July 1997 COMPLETED BY x. a..W1111ama TELEPHONE tfus)-se2-d346 (1) (2) (3) (4) (5)

R MET- -

E HOD T A OF LICENSE N Y S SHUT EVENT SYS- CAUSE AND CORRECTI'1E i O P DURATION O DOWN REPORI TEM COMPONENT ACTION TO l

. DATE E HOURS N R/X NO. CODE CODM PREVENT RECURRENCE i 11-P 97 2 F --

A --

HA CKTBKR LO POLE PRESSURE ON "2B" MAIN GENERATOR BREAKER 4 97- 7-26 'F 35.20 A 1 CH VALVEX STEAM GENERATOR "2D" MAIN STEAM ISOLATION VALVE l

(1) (2) (3) (4)

F Forced Reason- Method: Exhibit G - Instructions S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of, Data B-Maintenance or test 2-Manual Scram Ent U Sheets For Licensee C-Refueling 3-Automatic Scram Event Report (LER D-Regulatory Res?riction , ,

4-Other (Explain) File (NUREG-0161))

E-@ era $or Training & License Examination F-Administrative (5)

G-Operator Error (Explain) Exhibit I - Same Source H-Other (Explain)

MONTHLY REFUELING INFORM ATION RFOUEST

1. Facility name: Catawba. Unit 2

2. Scheduled next refueling shutdown: September 1998

3. Scheduled restart following refueling: November 1998 Tile PROJECT MANAGER llAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S. CilANGE OR LICENSE AMENDMENT. TilEREFORE, QUESTIONS 4 TilROUGli 6 WILL NO LONGER BE MAINTAINED IN Tills REPORT.

4. Will refueling or resumption of operation thereafter require a techuical specification change or other license amendment?

If yes, what will these be?

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

l

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

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

f 7. Number of Fuel assemblies (a) in the core: 191 1

(b) in the spent fuel pool: 600

8. Present licensed fuel pool capacity: 1418 Size of requested or planned increase: =

9. Projected date oflast refueling which can be accommodated by present license capacity:

Mav 2012 DUKE POWER COMPANY DATE: Aucust 15.1997 Name of

Contact:

R. A. Williams = Phone: (7041- 382-5346

a DOCKET: 50-414 UNIT: Catawba 2 Date: 08/15/97 NARRATIVE

SUMMARY

MONTil: July,1997 Catawba Unit 2 began the month of July operating at 100% full power. On 07/02/97at 2127 the unit began decreasmg power and held at 50% power from 07/02/97 at 2229 to 07/03/97 at 0310 due to lo pole pressure on "2B" main generator breaker, ne unit returned to 100% full power on 07/03/97 at 1300 and operated at or near 100*/. full power until 07/26/97 at 2223 when the reactor was manually tripped due to spurious closure of steam generator "2D" main steam isolation valve caused by optical isolator failure.

The unit was placed on-line 07/28/97 at 0935 He unit returned to 100% full power ori 07/29/97 at 1125 and operated at or near 100% full power the remainder of the month.

- Prepared by: R. A. Williams Telephone: (704)- 382 5346 '-

r

,.s.. . . _. ,.

4 -

CATAWBA NUCLEAR STATION

' MONTHLY OPERATING STATUS REPORT June 1997-i

1. - Personnel = E::posure -

The total station liquid reler.se for June has been compared-with the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

The total station gaseous release for June has been compared with:the Technical Specifications maximum annual dose commitment and was less than 10 percent of this limit.

l-

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