ML20105B542

Monthly Operating Repts for Aug 1992 for McGuire Nuclear Station

ML20105B542
Person / Time
Site:	McGuire, Mcguire
Issue date:	08/31/1992
From:	Robert Williams DUKE POWER CO.
To:
Shared Package
ML20105B544	List: ML20105B542 ML20105B757 ML20105B758
References
NUDOCS 9209210016
Download: ML20105B542 (10)

Text

_ _

0FEF AllNS IAT A FEF0P1 D3Cf E1 NO..

50-369 DATE fellester 15.199[

Dr[RAILM STATUS CONFlf1ED BY _M31J1aeL 1ELEPHONE 704-3613346

1. Unit Nasei McGuire 1

2. Reporting Ferio c August 1, 1992-August 31,1992

3. Licensed lhereal Fever (MWt):

3411

4. Naseplate Rating (Gross MWelt 13058 Nates tNaseplate Fating

5. Ceugn Electrical Fating (Net Mile):

1180 (Bross MWe) talculated as

6. Marious Dependable Capacity (Firo n MWe):

1171 1450.000 MVA

.90 power

7. Marious Dependable Capacity (Net MWe):

1129 fatter per Fage lii,

8. If Changes Occur in Capacity Fatings (Itess husber 3 Through 7) Since Last N'JF E G-0020.

Report. Give Reasons:

9. Power level io Which Restricted, If Any '. Net Mwe): ___

10. Reason For Restrictions, if any:

This Month Yr.-to-Date Cuealative

11. Hours in Reporttvg Feriod 744.0 5855.0 94247.0

12. Nuster Of Hours Featter Was Critical 7%.0 3933.7 65927.2

13. Reactor Reserve Shutdown Hours -

--0--

~0-

14. Hours Generator On-Line 744.0 3912.6 65193.5

15. Unit Reserve (butdown Hours - - -

16. Sress Thereal Energy Generated (MWH) 2514974 12B(5322 199830983

17. Gross Electrical Energy Generated (NH) 839606 4408799 68760624

18. Net Electrical Enargy Generated (MWH) b06579 4208242 65639295

19. Unit Service Factor 100.0 66.8 69.2

20. Unit Availability Fatter 100.0 66.8 69.2

21. Unit Capacity Factor (Using MDC Net) 96.0 63.7 60.4

22. Unit Capatity Factor (Uu ng DER Net) 91.9 60.9 59.0

23. Unit Forced Outage Rate 0.0 33.2 14.1

24. Shutdown Scheduled Over Next 6 Months (Type, Datt, and Duration of iach):

.kne'

25. If Shut Down At End Of Report Feriod. Estteated Date of Startup:

26. t! nits in Test Status (Frier to Commercial Operation):

Frarecast Achie ed v

INITIAL CGlilCALITY th!!!AC ELECTRICITY COMMERCIAL OFE6All0N 9009210016 920915 PDR ADOCK 05000369 R

PDR 9

OPERAllNG [ATA GEF0;I DOCKET NO

$0-369 t! Nil McGuire 1 DATEEeetenber 15. 1992 COVtETED EV R.A. Willians TELEPHONE _ 104-39?-5346 MONTH Auws tul472 E

AVEFA5t DAILY F0WER LEVEL 041 AVERABE LAlLY POWER LEVEL (MWe-Net)

(Ne-Net) 1 1063 17 1029 2

1019 19 10,f) 3 1022 19 1097 4

1083 20 1093 5

1045 21 1071 6

1075 22 1089 7

1077 23 1096 8

1079 24 1093 9

106*

25 1094 10 ICES 26 1090 11 1991 27 1099 12 1086 28 1100 13 1086 29 1097 14 1096 30 1098 15 1092 31 1093 16 1088 a

'M m

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-369 UNIT NAME ncuuli<t 1 DATE I9/1d/ 92 l

REPORT MONTH August 1992 COMPLETED BY b.

c. 31MMuus TELEPHONE

( / us ) -3 62-4263 l

(1) 2)

(4)

(5)

E HOD T

A OF LICENSE N

Y S

SHUT EVENT SYS-CAUSE AND CORRECTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE NO SHUTDOWNS OR REDUCTION S

I I

l (3)

(4) l (1)

(2)

Method:

Exhibit G - Instructions F Forced Reason-l c Scheduled A-Equi ment Failure (Explain) 1-Manual for Preparation of, Data B-Main

(- 'nce or test 2-Manual Scram EntW Sheets For Licensee Event Report (LER (NUEG-Ol61) )

3-Automatic Scram C-Refuel _.sg 4-Other (Explain)

File D-Regulaton' Restriction E-Operator Training & License Examination (5)

F-Administrative Exhibit I - Sare Source G-Operator Error (Explain)

H-Other (Explain) i L-

I DOCLET NO:

50 369 UNIT: McGuire 1

'r

" A(. Pp/15/92 AT NARRATIVE

SUMMARY

MONTil: August 1992 McGuire Unit 1 began the month of August operating at 99.3% powet due c-to over power delta temperature problems. The unit started a power decrease on 8/1 at 2004, the unit held at 90% from 2126 to 8/2 1305 due to concerns of "A" feedwater condenser vacuum swings.

The unit returned to 99.5% power at 1626. The unit started a power decrease on 8/5 at 0330 and held at approximately 90% from 0423 to 0925 to stabilize vacuum on the "A"

feedwater pump turbine.

The unit was returned to 99.5% at.

1215. The unit starttJ a power decrease on 8/9 at 0828 and held at 97.5% power from 0908 to 1220 for reactor protection system testing.

The unit was returned to 99.5% power at 1301.

The unit started a power decre-e on 8/15 at 0815 and held at 97.5% from 0906 to 1352 for reactor protecmion system testing.

The unit was returned to 99.5% power at 1454. The unit started a power decrease on 8/18 at 0838 cnd held at 97.6% from 0919 to 1550 for nuclear instrumentation calibrations.

The unit was returned to 99.5% power at 1610.

The unit started a power increase to 100% on 8/19 at 0758 and reached 100% full power at 0818.

The unit started a power decrease on 8/20 at 1010 due to the "B"

feedwater pump recirculation valve failing open.

The unit stopped the power decrease at 1030 and started a power increase.

The unit held at 99% power from 1238 to 1300 for venturi fouling coef fient evaluation, the unit reached 100% at 1320.

The unit started a power decrease on 8/21 at 2311 and held at 97.8% from 2355 to 8/22 at 0405 for reactor protection system testing. The unit was returned to 100% full power at C429. The unit operated at or near 100% full pcwer for the remainder of the month.

Prepared by:

N.

C. Simmons Telephone:

704-382-5263

MOHIRIJ_RRU11L1RG__11E_qBMATION REOUEST 1.

Facility name:_RgSyfre.

Unit 1 2.

Scheduled next refueling shutdown:_fiarsh.1993 3.

Scheduled restart following refueling: May 1993 Tile 'HOJECT MANAGER liAS BEEN ADVISED BY SEPARATE COMMUNICATION OF ANY T.S.

CllANGE OR LICENSE AMENDMENT.

Ti!EREFORE, QUESTIONS 4 T!!ROUGli 6 WILL NO LONGER BE MAINTAINED IN TilIS REPORT.

4.

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

If yes, what will these be?

If no, has reload design and core configuration been reviewed by Safety Review Committee regarding u1 reviewed safety questions?

5.

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

6.

Important licensing considerations (now 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: 193 (b) in the spent fuel pool: 112 8.

Present licensed fuel pool capacity: 1463 Size of requested or planned increase:

9.

Projected date of last refueling which can be accommodated by present licensed capacity: Marcil_Lojl6 Dune POWER COMPANY DATE:

September 15, 1992 Name of

Contact:

R. A.__Hillican Phone:

7 04 - 3 8 2 - 514J2_

- ~~

A 4

P 0FETATING DATA REFDRT DOCFET ND 50-370 DATE fectenber 15. 1992 DPEFATINS STATUS COMPLETED BY R.A. Willians IELEPHONE 704-382-5346

1. Unit Nase: McGuire 2

2. Reporting Ferit,d: Augur.t 1, 1992-August 31,1992

3. Licented Thern i Power (MWt):

3411

4. Naseplate Rating (Bross MWe):

1305t Notes INaseplate Rating

5. Design Electrical Rating (Net MWeh 1100 (Stoss flWel calculated as

6. l.arious Dependable Capacity (Gross MWe):

!!71 1450.000 W A

.90 power

7. Maxisus Dependable Capacity (Net W e):

1129 factor per Page lii,

8. If Changes Occur in Capacity Ratings Ilttes Number 3 Through 7) Since last NURE6-0020.

-Report. Give Seasons:

9. Power Level To Which Restiitted, if Any (Net M e):

10. Reason for Restrictions, if any:

Ihis Month Yr.-to-Date Euaulative

11. Hours in Reporting Feriod 744.0 5E55.0 74543.0

12. Nuaber Of Hours Reactor Was Critical 646.1 32B5.9 56C7.4

13. Reatter Reserve Shutdown Hours

--0--

--0--

--0--

14. Hours Senerator On-line 629.6 32!5.2 55569.1-

15. Unit Reserve Shutdown Hours

--0--

--0--

--0--

16. Gross Thereal Energy Generated (MWH) 2074101 10427355-181443785 17.-Groo Electrical Energy Generated (NH1 704528 3623247 63454162

18. Het Electrical Energy Benerated (W H1 672554 344436B 63824779

19. Unit Service Factor 84.6 54.9 74.6

20. Unit Availability Factor

-64.6 54.9 74.6

. 21. Unit Capacity Factor (Using MDE Net) 80.1 52.1 71.3

22. Unit Capacity Fattor (Using DER Net!

76.6 49.9 69.2

23. Unit Forced Outage Rate 15.4 6.8 9.0

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

._Rane

- 25. If Shut Down At End Of Report Period. Estinated Date of Startup:

26. Units in Test Status (Prior to Cessercial Operationh Forecast Athieved

-r INITIAL CRITICAUTY INITIAL ELECTRICITY COMERCIAL DPERATION y

.....--..-~-..-.-...7.

-~j

=,

1 i

OPERAllNS DATA REPORI-J

.I DOCrET NO.

50-370-UNIT' McGuire 2 DATE September 15, 1992

-COMPLETED BY R.A. Williaet.

i TELEPHONE 704-382-5346

-90 NTH Auoust. 1992 (Al AVERASE D41LY POWER LEVEL pal AVERAGE DAILY POWER I.EVEL-

.MWe-Nett (RWe-Net!

(

1.

1116 17 1116 E'

1114 18 1117 3

_1117 19 1119 4-1119 20 ille 5

123 21 1117 6

0 22 1117 7

0 23 1112 8-0 24 441

.4 l l-

~ 9-370 25 416 l

10 tilo 26 1116

[

- 11 1117 27 1120 L:

l:.

12-1115 28

'!!23 l -

.12.

1114 -

29 1117

- 14 1113 30 1117 15 1!!3 31 1118

- 16 1114 L

l t

L I

i l :.

i..

..a

e UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-370-UNIT.NAME ~MCuulut, z DATE 09/13/y2 REPORT MONTH August 1992 COMPLETED BY

~~N.

c.

51MMUNS TELEPHONE _j/041-Juz-ogo; (2

(3)

(4)

(5)

(1)

A ). met-E HOD T

A OF LICENSE N

Y S

SHUT EVENT SYS-CAUSE AND CORRECTIVE O

P DURATION O

DOWN REPORT TEM COMPONENT ACTION TO-DATE E

HOURS N

R/X NO.

CODE CODE PREVENT RECURRENCE 11 92 5 F

97.10 A

3 HH VALVEX REACTOR TRIP ON LC-LO STEAM GENERATOR LEVEL WHEN A FEEDWATER REG. VALVE FAILED CLOSED.

CG XXXXXX CHEMISTRY 15-P 92 9 F

A 12 92-8-24 F

17.28 A

3 UA GENERA REACTOR TRIP DUE TO LOSS OF GENERATOR EXCITER FIELD CG XXXXXX CHEMISTRY A

16-P 92-8-25 F

HB VALVEX CONTROL VALVE MOVEMENT TESTING B

17-P 92-8-25 S

18-P 92-8-25 F

B RC INSTRU POWER MISMATCH CALIBRATIONS IA INSTRU NUCLEAR INSTRUMENTATION CALIBRATION R

19-P 92-8-25 F

B 1

(1)

(2)

(3)

(4)

Method:

Exhibit G - Instructions F Forced Reason-1-Manual.

for Preparation of, Data-A-Equihment FailureB-Maintenance or test (Explain)

S Scheduled 2-Manual Scram Ent W.Sneets For Licensee-Event Report (NUEG-0161) )

(LER 3-Automatic Scram C-Retueling-4-Other

(~ Explain)

File D-Regulatory Restriction E-Operator Training &. License Examination F-Administrative (5)Exhibit I - Same Source.

G-Operator Error-(Explain)

H-Orher (Explain) i

UNIT:

McGuire 2 DATE:

9/15/92 NARRATIVE SUKHARY MONTil: August 1992 McGuire Unit 2 began the month of August operating at 100% full power.

On 8/5 at 0323 the unit experienced an automatic reactor trip due to a Lo-Lo steam generator level when a feedwater regulating valve failing closed. The unit was } ' aced on-line on 8/9 at 0429.

During power esculation, the unit t

-t 30% from 0655 to 1300 for primary system chemistry. The held at Erom 2110 to 2237 for nuclear instrumentation calibrat the unit reached 100% full power on 8/10 at 0300. On 8/24 at 1003

.perienced an automatic reactor trip due to loss of generator excit-c tield when a light bulb on the generator field cabinet ;horted while the bulb was being removed. The unit was placed on-line on 8/25 at 0320. During power esculation, the unit held at 30% power from 0603 to 1143 for primary system chemistry, and at 43%

power from 1330 to 1341 for control valve sequential movement testing.

The un't held at 51% power from 1442 to 1554 for reactor power mismatch calibrations and at 66.5% power from 1751 to 1809 for nuclear instrumentation calibrations. The unit was held at 89.6% power from 2110 to 2145 for nuclear it.strumentation calibrations and thermal power outputs checks. The unit was returned to 100% full power on 8/26 at 0213, The unit operated at 100% for the remainder of the month.

Prepared by:

N. C.

Simmons Telephone:

704-382-5263

- - -. ~

~ _ ~. -

2 MONTHLY REFUELING INFORMATION REOUEST l.-

Facility name: McGuire, Unit 2' 2.

Scheduled next refueling shutdown: June 1993 3.

Scheduled restart following refueling; Auaust 1993 THE PROJECT MANAGER HAS BEEN ADVISED BY~ SEPARATE COMMUNICATION OF ANY T.J.

CHANGE OR LICENSE AMENDMENT.

THEREFORE, QUESTIONS 4 THROUGH 6 WILL NO LONGER.BE MAINTAINED IN THIS REPORT.

4.

Will-refueling or resumption of operation thereaf ter require a.

technical specification change or other license amendment?

If yes, what will these be?

i If no, has reload design and core-configuration been reviewed by l

Safety Review Committee regarding unreviewed safety questions?

5.

Scheduled date(s) for submitting 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).

7.

Number of Fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 211 8.

Present licensed fuel pool capacity: 1463 Size of requested or planned increase: ---

9.

Projected date of last refueling which can be accommodated by present licensed capacity: December,2003 DUKE POWER COMPANY DATE:

September 15. 1992

.Name of

Contact:

R.

A. Williams Phone:

704-382-5364

,_