AECM-85-0292, Monthly Operating Rept for Aug 1985

Monthly Operating Rept for Aug 1985

ML20137P471
Person / Time
Site:	Grand Gulf
Issue date:	08/31/1985
From:	Cesare J, Dale L MISSISSIPPI POWER & LIGHT CO.
To:	Taylor J NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
AECM-85-0292, AECM-85-292, NUDOCS 8509190658
Download: ML20137P471 (11)

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l OPERATING DATA REPORT 50-416 DOCKET NO.

DATE 9/10/85 COMPLETED BY J.G. Cesare TELEPHONE (An1T 069-2585 OPERATING STATUS Grand Gulf Nuclear Station Notes

1. Unit Name:

August 1985

2. Reporting Period:

3. Licensed Thermal Power (MWI):

3833 Mut 1372.5 MWe

4. Nameplate Rating (Gross MWe):

1250 MW

5. Design Electrical Rating (Net MWe):

1157

6. Maximum Dependable Capacity (Gross MWe):

1108

7. Maximum Dependable Capacity (Net MWe):

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

N/A

9. Power Level To Which Restricted.lf Any (Net MWe):

N/A

10. Reasons For Restrictions. If Any:

N/A This Month Yr.-to-Date Cumulative 744 5,832 7.569

11. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 677.1 4.231.4 s.741.s 0

0 0

13. Reactor Reserve Shutdown Hours 647.0 3,710.1 4.413.2

14. Hours Generator On-Line 0

0

O

15. Unit Reserve Shutdown Hours

16. Gross Therma! F.nergy Generated (MWH) 2,204,464 10.396.715 11.276.855

17. Grou Electrical Energy Generated (MWH) 675.840 3,135,670 3.332.190

18. Net Electrical Energy Generated (MWHI 643,018 2.944.749 3.109'7in 87.0 41 1 91.3

19. Unit Service Factor 87.0 91.3 91.3

20. Unit Availability Factor 78.0 78.1 78.1

21. Unit Capacity Factor (Using MDC Net) 69.1 69.3 69.3

22. Unit Capacity Factor (Using DER Net) 13.0 8.7 8.7

23. Unit Forced Outage Rate

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

Fall Outage; October 12,1985; 46 days N/A

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

26. Units in Test Status (Prior to Commercial Operationi:

Forecast Achieved 8/18/82 INITIAL CRITICALITY

,10/20/84 INITIAL ELECTRICITY

.7/1/85 ytl COMMERCIAL OPERATION 8509190650 850031 g' g PDR ADOCK 05000416 R

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w INSTRUCIlONS FOR COMPLETING OPERATING DATA REPORT

'fhis report should be fumished each monthby licensees. The name and telephone number of the preparer should be provided in the designated spaces. The instructions below are provided to assist licensees in reporting the data consistently. The number of the instruction corresponds to the item number of the report format.

1. UNIT NAME. Self. explanatory.

or of commercial operation, whichever comes last, to the end of the period or decommissioning, whichever comes

2. REPORTING PERIOD. Designate the month for which first. Adjustments in clock hours should be made in the data are presented.

which a change from standard to daylight savirigs time (or vice versa) occurs.

3. LICENSED THERMAL POWER (MW )is the maximum g

thermal power, expressed in megawatts, currently auth-

12. NUMBER OF HOURS REACTOR WAS CRITICAL crized by the Nuclear Regulatory Commission.

Show'the total number of hours the reactor was critical during the gross hours of the reporting period.

4. NAMEPLATE RATING (GROSS MW,). The nameplate power designation of the turbine. generator in megavolt

13. REACTOR RESERVE SHUTDOWN HOURS. The total amperes (MVA) times the nameplate power factor of the number of hours during the gross hours of reporting turbine generator.

period that the reactor was removed from service for administrative or other reasons but was available for S. DESIGN ELECTRICAL RATING (NET MW,) is the operation.

nominal net electrical output of the unit specified by the utility and used for the purpose of plant design.

14. HOURS GENERATOR ON-LINE. Also called Service Hours. The total number of hours expressed to the near-

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MW,)

est tenth of an hour during the gross hours of the re-is the gross electrical output as measured at the output porting period that the unit operated with breakers terminals of the turbine-generator during the most re-closed to the station bus. These hours, plus those listed strictive seasonal conditions.

in Unit Shutdowns for the generator outage hours,should

7. MAXIMUM DEPENDABLE CAPACITY (NET MW,).

Maximum dependable capacity (gross) less the normal

15. UNIT RESERVE SHUTDOWN HOURS. The totalnum-station service loads, ber of hours expressed to the nearest tenth of an hour during the gross hours of the reporting period that the

8. Self. explanatory.

unit was removed from service for economic or similar nas ns ut was adaWe for opuadom

9. POWER LEVEL TO WHICH RESTRICTED, IF ANY (NET MW,). Note that this item is applicable only if

16. GROSS THERMAL ENERGY GENERATED (MWH).

restrictions on the power level are in effect. Short-tenn The thermal output of the nuclear steam supply system (less than one month) limitations on power level need during the gross hours of the reporting period, expressed not be presented in this item.

in megawatt hours (no decimals).

Since this information is used to develop figures on capa-etty lost due to restrictions and because most users of the

" Operating Plant Status Report" are primarily interested The electrical output of the unit measured at the output in energy actually fed to the distribution system. it is terminals of the turbine-generator during the gross hours requested that this figure be expressed in MWe-Net in of the reportmg period, expressed in megawatt hours (no spite of the fact that the figure must be derived from decimals).

MWt or percent power.

18.' NET ELECTRICAL ENERGY GENERATED (MWH).

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10. REASONS FOR RESTRICTIONS, IF ANY. If item 9 The gross electrical output of the unit measured at the Is used, item 10 should explain why. Brief narrative is output terminals of the turbine-generator minus the nor-acceptable. Cite references as appropriate. Indicate mal station service loads during the gross hours of the whether restrictions are self-imposed or are regulatory reporting period, expressed in megawatt hours. Negative requirements. Be as specific as possible within space limi-quantities should not be used. If there is no net positive tations. Plants in startup and power ascension test phase value for the period, enter zero (no decimals).

should be identified here.

11. HOURS IN REPORTING PERIOD. For units in power

19. For units still in the startup and power ascension test ascension at the end of the period, the gross hours from

23. phase items 19 23 should not be computed. Instead, enter the beginning of the period or the first electrical produc.

N/A in the current month column. These five factors tion, whichever comes last, to the end of the period.

should be computed starting at the time the unit is de.

clared to be in commercial operation. The cumulative For units in commercial operation at the end of the figures in the second and third columns should be based period, the gross hours from the beginning of the period on commercial operation as a starting date.

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19. UNIT SERVICE FACTOR. Compute by dividing hours the generator was on line (item 14) by the gross hours in the reporting period (item 11). Express as percent to the nearest tenth of a percent. Do not include reserve shut-down hours in the calculation.

20. UNIT AVAll. ABILITY FACTOR. Compute by dividing the unit available hours (item 14 plus item 15) by the gross hours in the reporting period (item iI). Express as percent to the nearest tenth of a percent.

21. UNIT CAPACITY FACTOR (USING MDC NET). Com-pute by dividing net electrical energy generated (item 18) by the product of maximum dependable capacity (item

7) times the gross hours in the reporting period (item 1I).

Express as percent to the nearest tenth of a percent.

22. UNIT CAPACITY FACTOR (USING DER NET). Com-pute as in item 21. substituting design electrical rating (item 5) for maximum dependable capacity.

23. UNIT FORCED OUTAGE RATE. Compute by dividing the total forced outage hours (from the table in Unit Shutdowns and Power Reductions) by the sum of hours generator on line (item 14) plus total forced outage hours (from the table in Unit Shutdowns and Power Reductions).

Express as percent to the nearest tenth of a percent.

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH). Include type (refuelmg. maintenance, other), proposed date of start of shutdown, and proposed length of shutdown.

It is recognized that shutdowns may be scheduled between reports and that this item may not be allinclusive. Be as accurate as possible as of the date the report is prepared.

This item is to be prepared each month and updated if appropriate until the actual shutdown occurs.

25. Self explanatory.

26. Self-explanatory. Note, however, that this information is requested for all units in startup and power ascension test status and is not required for units already in com-mercial operation.

TEST STATUS is defined as that period following ini-tial criticality during which the unit is tested at succes.

sively higher outputs, culminating with operation at full power for a sustained period and completion of war.

ranty runs. Following this phase, the unit is generally considered by the utility to be available for commercial operation.

Date of COMMERCIAL OPERATION is defined as the date that the unit was declared by the utility owner to be available for the regular production of electricity, usually related to the satisfactory completion of quali-fication tests as specified in the purchase contract and to the accounting policies and practiers of the utility.

14/77)

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AVERAGE DAILY UNIT POWER LEVEL j

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'50-416 DOCKET NO.

I UNIT 9/10/85 DATE J.G. Cesare COMPLETED BY (601) 969-2585 TELEPHONE MONDI August 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1036 I

g7 1088 998 1102 2

gg 3

787 39 1097 954 1105 4

20 1038 1100 5

21 1068 1102 7

437 23 225 0

0 8

24 9

104 25 265 10 796 26 906 1005 992 gg 27 12 28 13 926 29 1136 1037 1132 I4 30 1007 H16 15 3,

16 1088 INSTRUCTIONS On this format lisi the average daily unit power levelin MWe. Net for each day in the reporting month. Compute to the nearest whole rnegawait.

(9/77i

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UMUMU l

MET NO.

M-W l

UNIT SHUTDOWNS AND POWER REDUCi10NS UNIT NAME _ _

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DAM 9/10/85 COMPLETED BY J.G.

Cesare TELEPHONE (601) 969-2510 REPORT MONTH Aucust 1985 E

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yY3 Licensee 5%

• 1, Cause & Corrective

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No.

Date h

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jg5 Event gT EO Prevent Recurrence fI j;g g Repews a v>0 H

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85-18 8/7/85 F

48.5 A

3 85/030 TJ CON The generator and turbine tripped I

producing a reactor scram when a painter bumped a defective electrical j

connector causing a' loss of power to a generator cooling water instrument.

The instrument connector was reworked.

Six main steam line safety relief valves (SRVs) lifted during the transient as their low-low setpoint was reached.

85-19 8/23/85 F

48.5 A

1 N/A IB ANN The plant was shutdown to trouble-shoot f ailed Control Room annunciator:

Failed annunciator reflash cards were replaced and the plant restarted.

I 2

3 4

Method:

Exhibit G-Instructions F: Forced Reason:

S: Scheduled A-Equipment Failure (Explain) 1-Manual 5-Reduced for Preparation of Data B-M2intenance of Test 2-Manual Scram.

load Entry Sheets for Licensee 3 Automatic Scram.

Event Repost (LERI File (NUREG-C-Refueling 4 Continued 6-other 0161)

D-Regulatory Restriction EOperator Training & Ucense Examination 5

F-Administrative

• In accordance Exhibit I - Same Source G-Operational Error (Explain) with Nureg 1022 (9/77) flother (Explain)

c UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the in accordance with the table appearing on the report form.

report period. In addition,it should be the source of explan.

If category 4 must be used, supply brief comments.

ation of significant dips in average power levels. Each signi-LICENSEE EVENT REPORT #.

Reference the applicable 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 />)

Teportable occurrence pertaining to the outage or power reduction. Enter the first four parts (event year, sequential should be noted, even though the unit may not have been shut down completely. For such reductions in power level, report number, occurrence code and report type) of the five l

the duration should be listed as zero,the method of reduction Part designation as described in item 17 of Instructions for should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG-0161). This information may not be Cause and Corrective Action to Prevent Kecurrence column immediately evident for all such shutdowns, of course, since should be used to provide any needed explanation to fully further investigation may be required to ascertain whether or describe the circumstances of the outage or power reduction.

n t a reportable occurrence was involved.) If the outage or power reduction will not result in a reportable occurrence, NUMBER. This column should indicate the sequential num, the positive indication of this lack of correlation should be ber assigned to each shutdown or significant reduction in power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power SYSTEM CODE. The system in which the outage or power reduction begins in one report period and ends in another, reduction origintted sh'ould be noted by the two digit code of

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an entry should be made for both report periods to be sure Exhibit G Instructions for Preparation of Data Entry Shee s all shutdowns or significant power reductions are reported.

for Licensee Event Report (LER) File (NUREG4161).

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

Systems that do not fit any existing code.hould be designs.

ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or significant power reduction. Report as year, month, and day. August 14,1977 would be reported COMPONENT CODE. Select the most appropriate component as 770814. When a shutdown or significant power reduction from Exhibit I Instructions for Preparation of Data Entry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG4161).

be made for both report periods to be sure all shutdowns using the following critieria:

or significant power reductions are reported.

A. If a component failed,use the component directlyinvolved.

"IYPE. Use "F" or "S" to indicate either " Forced" c,r " Sche-dt<ed," respectively, for each shutdown or significant power B.

If not a component failure, use the related component:

reduction. Forced shutdowns include those required to be e.g., wrong valve operated through error; list valve as initiated by no later than the weekend following discovery component.

of an off-normal condition. It is recognized that some judg.

ment is required in categorizing shutdowns in this way, in C. If a chain of failures occurs, the first component to mal-ganeral, a forced shutdown is one that would not have been function should be listed. The sequence of events,includ.

i completed in the absence of the condition for which corrective ing the other co.nponents which fail, should be described action was taken.

under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Selfexplanatory. Wnen a shutdown extends Components that do not fit any existing code should be de-beyond the end of a report period, count only the time to the signated XXXXXX. The code 777777 should be used for end of the report period and pick up the ensuing down time events where a component designation is not applicable.

in the following report periods. Report duration of outages rounded to the nearest tenth of an hour to facilitate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

The sum of the rotal outage hours plus the hours the genera-RENCE. Use the column in a narrative fashion to amplify or tor was on line should equal the gross hours in the reporting explain the circumstances of the shutdown or power reduction.

period.

The column should include the specific cause for each shut-wn r s gn ant pown Mupn and h imme&ste and REASON. CateIorize by letter designation in accordance contemplated long term corrective action taken, if appropri-with the table appearing on the report form. If category H ate. This column should also be used for a description of the must be used, supply brief comments.

major safety.related corrective maintenance performed during the outage or power reduction including an identification of METHOD OF SHUTTING DOWN THE REACTOR OR the critical path activity and a report of any single release of REDUCING POWER. Categorize by number des:gnation radioactivity or single radiation exposure specifically associ.

I ote that this differs from the Edison Electric institute ated with the outage which accounts for more than 10 percent N

(EED definitions of " Forced Partial Outage" and " Sche.

of the al:owable annual values.

duled Partial Outage." For these terms. eel uses a change of For long textual reports continue narrative on separate paper 30 MW as the break pomt. For larges power reactors.30 MW and reference the shutdown or power reduction for ihn i

is too small a change to warrant oplanation.

narrative.

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MAIN STEAM SAFETY RELIEF VALVE CHALLENGES DOCKET NO. 50-416 i

UNIT 1

DATE 9/10/85 COMPLETED BY J.G. Cesare TELEPHONE (601) 969-2585 Date of occurrence:

August 7, 1985 i

Plant operating condition:

Rx Power (HWt) 3515 Rx Pressure 1027 psig Rx Mode 1

Rx Power (MWe) 1064 Rx Temperature 536*F Number of main steam SRV's:

20 Number of SRV's affected by event:

6 Narrative:

The main generator and turbine tripped when a painter bumped a defective electrical connector causing a loss of power to a generator cooling water instrument.

The reactor scrammed on a turbine control valve fast closure signal. Safety relief valves F051A, F051B, F051D, F051F, F047D, and F047G lif ted as their low-low setpoint was reached. See LER 85-030 for further details.

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MAIN STEAM SAFETY RELIEF VALVE CHALLENGES DOCKET NO. 50-416 UNIT 1

DATE 9/10/85 COMPLETED BY J.G. Cesare TELEPHONE (601) 969-2585 Date of occurrence:

August 16, 1985 Plant operating condition:

Rx Power (MWt) 3691 Rx Pressure 1035 psig Rx Mode 1

Rx Power (MWe) 1144 Rx Temperature 531*F Number of main steam SRV's:

20 Number of SRV's affected by event:

2 Narrative:

Safety relief valves F041A and F041C were opened as part of a planned power ascension test.

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i MAIN STEAM SAFETY RELIEF VALVE CHALLENGES DOCKET NO. 50-416 i

UNIT 1

DATE 9/10/85 RCOMPLETED BY J.G. Cesare TELEPHONE (601) 969-2585 Date of occurrence:

August 18, 1985 Plant operating condition:

Rx Power (MWt) 3790 Rx Pressure 1025 psig Rx Mode 1

Rx Power (MWe) 1184 Rx Temperature 535'F i

Number of main steam SRV's:

20 Number of SRV's affected by event:

1 Narrative:

During the performance of a routine monthly surveillance, the low-low set logic for SRV F051D was inadvertently actuated. The 'B' logic had been placed in l

the trip state by performance of the surveillance. The

'F' logic was actuated by a transient on the 24 volt DC power supply created when a trip unit was removed.

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MAIN STEAM SAFETY RELIEF _ VALVE CHALLENGES I

DOCKET NO. 50-416 5

UNIT 1

DATE 9/10/85 i

COMPLETED BY J.G. Cesare TELEPHONE (601) 969-2585 Date of occurrence:

August 26, 1985 j

Plant operating condition:

Rx Power (MWt) 3335 Rx Pressure 1022 psig Rx Mode 1

Rx Power (MWe) 1038 Rx Temperature 545'F Number of main steam SRV's:

20 i

i Number of SRV's affected by event:

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l Narrative:

j Safety relief valve F051B was lifted as a planned retest for a maintenance work authorization to verify proper operation of the low-low trip logic.

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MISSISSIPPI POWER & LIGHT COMPANY I

Helping Build Mississippi Edhhihkliddl P. O. B O X 16 4 0. J A C K S O N. MISSISSIPPI 39215-1640 September 16, 1985 NUCLEAR LICEN5ING & SAFETY DEPARTMENT Mr. James M. Taylor, Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attention: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/L-835.0 Monthly Operating Report AECM-85/0292 In accordance with 10CFR50.36, Mississippi Power & Light Company (MP&L) is providing twelve copies of the Monthly Operating Report for Grand Gulf Nuclear Station Unit 1 for August, 1985 (attachment).

If you have any questions or require additional information, please contact this office.

Yours truly, L. F. Dale Director GWD/JGC:bms Attachment cc:

Mr. J. B. Richard (w/a)

Mr. O. D. Kingsley, Jr. (w/a)

Mr. R. S. McGehee (w/a)

Mr. N. S. Reynolds (w/a)

Mr. H. L. Thomas (w/o)

Mr. R. C. Butcher (w/a)

Dr. J. Nelson Grace, Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 Chief (w/2)

Office of Resource Management U. S. Nuclear Regulatory Commission y %L Washington, D. C.

20555 J16AECM85090602 - 1 Ifg Member Middle South Utilities System