AECM-84-0509, Monthly Operating Rept for Oct 1984

Monthly Operating Rept for Oct 1984

ML20099E641
Person / Time
Site:	Grand Gulf
Issue date:	10/31/1984
From:	Cesare J, Dale L MISSISSIPPI POWER & LIGHT CO.
To:	Deyoung R NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
AECM-84-0509, AECM-84-509, NUDOCS 8411210466
Download: ML20099E641 (8)

Text

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Attrchment to AECM-84/0509 Page 1 of 7 OPERATING DATA REPORT DOCKET NO.

50-416 DATE 11/15/84 COMPLETED BY J. C. Cesare TELEPHONE Ant _axo 9585 OPERATING STATUS Notes Grand Gulf Nuclear Station

1. Unit Name:

October 1984

2. Reporting Period:

3. Licensed Thermal Power (MW ): 3833 1372.5

4. Nameplate Rating (Gross MWe p:

1250

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

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

NA

9. Power Level To Which Restricted. If Any (Net MWeI:

10. Reasons For Restrictions.If Any:

Pnuar A = an a i nn Tact-Phnen This Month Yr.-to-Date Cumulatise 273 hrs 273 273

!I. Hours In Reporting Period 214.1 hrs 214.1 214.1

12. Number Of Houri Reactor has Critical 0

0 0

13. Reactor Resene Shutdown Hours 69.2 69.2 69.2

14. Hours Generator On-Line 0

0 0

15. Unit Resene Shutdown Heurs 150,367 MWh -

150,367 150,367

16. Gross Thermal Energy Generated (MWHi 9,640 MWh 9,640 9,640

17. Gross Electrical Energy Generated (MWH) 7,935 MWh 7,935 7,93)

18. Net Electrical Energv Generated (MWHi A

NA u

19. Unit Service Factor NA NA NA

20. Unit Availability Factor NA NA NA

21. Unit Capacitv Factor (Using MDC Neti NA NA NA

22. Unit Capacity Factor (Using DER Net)

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23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Each1:

April,1985 4-6 week outage for surveillance, SRV lubricant changeout and j

implementation of ICREG 0588 reauirements November 1, 1984

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

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

Forecast Achieved INITIAL CRITICALITY R/1R/R2 10/20/84 INITI A L ELECTR! CITY 03/85 COMMERCI AL OPER ATION 84112104' 841031 PDR ADOCK 05000416 (oj773 R

PDR g g, M f

Attachment to' AECM-84/0509 Pagt 2 of 7 INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT

. Tha report should be furnished each month by 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 m>ttuetion 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. savings time (or vice versa) occurs.

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

thermal power, expressed in megawatts. currently auth.

12. NUMBER OF HOURS REACTOR WAS CRITICAL.

orized 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 superes (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

5. DESIGN ELECTRICAL RATING (NET MW ) is the operation.

e 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.

e 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 reas ns was 8vada f r puanon.

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,m effect. Short tenn The thermal output of the nuclear steam supply system (less than one month) limitations on power level need L

during the gross hours of the reporting period. expressed not be presented in thisitem.

in megawatt hours (no decimals).

Since this information is used to develop figures on capa.

city lost due to restrictions and because most users of the

17. GROSS ELECTRICAL ENERGY GENERATED (MWH).

t

" Operating Plant Status Report" are primarily interested The electrical output of the unit measured at the output I

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).

l MWt or percent power.

18. NET ELECTRICAL ENERGY GENERATED (MWH).

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 appiopriate. 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 produe.

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 penod. the gross hours from the beginning of the period on eummercial operation as a starting date.

ERD 1

JAttrchment'to l

AECM-84/0509 P;g2 3 cf.7

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i19J UNIT SERVICE FACTOR. Compute by. dividing hours '

the generator was on line (item 14) by the gross hours in

' the reporting period (item i1). Express as percent to the nearest tenth of a percent. Do not include reserve shut-down hours in the calculation.

20. UNIT AVAILABILITY 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 i1).

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 (itim 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 (refueling. 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. Self4xplanatory. 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.

l 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 availab!c for commercial operation.

Date of COMMERCIAL OPERATION is defined as the date that the unit was declared by the utility owner to

= be availaole for the regular production of electricity.

usually related to the satisfactory completion of quali-tication tests as speenfied in the purchase contract and to the accounting poheies and practices of the utility.

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Att:chnent to

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AECM-84/0509 AVERAGE DAILY UNIT POWER LEVEL :

P gi 4.cf 7 50-416 DOCKET NO.

UNIT DATE 11/15/84 J. G. Cesare COMPLETED BY TELEPHONE. 6ni ono-9sas October 1984 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 0 1

0-37 0

gg

~0 2

0 3

39 n

4 0

20 25 5

0 21 62 0

86 6

22 0

7 n

23 g

0 24 19 0

9 25 0

10 26 n

II O

27 0

0 0

12 28 0

0 13 29 14 0

30 0

15 0

3 0

0 16 INSTRUCTIONS On this format. list the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

l (9/77)

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t UNIT SHUTDOWNS AND POWER REDUC 110NS DOC m M.

%W6 UNIT NAME -

1 DATE 11/1 R IE COteLETED BY T

c ca ~ =

REPORT MONTH nnnhor - 1984-TELEPHONE 601-969-2sa5 i

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c

.2 E 3

y Y ~4 Licensee Eg Cause & Corrective

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No.

Date

{

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,3 g g Event U

Q Action to

$E 5

j di g Report *

<a O Prevent Recurrence g

d 84-1 10/21/84 F

8.4 B

5 NA ZZ ZZZZZ Hain generntor testing and maintenance i

84-2 10/21/84 F

0.6' B

5 NA ZZ ZZZZZ Kain generator testing and maintenance j

84-3 10/22/84 F

6.6 B

5 NA ZZ ZZZZZ Main generator testing and maintenance 84-4 10/24/84 S

129.3 B

5 NA ZZ ZZZZZ Hain generator testing and maintenance i

84-5 10/29/84 S

58.9 B

2 NA ZZ ZZZZZ The reactor was manually scrammed to complete the first phase of power ascension testing. A maintenance outage followed to modify the main steam bypass to condenser dump spargers for improved draining.

4 5

4 i

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e

-ts 1

m>>

l 1

2 3

4 S,

J t": g F: Forced Reason:

Method:

Exhibit G. instructions a9m B. Maintenance of Test 2-Manual Scram.

for Preoarat6on of Data l vid-@-

S. Scheduled A-Equipment Failure (Explain) 1-Manual i

Entry Sheets for Liceruce oRg C Refueling 3-Automatic Scram.

Event Repew (LER) File (NUREG-moo D-Regulatory Restriction g4)ehgr(Engo)ad 0161)'

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E-Operator Training A License Enmination Re uce F-Administrative 5

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, In accordance G-Operational Erro:IExplain)

Exhibie I Same Source 19/77)

Il4)ther (Explain) with Nureg 1022 I

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Attechment to-

. UNIT SHUTDOWNS AND POWER REDUCTIONS AECM-84/0509'

/

Page 6 of 7 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.

ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT #.

Reference the applicable 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 />) fePortable occurrence pertaining to the outage or power

• sh:uld be noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequential 3

shut down completely. For such reductions in power level, report number, occurrence code and report type) of the five 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 Recurrence 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 pewer reduction.

not 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 bet assigned to each shutdown or significant reductionin power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power reduction begins in one report period and ends in another, SYSTEM CODE. The system in which the outage or power tn entry should be made for both report periods to be sure reduction originated sh'ould be noted by the tw'o digit code of all shutdowns or significant power reductions are reported.

Exhibit G Instructions for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREG4161).

j ber shoul:1 be assigned to each entry.

Systems that do ::et fit any existing code should be designa.

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 apphcable, of each shutdown or significant power reduction. Report as year. month, and day. August 14.1977 would be reported as 770814. When a shutdown or significant power reduction COMPONENT CODE. Select the most appropriate component from Exhibit 1 Instructions for Preparation of Data Entr>

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 or significant power reductions are reported.

using the following critieria:

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche.

duled." respectively, for each shutdown or significant power B.

If not a componem failure. use the re!ated component:

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

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

ment is required in categorizing shutdrwns in this way. In C.

general, a forced shutdown is one that would not have been If a chain of failures occurs, the first component to mal.

completed in the absence of the condition for which corrective function should be listed. The sequence of events.includ.

action was taken.

ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur.

rence column.

DURATION. Sc!f. explanatory. When a shutdown extends beyond the end of a report period. count only the time to the Components that do not fit any existing code should be de.

end of the report period and pick up the ensuing down time s gnated XXXXXX. The code ZZZZZZ should be used for In the followmg report periods. Report duration of outages events where a component designation is not applicable.

rounded to the nearest tenth of an hour to facilitate summation.

The sum of the total outage hours plus the hours the genera.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

tot was on line should equal the pross hours m the reportmg RENCE. Use the column in a narrative fashion to amplify or peri d.

explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut-REASON. Categorize h3 lettes de>ignation m accordance down or significant power reduction and the immediate and with the table appearmy on the report form. If category H contemplated long term corrective action taken, if appropri-must be used. supply briel comments.

ate. This column should also be used for a description of the maior safety.related corrective maintenance performed during METHOD OF SHUTTING DOWN THE REACTOR OR the outage or power reduction including an identification of REDUCING POWER. Cateponic by number designation the critical path activity and a report of any single release of radioactivit3 or single radiation exposure specifically assoet-INote that this difiers f rom the Edison Electric Institute ated with the outage which accounts for more than 10 percent (Efil definitions of " Forced Partial Outage" and " Sche.

of the allowable annual values.

duled Partial Outage!' Foi these term 1.1.1 use> a 6hange of For long textual reports continue narrative on separate paper 30 M% as the break pomi. I o, larpei power reactors.30 M%

and reference the shutdown or power reductmn foi tha la i+*.*imJll J shange to wassaiit esplanaitori.

riarrative i

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Att chment to AECM-84/0509

~ Page 7 of 7

):

.o 2 MAIN STEAM SAFETY RELIEF VALVE CHALLENGES DOCKET No.

50-416 UNIT 1-

DATE.11/15/84 COMPLETED.BY J. C. Cesare TELEPHONE 601-969-2585 3

Date of. occurrence:

neenhar 13. 1984. 1349 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.132945e-4 months <br />

]

' Plant operating condition:

~

950~

Rx Mode - I

~ Rx Power (MWT)

- 739 Rx Pressure Rx Power '(MWE) 0:

Rx Temperature { '534

!I l

Number of main steam SRV's:

20 l

I Number: of SRVs affected by event::

Narrative:

s On October 13, 1984, a maintenance supervisor noticed the keylock handswitch.

for main' steam safety relief valve F051F in a position between "AUT0" and :

OPEN". This was reported to Operations. The operator investigating found that the switch was not loose, but when he touched the key switch, the red c

(open) indicating light illuminated. The operator immediately turned the-switch to "0FF" and then to."AUT0"..The computer printout indicates the time between the relief valve' pilot' solenoid sequencing on and off was'22 cycles of a second. The relief valve tail' pipe temperature indicated 175'F verifying the valve did lift.

There was no malfunction of the switch. 6m we;, the switch key was bent.

The position of the switch was such Wa e ight movement initiated an open signal. The key was replaced.

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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi N

P. O. B O X 164 0. -J AC K S O N, MIS SIS SIP PI 3 9 2 0 5 November 14, 1984 NUCLEAR LICEN$1NG & 5AFETY DEPARTMENT Mr. Richard C. DeYoung, 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-84/0509 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 October, 1984 (attachment).

Documentation of a challenge to a safety relief valve is included in this reporr as required by Technical Specification 6.9.1.10.

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

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

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

Mr. R. B. McGehee (w/o)

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

Mr. G. B. Taylor (w/o) l l

Mr. J. P. O'Reilly, Regional Administrator (w/a)

U. S. Nuclear Regulatory Commission l

Region 11 101 Marietta St., N.W., Suite 2900 Atlanta, Georgia 30323 Chief (w/2)

Office of Resource Management

/h U.S. Nuclear Regulatory Commission M

asMngton, D.Cg,geY Middle South Utilities System I