AECM-86-0040, Monthly Operating Rept for Jan 1986

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Monthly Operating Rept for Jan 1986
ML20153C694
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 01/31/1986
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-86-0040, AECM-86-40, NUDOCS 8602210505
Download: ML20153C694 (9)


Text

l Attechment to AECM-86/0040 DOCKET NO.

50-416 l

DATE 02/03/86 COMPLETED BY J. G. Cesare TELEPIIONE 601-969-2585 OPERATING STATUS 1.

Unit'Name:

GGNS Unit 1 l Notes:

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2.

Reporting Period:

January 1986 l

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3.

Licensed Thermal Power (MW ):

3833 MWt l

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l 4.

Nameplate Rating (Gross MW ):

1372.5 MWe l

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S.

Design Electrical Rating (Net MW ):

1250 MWe l

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6.

Maximum Dependable Capacity (Gross MW ):

1157 MWe l l

l 7.

Maximum Dependable Capacity (Net MW )T 1108 MWe l

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8.

If Changes Occur in Capacity RatingI (Items Number 3 Through 7) Sinci tast

(

Report. Give Reasons:

l NA l

9.

Power Level To Which Restricted, If Any (Net NW ): 60 percent (~ 700 MW -Net l

10. Reasons For Restrictions, If Any: Planned administrative power reduction for _

l economic and load dispatch considerations.

l This Month Yr to Date Cumulative

11. Ilours In Reporting Period 744 744

_ 11241

12. Number of liours Reactor Was Critical 711.6 711.6 7436.8
13. Reactor Reserve Shutdown Hours 0

0 0

l

14. Ilours Generator On-Line 681.6 681.6 6428.6
15. Unit Reserve Shutdown Ifours 0

0 0

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16. Gross Thermal Energy Generated (MWil) 1,790,640 1,790,640 17,747,133 1
17. Gross Electrical Energy Generated (NWil)

_548,420__

_548,420_

5,320,730

18. het Electrical Energy Generated (MWil) 519,614 519,614 4,995,3_2_6
19. Unit Service Factor 91.6 91.6 65.4
20. Unit Availability Factor 91.6 91.6 65d
21. Unit Capacity Factor (Using MDC Net) 63.0 63.0 55._5
23. Unit Forced Outage Rate 55.9 55.9 49.2
22. Unit Capacity Factor (Using DER Net) 8.4 8.4 9.9
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

i None

25. If Shut Down At End Of Report Period.

Estimated Date of Startup:

NA

26. Units In Test Status (Prior to Commercial Operation).

Forecast Achieved INITIAL CRITICALITY 08/, t h/l 2_

INITIAL ELECTRICITY 10L 84 COMMERCIAL OPERATION O

85 l

I fj20505060131 ff DOCK 05000436 PDR I

J14AECM86020701 - 3 ili

Attachment to AECM-86/0040

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INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT Tha report should be furnished each month by heensees. The name and telephone number of the preparer should be provided in l

the designated spaces. The mstructions below are prouded to assist heensees in reporting the data consistently. The number of the m>tiu non corresponos to the item number of the report format.

1. LNIT NetE. Self.esplanatory.

or of commercial operation. wSucheser comes last, to the l

end of the period or decommissiontng, 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 dayhght. savings time (or vice versa) occurs.

l

3. LICENSED THERMAL POWER (MW l ts the maumum i

thermal power, expressed in megawatts. currently auth-

12. NUMBER Of HOURS REACTOR WAS CRillCAL.

orized by the Nuclear Regulatory Commission.

Show the total number ut hours the reactor was critical during the gross hours of the reportmg period.

l

4. NelEPLATE RATING IGROSS MW,h The nameplate power designation of the turbine. generator in megavolt
13. REACTOR RESERVE SHUTD0%N HOURS. The total i

superes (MVA) times the nameplate power factor of the number of hours dunng the gross hours of reportmg turbme generator.

penod that the reactor was removed from service for administratise et other reasons but was available for

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

operation.

nommal net electrical output of the unit specified by the l

utihty and used for the purpose of plant design.

14. HOURS GENERATOR ON.LINE.

Also called Service

o. MAXIMUM DEPENDABLE CAPACITY IGROSS MW l Hours. The total number of hours expressed to the near-is the gross electncal output as measured at the output est tenth of an hour during the gross hours of the re-e terminals of the turbine Fenerator during the most re-portmp period,that the unit operated with breakers strictne seasonal conditions.

closed to the station bus. These hours, plus those listed m Umt %utdowns for the generator outage hours, should 7 MAXIMUM DEPENDABLE CAPACITY (NET MW, L Maumum dependable capacity Igross) less the normal station service loads-

15. UNIT RESERVE SHUTDOhN HOURS. The totalnum.

ber of hours expressed to the nearest tenth of an hour

6. Self<splanatory, durmg the grou hours of the reporting period that the l

unit was remmed from service for economic or similar l

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MW ).

Note that this item is appheable only if e

restrictions on the power level are in effect. Short term

16. GROSS THERMAL ENERGY GENERATED (MWH).

liess than one month) limitations on power lesel need The thermal output of the nuclear steam supply system not be presented in this item.

during the gross hours of the reportinit period, expressed in megawatt hours (no decimalst l

Smce this information is used to deselop figures on capa.

city lost due to restnctions and because most users of the

" Operating PlantStatus Reporv are primanly interested The electrical output of the unit measured at the output in energy actually fed to the distnhution system. it is termmals of the imbme generator during the gross hours requested that this figure be expressed in MWe Net in of the reportmp period expressed in megawatt hours (no l

spite of the fact that the figure must be denved from decimaist MWI or percent gower.

I

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18. NET ELECTRICAL ENERGY GENERATED IMWHL l
10. REASONS FOR RESTRICTIONS. IF ANY. It' item 9 The g.ns electrical output of the umt me.isured at the is used. Item 10 should explain wh). litief narratne is output termmals of the turbine generator mmus the not.

acceptable. Cite referenses as appropnate. Indisate whether testrictions are selfamposed or are regulatory mal station seru,e loads dunng the gross hours of the i

requirements. Be a speufie as pomble wntun space hmi-reporting penod, espressed m meFawatt hours. Negative latmns. Plants in startup and power acension test phase quantities should not be used. If there is no nel positive should be identified here.

value for the period, enter pero (no decunals).

11. HOURS IN REPORTING PERIOD For umts m power
19. For units still m the startup and power ascension test ascension at the end of the penod. the grms hours f rom 23 phase, items 19 23 should not be 60mputed. Instead. enter the begmnmg of the penod or the first electnsat produe.

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

should be computed startmp at the tune the unit is de.

Ior units in commercial operation at the end of the slated to be m somrnercial operation. The cumulative figmes m the wcor4 and thhd columm should be beed period, the gross hours from the begmmng of the renod on sommerdal operatmn n a startmg date.

M __,

Attechment to AECM-86/0040

19. UNIT SERVICE FACTOR. Compute by dividing hours the generator was on hne (item 14) by the gross hours in the reporting peri (d (ium !!). 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 pcNent.
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 I!).

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 titem 14) plus total forced outage hours I

(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. Self-explanatory. Note, however, that this information is requested for alt 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 im-tist criticality during whish the unit is tested at sleces-sively higher outputs. culmmatmg with operation at full power for a sustamed period and 6ompletion of war.

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

Date of COMMERCIAL OPERATION is defined as the daic that ale unit was declared by the utility owner to be available for the regular produstion of electricity, usually related to the satisfJstory Gompletion of quali-fication tests as specified in the pur$hase contract and in ihe accounting pohsics and practises of the utihty.

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Attachment to AECM-86/0040 DOCKET NO.

50-416 UNIT UNIT I DATE __ 02/03/86 COMPLETED BY J. G. Cesare TELEP110NE 601-969-2585 MONTH JANUARY DAY AVERAGE DAILY POWER LEVEL DAY (MW ~

  • AVERAGE DAILY POWER LEVEL e

(MN -Net) 1 0

e 17 677 2

482 18 677 3

962 19 4

694 1163 20 688 5

1147 21 6

664 1081 22 195 7

1076 23 8

10 1087 24 227 9

1086 25 10 447 1053 26 674 11 702 12 27 707 712 28 688 13 693 29 14 669 693 30 681 15 685 31 669 16 686 J14AECM86020701 - 7

, +. -

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=

Attcchment ts AECM-86/0040 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-416 DATE

.02/03/86 COMPLETED BY J.

G. Cegare TELEPHONE 601-969-2533 I

i i

i I

Method or i Licensee Cause & Corrective No.

Date Type Du ra t ion Reason Shutting Downl Event System Component Action I

(1) l Hours (2)

Reactor i Report # l Code Code i

I (3)

(4)

(5)

Prevent Recurrence (Shutdown continued from last I

i report).

85-26.12/31/85 F

9.2 H

G 4

85-050 SD LT Faulty sndication or condenser l

l l

l hotwell level led to a hotwell 1

(

I low condensate level which caused l l

I condensate pump trips.

The loss l l

1 l

l l Of the condensate pumps caused a.I l

l l reactor vessel low water level l

I i

I automatic scram.

Co rrec t ive l

l actions were to complete the fill I l or the instrument reference legs l i

i l

I l (which had begun prior to the l

l I

l trips) and to revise operator l

1 l

l 1.

I a la rm response instructions to l

(

l improve operator response to I

this shutdown.

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1 I

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u l

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1 2

3 4

F: Fo rced Reason:

Method:

Exhibit C - Instructinns S: Scheduled A-Equipment Failure 1-Manual for Preparation of Data (Explain) 2-Manual Sc ra m Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Report (LER)

C-Refueling 4-Continued file (NUREG-Ol61)

D-Regulatory Restriction 5-Reduced load E-Ope ra to r T ra i n i ng &

6-Other Licensing Examination F-Adm in i s t ra t ive 5

G-Ope ra t iona l E rro r Exhibit 1-Same Source

( Exp l a i n )

H-Other (Expla in)

?

t

Atttchment to AECM-86/00f0 4

UNI T SitVTDOWNS AND POWER REDUCilONS DOCKET NO.

SfL-416 DATE 02/01/D.6 COMPLETED BY J.

G d egale TELEPHONE 601-969-2585 l'

Method of Licensee Cause & Corrective No.

Date Type Du ra t ion Reason Shutting Down" Event System ' Component Action j

(1)

Ifours (2)

Reactor Report #

Code Code Prevent Recurrence l

(3)

(4)

($)

_____I I

?86-01 01/01/86 F

17.8 G

3 86-001 ZZ 22777 The reactor automatically scramed due to low reactor water level.

IDuring a reactor sta rtup, the H

l reedwater system discha rge pressure i

became insufficient to overcomo I

reactor pressure causing the I

reactor water level to drop to the I

ilow leve* trip.

A Stuck pen on the

, water level recorder had led the l

operator to believe water level was H

l

. normal.

Corrective actions include l

ll t revisions to Ala rm Response linstructions and training on the l

l ll luse or redundant l

l instruments.

l I

l ll l

l 1

I 1

1 1

I 1

1 2

3 4

i F: Fo rced Reason:

Method:

Exhibit G - Instructions S: Scheduled A-Equipment Failure 1-Manual for Preparation of Data (Explain) 2-Manual Sc ram Entry Sheets for Licensee B-Ma intenance or Test 3-Automatic Scram Event Report (LER)

C-Refueling 4-Continued Filo (NUREG-0161) l D-Regula tory Restriction 5-Reduced load l

E-Ope ra to r T ra i n i ng &

6-Other Licensing Examination l

F-Adm i n i s t ra t i ve 5

l G-Ope ra t i ona l E rro r Exhibit 1-Same Source (Explain) l H-Other ( Expla in)

"In accordance with NUREG 1022 J14AECM86020701 -6

e Att:chment t2 AECM-86/0340 UNIT SHUTDOWNS AND POWER REDUCTIONS i

DATE 02/03/86 COMPLETED BY J. C _9tgare m

TELEPHONE 601-969-2585 l

l l

l l

l Method of Licensee Cause & Corrective l

No. 1 Date Type Du ra t ion Reason : Shutting Down Event System Component Action (1) l Hours (2)

Reactor Report #

Code Code H

Prevent Recurrence l

l (3)

(4)

(5)

H l

l I

86-02 01/10/86 S

I 0.0 F

5 N/A ZZ ZZZZZ Planned administrative power i

reduction for economic and load dispatch considerations.

I 11 86-03 01/22/86' F

35.4 H

3 86-003 ZZ I

ZZZZZ The reactor automatically scrammedu I

l due to a generator load reject H

l l Signal, A grid phase dif ferential I

I l

1 occurred while restoring power i

i f rom the pInnt to a pa rticula r i

4 system grid conneciton. The l

l l

l generator output oscillated l

t H

l l causing the load reject relay to i I

actuate.

The load reject and l

ll h

reactor trip interface design willi l

l 1

I be reviewed to determine if an I

acceptable alternative desian i

I exists to alleviate reactor trips l resulting from a load reject.

l ll l

1 2

3 4

F: Fo rced Reason:

Method:

Exhibit G - I nst ruct ions S: Scheduled A-Equipment Failure 1-Manual for Preparation of Data (Explain) 2-Manual Sc ram Entry Sheets for Licensee B-Maintenance or Test 3-Automatic Scram Event Report (LER)

C-Refueling 4-Continued File INUREG-0161)

D-Regulatory Restriction 5-Reduced load E-Operator Training &

6-Other Licensing Examination F-Administrptive 5

G-Operationa l Error Exhibit 1-Same source (Explain)

H-Other (Explain)

  • In accordance with NUREG 1022 J14AECM86020701 - 10

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Attachment to UNIT SHUTDOWNS AND POWER REDUCTIONS AECM-86/0040 INSTRUCTIONS This report should describe al! ;Pnt 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 signiGeant dips in avera;e power levels. Each signi-ficant reduction in power level (greater than 20% reduction LICENSEE EVENT REPORT ar.

Reference the appbcable 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 />) reportable occurrence pertaming to the outage or power should be noted, even though the umt may not have been reduction. Enter the first four parts (event year, sequential l

shut down completely. For such reductions in power lesel, report number, occurrence code and report type) of the five the duration should be listed as zero.the method of reduction part designation as desenbed in item 17 of instructions for should be hsted 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 snould be used to provide any needed nplanation to fully further m, vestigation may be required to ascertam whether or desenbe the circumstances of the outage or power reduction.

n t a reportable occurrence was mvolved.) 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 a signed to each shutdown or sigmficant reduction m power noted as not applicable (N/A).

for that calendar year. When a shutdown or significant power reduction begms m one report penod and ends m another, SYSTEM CODE. The system m which the outage or power an entry should be made for both report periods to be sure reduction originated should be noted by the two digit code of all shutdowns or significant power reductions are reported.

Exhibit G Instructions ror Preparation of Data Entry sheets Until a unit has achieved its first power generation, no num-f r Licensee Event Repo-t (LER) Fde (NUREG4)l61).

ber should be assigned to each entr).

Systems that do not ht any existing code should be designa-ted XX. The code ZZ should be used for thosa 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 COMPONENT CODE. Select the most appropriate ramponent as 770814. When a shutdown or significant power reduction from Exhibit I Instructions for Preparation of Date Entry begmsin one report period and ends in another, an entry should Sheets for Lisensee Event Report (LER) File (NUREGE61 h be made for both report penods to be sure all shutdowns using the following entieria:

or significant power reductions are reported.

TYPE. Use "F" or "S" to indicate either " Forced" or " Sche-duled." respectively, for each shutdown or sigmficant 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 mitiated by no later than the weekend fouowmg discover) component.

of an off normal condition. It is recognued that some judg-ment is required m categonang shutdowns in this way. In C.

If a chain of fattures occurs, the first component to mal-general, a forced shutdown is one that would not hase been function should be hsted. The sequence of events.mclud-completed in the abserve of the condition for w hich corrective ng the other components which fail, should be desenbed action was taken.

under the Cause and Corrective Action to Prevent Recur-rence column.

j DURATION. Self-explanatory. When a shutdown extends beyond the end of a report penod. count only the time to the Components that do not fit any existing code should be de-signated XXXXXX. The code ZZZZZZ should be used for end of the report penod and pick up the ensuing down time m the fouowing report penods. Report duration of outages events where a component designation is not applicable.

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

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total outage hours plus the hours the genera-RENCE. Use the column in a narrative fashion to amphfy or tor was on hne should equal the gross hours m the reportmg explain the circumstances of the sht tdown or power reduction.

penod.

The column should include the specific cause for each shut.

down or significant power reductwn and the immediate and REASON. Categonic by letter designanon in accordance ontemplated long term correctise action taken. if appropri.

with the table appearmg on the report form. If category 11 must be used. supply bnet comments.

ate. This column should also be used for a desenption of the major safety related corrective mamtenance performed dunnp METHOD OF SHUTTING DOhN Tile REACTOR OR the outage or power reduction includmg an identification of REDUCING POWER.

Categorue by number designanon the entical path actmty and a report of any smgle release et radioactivny or smgle radiation exposure spectfically assoa I Note that this ditters f rom the Edison Liectne Institute ated wnh the outage which accounts for more than 10 percent teel) definitions of " Forced Parti.si Outage" and " Sche.

of the aHowable annual values JuleJ Partial Outagef F m these termx 1.1.I u>cs a shange of For long textual reports continue narrative on separate paper

.0 M% as the break pomt f or larger power reactors 30 MW and referense the shutdow n or power reduction im tha is int sinJU J shJnpc to wJflJH1 L'\\plJrldllittL nJrrJ!ive (O T

_,.E--._----.-_--

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

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MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi EsRalhMiddB P. O. B OX 16 4 0. J A C K S O N, MIS SIS SIP PI 39215-1640 February 14 1986 NUCLE AR LICEN$1NG & 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

Dear Mr. Taylor:

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/L-835.0 Monthly Operating Report AECM-86/0040 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 January, 1986 (attachment).

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

Yours truly, L. F. Dale Director WEC/JGC:dmn Attachment cc:

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

Mr. T. H. Cloninger (w/a)

Mr. R. B. 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 d

[J,P Chief (w/2)

Office of Resource Management f

U. S. Nuclear Regulatory Commission 3 I Washington, D. C.

20555 J14AECM86020701 - 1 Member Middle South Utilitie.s System