ML20073K079

Monthly Operating Rept for Mar 1983

ML20073K079
Person / Time
Site:	Grand Gulf
Issue date:	04/14/1983
From:	Richardson J MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20073K075	List: AECM-83-0235, Forwards Monthly Operating Rept for Mar 1983 ML20073K079
References
NUDOCS 8304190523
Download: ML20073K079 (8)

Text

Attachm mt to

.,. *: AECM-83/0235 Page 1 of 8 OPERATlhG DATA REPORT DOCKET NO. 50-416 DATE 4-14-8'l COSIPLETED BY T- n Rfchardson TELEPilONE 601-969-2630 OPERATING STATUS Grand Gulf Nuclear Station Notes

1. Unit Name:

2. Reporting Period: March 1983

3. Licensed Thennal Power (SIWt): 191 -

4. Nameplate Rating (Gross .\lWe): 1372.5

5. Design Electrical Rating (Net AlWe): 1250

6. .\tasimum Dependable Capacity (Gross 51We): N/A

7. Af asimum Dependable Capacity (Net 51We): N/A S. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:

N/A

9. Power Level To Which Restricted. lf Any (Net alwel: N/A

10. Reasons For Restrictions.lf Any: As restricted by O. L. NPF-13 as listed in 3.0 above.

This alonth Yr. to.Date Cumulative

11. Ilours in Reporting Period 0 0 _

0

12. Number Of flours Reactor Was Critical 0 0 0

13. Reactor Reserve Shutdown llours 0 0 0

14. Ilours Generator On-Line 0 0 0

15. Unit Reserve Shutdown flours 0 0 0

16. Gross Thermal Energy Generated (SlWil) 0 0 0

17. Grow Electrical Energy Generated I.\lWil) 0 0 0

18. Net Electrical Energy Generated (51Will 0 0 0

19. Unit Service Factor N/A N/A N/A

20. Unit Availability Factis N/A N/A N/A

21. Unit Capacity Factor iUsing SIDC Net) N/A N/A N/A

22. Unit Capacity Factor (Using DER Net) N/A N/A N/A 23.' Unit Forced Outage Rate N/A N/A N/A

24. Shutdowns Scheduled Over Next 6 51onths (Type. Date.and Duration of Each):

N/A

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

26. Units in rest Status (Prior io Commercial Operation): Forecast Achiesed INITIA L CRITICALITY 8/14/8_2 8/18/82 INITI \ L ELECTRICITY 6/83 CO\l\lERCIAL OPERATION 12/83 8304190523 030414 PDR ADOCK 05000416 R PDR to/77 )

Attachment to' AECM-83/0235 INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORyage 2 of 8 This report should be furnished each month by licensees. The name and telephone number of the preparer should be provided in the designated spaces. The mstructions 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 hauts should be made in the data are presented. which a change from standard to daylight savmgs time (or vice versa) occurs,

3. LICENSED THERMAL POWER (MW,)is the maximum thermai power, expressed in megawatts currently auth. 12. NUMBER OF HOURS REACTOR WAS CRITICAL.

ori/ed by the Nuclear Regulatory Commission. Show the total number of hours the reactor was critical during the gross hours of the reporting period.

4. NAME? LATE RATING (GROSS MW,). The nameplate -

power designation of the turbine genetator in megavoit 13. REACTOR RESERVE SilUTDOWN llOURS. The total

.enperes (MVA) times the nameplate power factor of the number of hours during the gross hours of reporting turbine generator. period that the resetor was removed from service for administrative or other reasons but was available for

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

nominal net electrical output of the unit specified by the utility and used for the purpose of plant design. 14. IlOURS GENERATOR ON-LINE. Also called Service llours. The total number of hours expressed to the near-

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MWe ) .

est tenth of an hour during the Fross 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- n Unit Shutdowns for the generator outage hours,should equal the gress hours in the reporting period.

7. MAXIMUM DEPENDABLE CAPACITY (NET MW,).

Mnimum dependable capacity (gross) less the normal 15. UNIT RESERVE SilUTDOWN ilOURS. The total num-station service loads.

ber of hours expressed to the nearest tenth of an hour during the gross hours of the reporting period that the S. Self explanatory.

unit was removed from service for economic or similar reas ns but was available for operation.

9. POWER LEVEL TO WHICil RESTRICTED, IF ANY (NET MWe ). Note that this item is applicable only if 16. GROSS TilERMAL ENERGY GENERATED (MWil).

restrictions on the power level are in effect. Short tenn The thermal output of the nuclear steam supply syste n tiess than one month) limitations on power level need during the gross hours of the reportini; period, expressed not be presented in this item.

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 (MWill.

" Operating Plant Status Report" are primarily interested The electrical output of the unit measured at the output l 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 (MWil).

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. Ikief 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 iegulatory 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).

i should be ider.tified here.

11. IiOLRS IN REPORTING PERIOD. For units in power 19 For units still in the startup and power ascension test asces.sion at the end of the penod, the gross hours from 23. phase. items 19-23 should not be computed. Instead.cnter the beginning of the penod 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 .n commercial operation. The cumulative for units in commercial operation at the end of the figures m the second and third columns should be based period, the gross hours from the beginning of the penod on commercial operatmn .n a startmg date.

i 80 rU b t_

Attschment to

. AECM-83/0235 Pegn 3 of.8

19. UNIT SERVICE FACTOR. Compute by dividing hours the generator was on line (item 14) by the gross hours in the reporting period (item iI). 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) b.r the gross. hours in the reporting period (item 1!). 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 11).

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. SilUTDOWNS SCilEDULED OVER NEXT 6 MONTilS (TYPE DATE. AND DURATION OF EACil). 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<xplanatory.

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 asailab!e for commercial operation.

Date of CO\lilERCIAL OPERATION is defined as the date that the unit was declared by the utility owner to be available for the regular production of electricity.

usuall: related to the satisfactory completion of quali-tication tests as specified in the purchase contract and to the accounting pohcies and practices of the utility.

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Atttchm:nt to AECM-83/0235 e

Pcgn 4 of 8 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. ._50-416 IINIT I DATE 4-14-83 COMPLETED BY J. D. Richardson TELEPHONE 601-969-2630 i

MONTil March DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net n (MWe-Net) l No nower nenarated 37 2 18 3 19 4 20 5 21 6 22 7 23 8 24 9 25 10 26 Il 27 12 28 13 29

._ __14 30 IS 31 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.

(9/77 )

c UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-416 UNIT NAME Crand Cn1f m mlear Sta...

DATE 4-14-83 REPORT MONTII March COMPLETED BY J. D. Richardson' TELEPHONE 6n1 469 7619 No. Date g

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Report # 'N U u

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N/A N/A N/A N/A N/A N/A N/A N/A N/A EDN 290 l O i 2 3 4 F: Forced Reason: Method: Exhibit G Instructions um{

o " to S: Scheduled A Equipment Failure (I.xplain) 14fanual B41aintenance of Test 2-Manual Scram.

for Preparation of Data Entry Sheets for Licensee mw C Refueling D Regularory Restriction 3 Autornatic Scram. Event Report (LER) File (NUREG. "E 4-Other ( Explain) 0161)

E Opciator Training & License Fsamination F-Administrati.e 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) lI Other (Explain)

. 1 Attrchment to AECM-83/0235

• UNIT SHUTDOWNS AND POWER REDUCTIONS Paga 6 of 8 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 />) reportable occurrence pertaining to the outage or power should be noted, even though the unit may not have been reduction. Enter the first four parts (event year, sequential shut down completelyl. 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 ecurse, since should be used to provide any needed explanation to fully further investigation may be required to ascertam 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 orsignificant reductionin power n ted 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, $YSTEM CODE. The system in which the outage or power g

an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported. Exhibit G - Instructions for Preparetion of Data Entry Sheets Until a unit has achieved its first power generation, no num- f r Licensee Event Report (LER) File (NUREG-0161).

ber should be assigned to each entry.

Systems that do not 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 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 1 - Instructions for Preparation of Data Entry beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG.0161).

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

or significant power reductions are reported.

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

duled." 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 requiled in categorizing shutdowns in this way. In C. If a chain of failures occurs, the first component to mal.

general, a forced shutdown is one that would not have been function should be listed. The sequence of events,includ-completed in the absence of the condition for which corrective ing the other components which fail, should be described action was taken.

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

DURATION. Self-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 following 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-tor was on line should equal the gross hours in the reporting RENCE. Use the column in a narrative fashion to amplify or period. explain the circumstances of the shutdown or power reduction, The column should include the specific cause for each shut-REASON. Categorize h3 letter designation in accordance wn rsn nt pown r u n and se immdau and with the table appearing on the report form. It. category 11 contemplated long term corrective action taken. if appropri-must be used. supply brief comments. ate. This column should also be used for a description of the or safay-related corrective maintenance performed during METHOD OF SilUTTING DOWN THE REACTOR OR outag or power reduction including an identification oi REDUCING POWER. Cateponte by number designation the critical path activity and a report of any single release radioactivity or single radiation exposure speetfieally associ-INote that this differs from the Edison Elestric Institute ated with the outage which accounts for more than 10 percent (EEI) definitions of " Forced Partial Outage" and " Sche. of the allowable annual values.

Juled Partial Outage? For these tenna. El I uses a change of For long textual reports continue narrattse on separate paper 30 MW as the break pomt. l~or larges power reactors.30 MW and reference the shutdown or power reduction - for thn is toa small a change to wanant esplananon. narrauve.

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. 2 I? , Att."chment to- 'Dockst No. 50-416

., O]jAECM-83/0235s '

Dito: ~4/14/83 .

Completed by: J. D. Richardson Page-7 of 8:

' Telephone: -601-969-2630

' OPERATING DATA REPORT SUPPLEMENTAL 1INFORMATION

- 4 Major- Changes to 'the Radwaste System

, Several: design changes'to the. Grand Culf Nuclear Station Radwaste System are either'in preparation or'have been approved by the Plant Safety Review Committee'(PSRC).during'the' month of March. .The changes will improve opera-bility'and provide the required solidification-functions"for'the orderly startup of Unit.fl.

Although three of the design changes were ' approved by the PSRC during this reporting period, the detailed descriptions and radiological' exposure

-analyses'as requir'ed for.this report will be, deferred and. reported prior to Lascension to 5% power when other key design changes are also approved'and included in the analyses.; Briefly, the approved major design changes include the following:

1. DCP-82/651, Condensate Phase Separator System

A. Description of Change i

This design change provides additional storage capacity to initially hold filter /demineralizer wastes to allow settling time and subsequent decantation of waste water for plant. recycle. - The

, - concentrated slurry will be transferred to the waste storage tanks for solidification. This DCP also' requires the removal of.

- portions of the permanent solid radwaste system to make room for 4

the new condensate phase separator tanks, pumps, separation shield wallsk-instruments, controls,fconduits and associated i appurtenances.

B.. Status .

1. 1 This DCP has been' approved by the PSRC. The system checkout g

following construction is scheduled for completion by 15 July, 1983,

2. DCP-82/607 A. Description of Change This DCP.provides for increasing the maximum discharge rate of

~

liquid radwaste effluent from a maximum of 35 gpm to a flow rate based on the minimum discharge basin dilution flow rate and the

[ actual activity of the effluent stream as. determined by sample analysis from the sample tank. The isolation' valve in the

.'-- effluent line will be relocated farther downstream in the line and the activity sampling point will be located nearer the

}- isolation valve to improve response time and reduce the volume of effluent released in the event that the activity setpoint is exceeded. A low dilution flow interlock will be relocated from the cooling tower blowdown .line to the flow through the 54-inch line from the station to the river.

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W F ~Atitcchment' to; --

Dockat No. 50-416 '

e j "AECM-83/02351 DIts!-l4/14/83

. LPage.8 of 8

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Completed by: J.'~D. Richardson Telephone: 601-969-2630--

B.: Status 1

This DCP has-been approved by the PSRC. The. implementation of

-the change is' scheduled for completion by 1 June,'1983.

l _

3.- DCP-82/650, Radwaste-Transfer Lines-From' Liquid Radwaste Equipment.to Transfer-Station..

A. ' Description of Change

This DCP_ requires modification of the Grand Gulf'radwaste systems-such that liquid radwaste from several storage tanks can be'

' transferred directly to a contractor's temporary radwaste solid-ification station installed in the radwaste building rail / truck s

. hay. iThis DCP.willLalso provide for decantation return from the

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' contractor's: solidification container to;the RWCU phase separation tanks and provide service. air and condensate to backflush the r effluent-lines. This design change also provides for the heat tracing and insulation.oflthe lines-from the waste holding and

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evaporator bottoms tanks to prevent crystalization in the lines.

2 2

B .' Status-

, r.

I '

This DCP has been approved by the PSRC. The design

implementation is scheduled for. completion by 1 June, 1983.

[ -The. major design change not yet approved by the Plant Safety Review Committee

'. .is as follows:

DCP-82/0028.- Installation of a Temporary'Radwaste Solidification System as Provided by a Contractor.

A. Description of Change p

P uA temporary radwaste solidification system as provided by a co'ntractor will be installed .in the rail / truck bay of the rad-' -

waste building and necessary support services supplied. A vent

{' connection from the solidification container will be-provided to the radwaste building ventilation system. Necessary curbing will

-be'provided to encompass the container filling area.

B.. Status-4 This:DCP has not been approved by the PSRC pending completion of j  ; the 10CFR50.59 safety analysis and. final selection of one of the two contractors currently under evaluation. One contractor's j , equipment is.on-site and has been utilized to process non-radioactive liquid' waste (glycol contaminated, floor drains waste).-

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