ML20069D362

Monthly Operating Rept for Aug 1982

ML20069D362
Person / Time
Site:	Grand Gulf
Issue date:	09/15/1982
From:	Richardson J MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20069D358	List: AECM-82-406, Forwards Monthly Operating Rept for Aug 1982 ML20069D362
References
NUDOCS 8209210057
Download: ML20069D362 (8)

Text

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Attachment AECM-82/406 Page 1 of 8 OPERATING DATA REPORT DOCKET NO. 50-416 DATE 9/15/82 CO\lPLETED BY LD. Richardson TELEPil0NE 601-969-2510 OPERATING STATUS Grand Gulf Nuclear Station Notes

1. Unit Name:

2. Reporting Period: August 1982 191

3. Licensed Thennal Power 4%IWt): _

4. Nameplate Rating IGross 51We):

5. Design Electrical Rating (Net 5 thel: 1250

6. Alasimum Dependable Capacity (Gross alWe): N/A

7. Niasimum Dependable Capacity (Net SlWe): N/A S. If Changes Oecur in Capacity Ratings (items Number 3 Throu::h 7)Since Last Report. Gise Reasons:

N/A

9. Power Lesel lo Which Restricted. lf Any (Net alwc3 N/A

10. Reasons For Restrictions.'If Any: as restricted by 0.L. NPF-13 as listed in 3.0 above.

This alonth Yr. to Date Cumulatise

11. Ilours in Reporting Period 0 0 0

12. Number Of liours Reactor was Critical 0 0 0

13. Reactor Rewne Shutdown llour, 0 0 0

14. Ilours Generator On-Line 0 0 0

15. Unit Rewne Shutdown flours 0 0 0

16. Gross Thermal Energy Generated 1.\lWill 0 0 0

17. Grow Electrical Energy Generated t\lwill _ _ ___

0 0 0 ih. Net Electrical Energy Generated (51% til 0 _0 0

19. Unit Senice Factor N/A N/A

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20. Unit Asailability Factsg ,

21. Unit Capacity Factor (Using .\lDC Net t N/A

22. Unit Capacity Factor (Using DER Neil N/A

23. Unit Forced Outage Rate N/A

24. Shutdowns Scheduled Oser Nest 6 Stonths(T)pe.Date,and Duration of Each1:

N/A 25.-If Shut Down at End Of Report Period.Estim:ced Date of Startup: N/A

26. Units in Test Status tPrior to Commercial Operation): Forecast Achiesed INill \ L CR111 Call 1 Y 8/14/82 8/18/82 INill \L LLECTRICITy 2/83 CO\l\1LRCI \L OPER AIlON 8/83

- l 8209210057 820915 PDR ADOCK 05000416 p,j77, R PDR

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Attachtnent -

Aecm-82/406

1. E' INSTRUCTIONS FOR COSIPLETING OPERATING DATA REPORT Thn repon 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>truction corresponds to the item number of the report format.

i UNIT NA\lE. 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 Grst. 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.

1. LICENSED tiler 51AL P0hTR (SIW,)is the maximum thermal power, expressed in megawatts. currently auth- 12. NU5tBER OF fl0URS REACTOR WAS CRITICAL.

oriecd by the Nuclear Regulatory Commission. Show the total number of hours the reactor was critical 4.1IASIEPLATE RATING (GROSS SIW, L The nameplate mwer designation of the turbine generator in megavoit 13. REACTOR RESERVE SilUTDOWN 110URS. The total enteres tStVA) times the nameplate power factor of the number of hours during the gross hours of reporting turbme generator. period that the reactor was removed from service for .

administrative or other reasons but was available for

5. DESIGN ELECTRICAL RATING (NET SIW e ) is the operation.

nominal net electrical output of the unit specified by the utility and used for the purpose of plant design- 14. Il0URS GENERATOR ON LINE. Also called Service llours. The total number of hours expressed to the near-

6. SI AXI51U51 DEPENDABLE CAPACITY (GROSS 51We ) est tenth of an hour during the gross hours of the re-is the gross electrical output as measured at the octput 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 strictr a seasonal conditions. in Unit Shutdowns for the generator outage hours,should

7. SIAX151U51 DEPENDABLE CAPACITY (NET 51We 1.

Slaximum dependable capacity (pross) less the normal 15. UNIT RESERVE SliUTDOWN 110URS. 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 re s ns but was available for operation.

9. POWER LEVEL TO WHICil RESTRICTED, IF ANY (NET 5tW,). Note that this item is applicable only if 16. GROSS tiler 51AL ENERGY GENERATED (NIWil).

restrictions on the power level are in effect. Short term 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.

n 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 (51Will.

" Operating Plant Status Report" are primarily interested The electrical output of the unit measured at the output in energv'actually fed to the distnbution system. it is temiinals of the turbine. generator during the gross hours requested that this figure be expressed in $1We Net in of the reportmg period, expressed in megawatt hours (no spite of the fact that the Ogure must be de ived f rom decimals).

SIWt or percent power.

18. NET ELECTRICAL ENERGY GENERATED 151Wil).

10. REASONS FOR RESTRICTIONS. IF ANY. If item 4 The gross electrical output of the unit measured at the is used, item 10 should explain why. Brief narrante 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 restnetions are self-imposed or are regulatory reporting period expressed in megawatt hours. Negative requnements. Be as specifie as possible within space hmi- quantities should not be used. If there is no net positive iations. Plants in startup and power ascension test phase value for the period, enter zero (no decimals).

should be identined here.

11. IiOURS IN REPORTING PERIOD. I or 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 begmmng of the penod or the Orst electrical produe. N/A in the current month column. These Gve 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 m commercial operation. The cumulative For umts in commercial operation at the end of the Ogures m the second and thud columns should be based period, the gross hours from the beginmng of the penod on commercial operation as a starting date, 4o1776

Attachment Accm-82/406 Page 3 of 8

19. UNIT SERVICE FACTOR. Compute by dividing hours the generator was on line (item 14) by the gross hoursin 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 i1). Express as percent to the nearest tenth of a percent.

21. UNIT CAPACITY FACTOR (USLNG MDC NETL Com.

pute by diviJing 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 (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 P? ductions) by the sum of hours generator on ime titem 14) plus total forced outage hours (from the table in Urit 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. .

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

l 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.

l TEST STATUS is defined as that period following ini-tial criticality during which the unit is tested at succes-sisely higher outputs, culminating with operation at full power for a sustained period and completion of war-ranty runs. Following this phase. the umt is generally considered by the utility to be availab!c for commercial operation.

Date of CO\lMERCIAL OPERATION is defined as the date that the umt. was declared by the utihty owner to be available for the segular production of electricity, usually related to the satisfactory completion of quali-l tication tests as specilled in the purchase contract and to

! the accounting pohcies and practices of the utility.

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.'ttschment A

AECM-82/406 Pege 4 of 8 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-416 UNIT I DATE 9/15/82 COMPLETED BY J.D. Richardson TELEPHONE 601-969-2630 MONTil August DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL IMWe Net) lMWe-Net i I No Power Generated 37 2 18 3 19 4 20 5 21 6 22 7 23 8 24 9 25 10 26 11 27 12 28 13 29

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30 _- . . - .

15 31 16 INSTRUCTIONS On this format list the average daily unit power leselin MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt (9/77 )

O

Page 5 of 8 DOCKET NO. 50-416 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Grand Gulf helear Sta.:

DATE 9/15/82 Austust COMPLETED BY .T _ n. nichnrdaon REPORT MONTil 601-969-7630 TELEMf0NE e.

_ E c

, .5 ? "h j E3 Licensee ,E ,, [*, Cause & Corrective No. Date g 3g 4 ,g g 5 Event g? g3 Action to

• f~ $ j di g Report # in U g' Prevent Recurrence 6.

f N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 4

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I 1 2 3 4 F: Forced Reason : Method: Exhibit G - Instructions S: Scheduled A. Equipment Failure (Explain) 1 -Manual for Preparation of Data B41aintenance of Test 2-Manual Scram. Entry Sheets for Licensee

• C-Refueling _

3 Automatic Scram. Event Report (I.ER) Fde (NURI&

D-Regulatory Restriction 4-Other (Explain) 01611 E-Operator Training & License Examination F Administrative 5 G-Operational Error (Explain) . Exhibit 1 - Same Source 19/77) 11-O:her (E xplain) 9

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At techtnent

• AECM-82/406 Page 6 of 8 UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should desenbe all plant shutdowns during the in accordance with the table appearmg cn 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 appheable 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 />) 'eportable 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, rep rt number, occurrenc 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 listed as 4 (Other), and the Cause and Corrective Prep ration 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 colurnn immediately evident for all such shutdowns, of course, since should be used to provide any needed explanation to fully further mvestigation may be required to ascertain whether or describe the circumstarices 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.

NUhlHER. Ttus 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 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, SYSTESI CODE. The system in which the outage or power an entry should be made for both report periods to be sure reduction originated sh'o uld be noted by the two I 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 ucensee 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 C051PONENT 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 (NUREG-0161).

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

or significant power reductions are reported.

r A. If a component failed,use the component directly involved.

' TYPE. U>e "F" or "S" to indicate either " Forced" or " Sche.

duled," respectively, for each shutdown or significant power IL 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 categorizmg shutdowns 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-function should be listed. The sequence of events. melud.

completed in the absence of the condition for wiuch corrective ng 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 cxtends 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 penod and pick up the ensuing down time signated XXXXXX. The code ZZZZZZ should be used for m the following report penods. Report duration of outages events where a component designation is not applicable.

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

The sum of the total outage hours plus the hours the genera- CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-tor was en line should equal the gross hours in the reportmg RENCE. Use the co!umn 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.. Categorue b) letten designation in accordance down or significant power reduction and the immediate and with the table appearing on the report form. If 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 major safety-related corrective maintenance performed dunng SlETil0D OF SilUTTING DOWN Tile REACTOR OR the outage or power reduction including an identification of REDUCING POWER. Categorue by number designation the critical path actmty and a report of any single release of radioactivity or single radiation exposure speettically assom INote that this ditfers trom the Edison Ileerric Institute ated with the outage which accounts for more than 10 percent (EEI) dermitions of " Forced Partial Outage" and " Sche. of the allowable annual values.

duled Partial Out.igef I or these term . l.1 I uses a change of For long textual reports continue narrative on separate pare 30 S!W as the break pomt. I or larger powet reactors. 30 hlW and reference the shutdown or power reduction for this i% tim hmJll a shange to wairant explanation. narrative.

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Attachment AECM-82/406 Page 7 of 8 Docket No. 50-416 Date 9/14/82 Completed by: J. D. Richardson Telephone 601-969-2510 OPERATING DATA REPORT SUPPLEMENTAL INFORMATION As referenced in letter dated August 13, 1982 (AECM-82/348) MP&L reported that a temporary change to the Grand Gulf Nuclear Station solid radwaste system was made on or about June 23, 1982 in accordance with Technical Specification 3.11.3. As indicated in the aforementioned letter, additional information would be provided in the August Monthly Operating Report.

In accordance with the Grand Gulf Technical Specifications 6.15.1, licensee initiated major changes to the radwaste system shall be reported to the Commission in the Monthly Operating Report. The discussion of each change shall contain:

a. A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59;

b. Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information;

c. A detailed description of the equipment, components and processes involved and the interfaces with other plant systems;

d. An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;

e. An evaluation of the change which shows the expected maximum exposures to individual in the unrestricted area and to the general population that differ from those previously estimated in the license application and amendments thereto;

f. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releaset for the period prior to when the changes are to be made;

g. An estimate of the exposure to plant operating personnel as a result of the change; and l h. Documentation of the fact that the change was reviewed and found acceptable by the TEC.

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Attachnant AECM-82/406 Page 8 of 8

RESPONSE

a. A summary evaluation has revealed that the modification to the radwaste solidification system does not 1), increase the probability of an occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report 2, does not create the possibility for an accident or malfunction of a different type than any evaluated previously in the safety analysis report and 3), does not reduce the margin of safety as defined in the basis for any technical specification,

b. The permanent plant radwaste solidification system could not be readied for use in concert with the present schedule for operation because changes to the permanent plant radwaste solidification system based on vendor recommendations were incomplete. To support plant operations in the interim, a portable solidification system was placed in service,

c. A detailed description of the portable radwaste solidification is presented in the proprietary Topical Report CNSI-2 Revision 1 (4313-01354-01) entitled " Mobile Cement Solidification System" submitted to the Commission March 22, 1982 by Chem-Nuclear Systems, Inc. (CNSI).

d. Section 9.0 of the Topical Report referenced in c. above and answers to the staffs questions 23 and 31 pertaining to the topical report and submitted to the staff on June 23, 1982 provide details of a postulated worst case failure of *.he Mobile Solidification Systems. Comparison of this CNSI postuleted event to events analyzed in the Grand Gulf Final Safety Analysis Report (FSAR) sections 15.7.2 and 15.7.3 indicate the FSAR analysis bounds the CNSI event. Therefore, use of the CNSI Mobile Solidification System will not result in releases which differ from those previously predicted nor will there be a change to the maximum exposure to an individual in the unrestricted area.

e. Refer to the response in part d. above,

f. This question does not apply since there is no release data to provide a comparison to the predicted releases.

g. An estimate of the exposure to plant personnel as a result of the l use of the CNSI Mobile Solidification System is best explained in Section 4.5 of the referenced Topical Report and the response to the staff's question number 4 submitted by letter on June 23, 1982.

l h. The PSRC reviewed the CNSI system on June 23, 1982 and approved the use of the system on June 24, 1982. This approval is documented in the PSRC meeting ninutes.

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