ML20027C525

Monthly Operating Rept for Sept 1982

ML20027C525
Person / Time
Site:	Grand Gulf
Issue date:	10/15/1982
From:	Richardson J MISSISSIPPI POWER & LIGHT CO.
To:
Shared Package
ML20027C522	List: AECM-82-480, Forwards Monthly Operating Rept for Sept 1982 ML20027C525
References
NUDOCS 8210180109
Download: ML20027C525 (8)

Text

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Attachm:nt AECM-82/480 Page 1 of 7 i

4 OPER ATING DATA REPORT DOCKET NO. 50-416 I

DATE 10/15/82 COSIPLETED IlY J. D. Richardson TELEPilONE 6ni_q69-2630 i

OPER ATING STA IUS

l. Unit Name: Grand Gulf Nuclear Station N"

2. Reporting I'eriod: September 1982

3. Licensed Thennal Power (Sihti:

191 1372.5

4. Namepbre Rating (Grow 31We):

1250

5. Design Electrical Rating (Net 31We):

N/A

6. Stasimum Dependable Capacity IGrow SlWe):

7. Stasimum Dependable Capacity INel 31We):

N,fA

8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Imt Repmt. Gise Reasons:

N/A

9. Power Level In Which Restricted. lf Any (Net SlWer N/A

10. Reasons for Restrictions. lf Any:

as restricted by O. L. NPF-13 as 1.tsted in 3.0 above.

This Stonth Yr.-to Date Cumulatise 0

0 0

I1. Ilours in Reporting Period 0

0 0

12. Number Of flours Reac:or was Critical 0

0 0

13. Reactor Rewne Shutdown llour,

14. Ilours Generator On-Line 0

0 0

0 0

0

15. Unit Rewne Shutdown flour,

16. Grow Thermal Energy Generated 131Will 0

0 0

17. Gross Electrical Energy Generated t \\lhill 0

0 0

4 Ih. Net Electrical Energy Generated 151%III 0

0 0

I l

19. Unit Senice Factor N/A N/A N/A i

20. Unit Asailability Factor N/A N/A N/A N/A N/A N/A

21. Unit Capacity Factor iUsing SIDC Neti

22. Unit Capacity I' actor iUsing DER Net p N/A N/A N/A N/A N/A N/A

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 SlonthsiT)pc. Date.and Duration of Each t:

N/A

25. If Shut Down \\t End Of Report Period.latimated Date of Startup:

N/A 26 Units in Test Status (Prior io Commercial Operation):

Iorecast Achiesed INiil \\ L CRillCAlli y 8/14/82 8/18/82 2/83 INill \\ L LLECT RICIIY I

Cost \\ll RCI \\1. Orl'R A IION 8/83 8210180109 821014

("I773 PDR ADOCK 05000416 R

pcq

At tachmettt AECM-82/480 Paga 3 of 7

19. UNIT SERVICE FAC10R. Compute by dividing hours the generator was on line (item 14) by the gross hoursin the reporting period (item II). Express as percent to the nearest tenth of a percent. Do not include reserve shut.

down hours in the c. 8:ulation.

20.' UNIT AVAILAhlLITY FACTOR. Compute by dividing the unit available hours (item 14 plus item 15) by the gross hours in the reporting period (item 1I). Express as percent to the nearest tenth of a percent.

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

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

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 $) for maximum dependable capacity.

23. UNIT FORCED OUTAGE RATE. Compute by dividing the total forced outage hours (from the table in Unit i

Shutdowns and Power Reductions) by the sum of hours Fenerator on line Otem 14) plus :otal forced outage hours (from the table in Unit Shutdowns and Power Reductions).

lixpress as percent to the nearest tenth of a percent.

24. SilUTDOWNS SCIIEDULED OVER NEX16 NIONTils (TYPE. DATE. ANI) DURATION OF EACil). Include type (refueling mamtenance, 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 antil the actual shutdown occurs.

25. Self<xplanatory.

26. Self. explanatory. Note, however, that this information is, request _ed for all tmits in startup and power ascension test status and is not required for units aircady in com-

~

mer cial operation.

TEST STATUS is defined as that period followmg ini.

tial cntieahty during whhh the unit is tested at succes.

sively higher outputs, culmsating with operation at full power for a sustamed period and completion of war-ranty runs. Following this phase, the unit is generally considere i by the utihty to be availah!c for commercial operation.

Date of C0\\lNIERCIAL OPERAIl0N is defined as the J.'te that the i;mt was dedared by the utility owner to be available for the regular production of eleetncity, usually related to the satisfactory completion of quali.

ficatmn tests as specified in the pmchase contract and to the accounting policies and prastices of the utility.

Attachment AECM-82/480 Page 4 of 7 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO, 50-416 UNIT I

DATE 10/15/82 COMPLETED BY J. D. Richardson TELEPHONE 601-969-2630 MONT13 September DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) 1MWe-Net) l No Power Generated l7 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 15 31 16 INSTRUCTIONS On this format. list the average daily unit powei lesel m MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77 )

Attachment AECM-82/480 3e Page 5 of 7 UNIT SIIUTDOWNS AND POWER REDUC 110NS DOCKET NO.10-416 UNIT NAME crand culf h elear

~

DATE - 10/15/82

, Station REPORT MONTH September COMPLETED BY

.1 D. Richardson TELEPHONE 601-969-2630 3 e.o 2 E

=

es 5d li'*"S**

5't Cause & Conective

'h.

k _5 5

?3m No.

Dase Event g7 gg 4c,;o,,,

s' 5 3 0

5 o

g; a g Report a mo Prevent Recurrence CO 6

N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A 3

i 9

I 2

3 4

F: Forced Reason:

Method:

Exhibit G - Inst ructions S: Scheduled A-rquipment Failure (Explain) 1-Manual for Preparation of Data H.\\taintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Autonatic Scram.

Event Report (LER) File (NUREG-D-Regulatory Restiictson 4-0.her (Explain) 0161)

E-Operator Training & License Examination F-Administrative

}

5 G-Operational Error (E xplain )

Exhibit I - Same Source (9/77) iI4)ther (Explain) 4

4 UNIT SHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe gli p' ant 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-4 Scant reduction in power level (greater than 207c 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 />)

'cPortable occurrence pertaining to the outage or power should be noted, even though the unit may not have beca reduction. Enter the first four parts (event year, sequential l

shut down completely. For such reluctions in power le.el, rep rt number, occurrence code and report type) of the five the duration should be listed as rero, the method of ret ueti >n p it designation as described in item 17 of Instructions for should be hsted as 4 (Other), and the Cause and Corrc tiva Preparation of Data Entry Sheets for Licensee Event Report Action to Prevent Recurrence column should explain. l'e (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 power rmuction.

n t a reportable occurrence was involved.) If the cutage or power reduction will not result in a reportable occurrence.

NUMitER. This colunm 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 outag or power reduction begins in one report period and ends in another.

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 for Preparation of Data Entry Sheets Until a unit has achieved its first power generation, no num-f r Licensee Event Report (LER) File (NUREGoi61).

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 -lay. 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 Entr3 beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (I FR) 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 riot a component failure, use the related component:

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

of an oif-normal condition. It is recognized that some judg-ment is required m 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 hsted. The sequence of events,melud-completed in the absence of the condition for which corrective ing the other components which fad, should be descnbed action was taken.

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

DURATION. Self-explanatory. When a shutdown extends beyond 'he end of a report period, count only the timc to the Components that do not fit any existmg code should be de-end of the report period and pick up the ensuing down time signated XXXXXX. The code ZZZZZZ should be used for in the following report periods. Report duration of outages events where a component designation is not apphcable.

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

The sum of the total ouine 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 amphfy or penod.

explam the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut.

REASON. Categorize h3 letter deugnation in accordance down or significant power reduction and the immediate and wnh the table appearing on the report form. If category 11 ontemplated long term corrective action taken, if appropn.

must be used supp!> bnet comments.

ate. This column should also be used for a description of the maior safety related corrective maintenance performed dunng METilOD OF SilUTTING DOWN Tile REACTOR OR outap m power reduction including an identification of t

REDUCING POWER.

Categorize by number designation the entical path activity and a report of any smgle release of radioactivity or smgle radiation exposure specifically associ-INote that this ditTen f rom the I dison Ilectric Institute ated with the outage which accounts for more than 10 percent tEl'I) delimtions of " Forced Partial Outage" and "Sehe.

of the allowable annual values.

duled Partial OutJge.' l'or these telm). 1.51 ubeh a UJnge of For long testual reports continue narrative on separate paper 30 MW as the break pomt. I ot tarpei powei reactors. 30 MW and reterence the shutdown or power reduction los tins is toa small a change to wanant esplanation.

narrative.

pm

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Actshement AECM-82/480 Page 6 of 7 Docket No. 50-416 Date 10/15/82 Completed by:

J. D. Richardson

. Telephone: 601-969-2630 OPERATING DATA REPORT SUPPLEMENTAL INFORMATION i

A temporary alteration was made on September 27, 1982, to the Liquid Radwaste System to allow discharge in excess of 35 gpm, after having been reviewed and approved by the Plant Safety Review Committee (PSRC). The 4

following information is submitted pursuant to Technical Specification 6.15.1:

6.15.1.

a.

An evaluation was conducted and a determination was made in

'conformance with 10 CFR 50.59 that the temporary jumpering and resetting of interlocks to allow discharging non-radioactive water through the liquid radwaste line in excess of 35 gpm will not.

increase the probability of an occurrence or the consequences of an accident previously evaluated in the FSAR as discharge flow. This alteration is encompassed by the FSAR Accident Analysis. The discharge is in conformance with the National Pollution Discharge j

. Elimination System requirements.

i; b.

The reason for the temporary change is to allow the discharge of quantities of non-radioactive water, in excess of the flow rates presently allowed by the interlocks. Non-radioactive water, slightly contaminated with glycol, held in the radwaste inventcry, should be reduced in volume by discharging up to 3 million gallons having a maximum concentration of 20 ppm biodegradable organic.

matter. Dilution would occur by discharging to the river at the rate of approximately 90 gpm.

c.

The temporary change removes, by means of jumper cables,' the low-flow interlock'for cooling tower dilution flow of 11,300 gpm and raises the maximum radwaste discharge flow from 35 to 90 gpm. The radwaste discharge flow and dilution flow was calculated using the

-Offsite Dose Calculation Manual (ODCM) as required by Technical Specifications (Tech. Spec. 3.3.7.11, LCO).

d.

It is anticipated that no water with significantly above background i

detcetable amounts of radiation, as determined by sampling, will ba discharged. The predicted releases are negligible and within the limits addressed in the FSAR.

e.

Since non-radioactive water will be discharged, there are no significant changes-in expected maximum exposures to individuals in unrestricted areas, nor significant differences from exposures previously calculated in the FSAR.

f f.

Since no prior release data of significant quantities is available, this non-radioactive discharge cannot be meaningfully compared, a-

[^...*

Attchement AECM-82/480 Page 7 of 7 Docket No. 50-416 Date 10/15/82 Completed by:

J. D. Richardson Telephone: 601-969-2630 g.

The change in exposure to plant operating personnel will be negligible since it is anticipated that no water with significantly above background radiation will be discharged.

h.

The change was reviewed and found acceptable by the PSRC as shown by approval signature on the 10 CFR 50.59 evaluation form retained in PSRC files, and as addressed in the notes of the PSRC meeting considering this temporary alteration.

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