AECM-84-0071, Monthly Operating Rept for Jan 1984

Monthly Operating Rept for Jan 1984

ML20080T761
Person / Time
Site:	Grand Gulf
Issue date:	01/31/1984
From:	Cesare J, Dale L MISSISSIPPI POWER & LIGHT CO.
To:	Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
AECM-84-0071, AECM-84-71, NUDOCS 8403020047
Download: ML20080T761 (12)

Text

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Attachment to AECM-84/0071 Page 1 of 6 OPERATING DATA RF. PORT DOCKET NO. 50-416 DATE 2-14-84 COMPLETED BY T-c. comare TELEPHONE 6'" -969-2585 OPER ATING STATOS

1. Unit Name:

Grand Gulf Nuclear Station Unit 1 N"k$

2.' Reporting Period: January, 1984

3. Licensed Thermal Power (MWt p: 191

4. Nameplate Rating (Gross MWel: 1372.5

5. Design Electrical Rating iNet MWeI: 1250

6. Masimum Dependable Capacity (Gross MWel: NA NA

7. Masimum Dependable Capacity INet MWe):

S. If Changes Occur in Capacit.s Ratings titems Number 3 Through 7)Since Last Report. Gise Reasons:

NA

9. Power Lesel To Which Restricted.lf Any (Net MWel:

NA yearrirred by 0.L. NPF-13 as listed in 3.0 above.

10. Reasons For Restrictions. lf Any:

na This Month Yr. to.Date Cumulatise II. Hours in Reporting Period 744 744 3672

12. Number Of Hours Reactor has Critical 0

0 995.3

13. Res.-tor Reserse Shutdown Hours 0

0 0

14. Hours Generator On-Line 0

0 0

15. Unit Reserve Shutdown Hour, 0

0 0

16. Gron Thermal Energy Generated iMWHi 0

0 77'388

' 17. Grow Electrical Energy Generated (MWHl' O

O 0

lb. Net Electrical Energy Generated iMWH 6 0

0 0

19. Unit Service Factnr NA NA NA

20. Unit t.vailability Factor NA

-NA NA NA

.NA NA

21. Unit Capacity Factor iUsing MDC Neti 122. Unit Capacity Factor (Uning DER Nett NA NA NA NA NA NA

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Months tT3pe.Date.and Duration of Eacht:

11A

25. If Shut ihmn At End Of Regert Period Estimated Date of Startup:

NA

26. Units in Teq Status IPrior io Commercial Operationi:

Forecast Achiesed INITI4 L CRITICALITY 8-14-82 8-18-82 INITI %L ELECTRK'ITY 4/84 COMMERCl4L OPER ATION 10/84 pg3020047840131 ADOCK 05000416 g

PDR to/771 c,

V Attachment AECM-84/0071 INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT Page 2 of 6 Tha repon should be furnished each month by licensees. The name and telephone number of the preparer should be provided in pv 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.

!. UNIT NAME. Self-explanatory.

or of commercial operation. whichever comes last. to the end of the penod or decommissionmg.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 daybght.savmgs time (or vice versa) occurs.

3. LICENSID THERMAL POWER (MW,Iis the maximum therm:1 power, expressed in megawatts. currently auth.

11 NUMBER OF' HOURS REACTOR WAS CRITICAL.

ori/cd by the Nuclear ReFulatory Commission.

Show the total number of hours the reactor was entical

- -1. NOfEPLATE RATING IGROSS MW,I. The nameplate n.mer designation of the turbme. generator m megavoit

13. RDCTOR RESERVE SHUTDOWN HOURS. The total enperes (MVA) times the nameplate power factor of the number of hours during the gross hours of reportmg turbme generator.

period that tre reactor was removed from service for administrative or other reasons but was available for

f. DESIGN ELECTRICAL RATING (NET MW l 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-

o. MAXIMUM DEPENDABLE CAPACITY (GROSS MW l est tenth of an hour during the gross hours of the re.

e is the gross electrical output as measured at the output portinF period that the unit operated with breakers terminals of the turbine generator dunng the most re*

closed to the statiar. bus. These hours plus those listed strictive seasoral conditions.

in Unit Shutdowns for the gene ator outs e hours.should

• MAXIMUM DEPENDABLF CAPACITY (NET MW,).

Maximum dependable capacity (gross) less the normal

15. UNIT RESERVE SHUTDOWN HOURS. 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 Mas ns ut was a ae Pera @ n.

9. POWER LEVEL TO WHICH RESTRICTED. IF ANY (NET MW,). Note that this' item is applicable only if

16. GROSS THERMAL ENERGY GENERATED (MWH).

restnetions on the power level are in effect. Short. term The thermal output of the nuclear steam sapply system sliss than one month) limitations on power level need during the gross hours of the reporting period, expressed nrt be presented in this item.

in megawatt hours (no decimals).

Since thts information is used to develop figures on capa-

17. GROSS ELECTRICAL ENERGY GENERATEDIMWHL city lost due to restrictions and because most users of the The electrical output of the unit measured at the output "O'perating Plant. Status Reporr are primarily interested terminals of the turbine. generator durinF the gross hours in energy actually fed to the distribution system. it is of the reportmg period. expressed in megawatt hours (no requested that this figure be expressed in MWe Net in decimals).

spite.of the fact that the figure must be derived f rom MW or percent power.

18. NET ELECTRICAL ENERGY GENERATED IMWHL

10. REASONS FOR RESTRICTIONS. IF ANY. If item 9 The gross electriest output of the unit measured at the is used, item 10 should explain why. Bnef narrante is output termmals of the turbine. generator mmus 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 reFulatory reporting period. expressed in megawatt hours. Negative requirements. Be as specific as possible withm space hmi-quantities should not be used. If there is no net positive tations. Plants in startup and power ascension test phase value for the perio l. enter zero (no decimals).

should be identified here.

19. For units still in the startup and power ascension test II. HIURS IN REPORTING PERIOD-For umts in powe,

23. phase. items 19 23 should not be computed. Instead. enter ascension at the end of the penod. the pross hours trum N/A in the current month column. These live factors the begmning of the penod or the first electrical produe.

should be computed starting at the time the unit is de.

tion whichever comes last, to the end of the penod.

clared to be m commercial operation. The cumulatise For units in commercial operation at the end of the figures m the scennd and third columns should be based

. period, the pross hours from the beginning of the penod on commercial operation as a st irting daic.

Attachm?nt to

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AECM-84/0071 Page 3 of 6

19. UNIT SERVICc. FACTOR. Compute by dividmg hours the generator was on line titem 14) by the gross houn in

. the reporting period (item 11). Express as percant 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 hoars litem 14 plus item 15) by the gross hours in the reporting period htem 11). Express

-.as percent to the nearest tenth of a percent.

21. UNIT CAPACITY FACTOR (USLNG MDC NET). Com-pute by dividing net electrical enerFy generated (item 18) by the product of maximum dependable capacity (item

7) times the gross hours in the reporting period (item I11

, Express as percent to the nearest tenth of a percent.

22. UNIT CAPACITY FACTOR (USLNG 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 Shutdowns and Power Reductions) by the sum of hours generator on hne titem 14) plus total forced outage hours (from the table in Unit Shutdowns and Power Redi'etions).

Express as percent to the nearest tenth of a percent.

24. SHUTDOWNS SCHEDULED OVER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACHl. Include type Irefuehng, maintenance. other). proposed date of start.of shutdown, and proposed length of shutdown.

It is recognized th;t 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 approptist6 until the actual shutdown occurs.

25. Self explanatory.

26. Self-explanatory. Note. however; that this information is requested _fo.r_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 im.

tial critieahty durmg which the unit is tested at susces-sively higher outputs. culmmating with operation at full

. power for a sustamed period and completmn of war.

ranty - runs. Folhiwmg this phase. the umt is generally considered by the utihty to be availab!c for commercial

. operation.

.Date of COMMERCIAL OPERATION is defined as the date that the umt was declared by the utihty owner to be available tor the regular production of electricity.

.usually. related to the satisfactory completion of quali.

. lication tests as specified m the puichase contract and to the. accounting policies and practices of the utility.

F..

Attachment to AECM-84/0071 Page 4 of 6 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-416 UNIT I 2-14-84 DATE COMPLETED BY J. G. Cesare TELEPHONE 601-969-2585 MONTH January,-1984 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net t (MWe-Net i g

No Power Generated g7 2.

18 3

19 4

20 5

21 6

22 7

23

-8 24 9

25

.10 26 11 27 12 28 13 29 14 30 15 31 16' INSTRUCTIONS On this formai.hst the userage dail) umt power lesel in MWe Net for each day in the reportmg month. Compute to the nearest whole megawatt.

(4'771

Attichment to AECM-84/0071' PI:gs 5 of 6 UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKETNO. 50-416 UNIT NAME Crnnd Culf Nur 1 ear ~ Sta..

DATE ?-1A RA REPORT MONTH January, 1984 COMPLETED BY J.

G.

Cesare TELEPHONE 601-969-2585 n.

-E E

.5 E 3

jU Licensee P,

{a.

Cause & Corrective No.

Date i

3g 4

2g5 Event py 5]

c.

Action to H

j=

5 Ji g =g Report a mO Prevent Recurrence e

u o

4 11/09/83 S

744.0 F

1 NA NA NA Continuation of outage following (Cont-completion of low power testing.

inued)

I 2

3 4

F: Forced Reason:

Method:

Exlubit G - Inst ructions S: Scheduled A-1:quipment FailureIlixplain) 1-Manual for preparation of Data R-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report II.ER) File tNURI:G.

' O Regulatory Restr.etion 4-Other I Explam) 0161)

I.-Operator Training & Ihenw I.~saminalion F Administrative 5

G-Operational I eror 11 splain t Exhibit I Same Source 19/77)

II-Other Ilixplain) t

At.tachment to-AECM-84/0071 UNIT SHUTDOWNS AND POWER REDUCTIONS Page 6 of 6 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 c.

Reference the appbeable in average daily power level for the precedmg 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 3

shut down completely. For such redpctions in power level, rep rt number. occurrence code and report type) of the five the duration should be hsted 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). Tlus information may not be Cause and Corrective Action to Prevent Recurrence column immediately evident for all such shutdowns. of course, smce 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.

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 correlanon 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 SYSTEM CODE. The sys.em m which the outage or power reduction begins in one report period and ends m another.

an entry shmid be made for both report periods to be sure reduction originated should be noted by the two digit code of all shutdowra or sigmficant power reductions are reported.

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

ber should be :ssigned 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 appropnate component as 770814. When a shutdown or significani power reduction from Exhibit I - Instructions for Preparation of Data Entr>

beginsin one report period and ends in another, an entry should Sheets for Licensee Event Report (LER) File (NUREG 0161 L be made for both report penods to be sure all shutdowns using the followmg critieria:

or significant power reductions are reported.

TYPF. Use "F" or "S" to indicau either " Forced" or " Sche.

duled." respecuvely. for each shutdown or significant power B.

If not a component failure. use the related component reduction. Forced shutdowns melude those required to be e.g.. wrong valve operated through error; hst vahe as initiated by no later than the weekend following discoveri component.

of an off-normal condition. It is recogmzed that some judg.

ment is required m categorizing shutdowns in tlus way. In C.

If a cham of failures occurs. ne first component to mal-general, a forced shutdown is one that would not have been function should be listed. The sequence of events. melud.

completed in the absence of the condition for w hach corrective ing the other components which fail, should be described action was taken, under the Cause and Corrective Action to Present Recur-rence column.

DURATION. Self. explanatory. When a shutdown extends Components that do not fit any existmg code should be de.

beyond the end of a report penod. count only the time to the signated XXXXXX. The code ZZZZZZ should be used for end of the report period and pick up the ensuing down time events where a component designation is not apnheable m the followmg report penods. Report duration of outages rounded to the nearest tenth of an hour to facihtate summation.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-The sum of the total.H%ge hours plus the hours the genera ^

RENCE. Use the column in a narranve fasluon to amphis or tot was on hne should equal the gross %urs in the reportm; explain the circumstances of the shutdown or power reduction.

penod.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and REASON.. C.ateponic by lettes deugnanon m ucordance contemplated long tenn corrective action taken, if approrn-with the table appearmg on the report form. Il, category 11 ate. This column should also be used for a desenption of the must be used supply boet comments.

m or safe 3 related corrective maintenance performed durng METHOD OF SHUTTING DOWN THE REACTOR OR outage or power reduction includmg an idenuficanon of t

REDUCING POWER. Categonie b3 number deugnation enucal path acunty and a report of any smgle release of i

radioactmt3 or smgle radiation eAposure speiilli3}ly JssoiF INote that this ditfer, f rom the Edison Elecine Institute ated with the outage which neounts for more than 10 percent (Elli defininons of " Forced Parnal Outace" and " Sche, of the allowable annual values duled Painal Outage? For these tenn. I I I u>cs a change of For long textual reports continue narrative on separate papes lO MW a> the break pomt f or lances powei reactors.10 M%

and retesence the shutdown or power reducuon im itn-h 1".8 bmJII J chJil*? to w JilJill e%pIJilJlsoll nJl rJf ib' ps --

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Attechunt to

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G AECM-84/0071 x,

Page 1 2

Docket No. 50-416.

~Date: 2-11-84

' Completed By: J. G. Cesare Telephone: 601-969-2585

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OPERATING DATA 10RT

' SUPPLEMENTAL-INFORMATION Major Changes to' Radioactive Waste Treatment Systems 2 1. '

Design; Change Package-(DCP) 83/278 Waste Metering Pump Modification-LA.

-Summary of:10CFR 50.59 Considerations-

-7 DThe design change described below does not involve.the reduction of' safety margins. No significant increase in the probability,or consequences ofran-accident _previously evaluated is-involved nor is the possibility of a newcor different kind of sccident from any accident previously evaluated created. The postt: lated; worst case

, failures (radwaste tank rupture and piping leaksi. analyzed in FSAR Section 15.7.2 and 15.7.3 are considered totenvelope the occurrence

_-and consequence of postulatedyaccidents'due.to this design: change.-

3 The possibility;for.an. accident or malfunction of'a different i.ype

~

[than any previously evaluated in the Final Safety, Analysis Report will not'bel created because::All'potentially_ radioactive portions of 7

_ the waste transfc;r pump subsystem are located _within the radwaste

~(

ibuilding, and designs;were developed in accordance'with the related

^

guidance in Branch Technical Position ETSB 11-3 of. NRC Standard -

Review Plan ~11.4 Therefore, useLof.the' waste tranafer pump

^

': subsystem.will notJresult.in releases which differ from those

-previously predicted in FSAR Sections-15.7.2 and 15.7.3 nor will there be's change;to the maximum exposure to_an; individual in the 4

? unrestricted area'.

The margin of safety, as defined in"the ba' sis for. Technical Specifications will n'ot.be? reduced because: The. design change does

'not. change the limiting conditions for operation', applicabfifty, actions or-surveillance requirements as defined in the basis for Technical Specifications 3/4.11.1,7 6.12, 6.13, and 6.15.

4

( B. ;-

Reason for Change-

)The-vendor ~suppliedwaste'meteringpumpsare-presently _locatadon

elevation =124'-3 3/4" of2the Radwaste Building directly beneath ther

.,f

' waste holding tanks.~- The space beneath'each waste holding tank measures:approximately 10',x_12' x 3'.

Because of the piping, y ~,

. equipment,'and. valving placed~in these spaces.. access for 1 maintenance.is_: severely restricted even for one man.- - Radiation

-?=

. buildup"over a period of time in-the components and piping located

~

iin the cubicle will produce high' background radiation levels.

-Therefore,:-the space restrictions and high background radiation _-

levels beneath'the waste holding tanks result in a virtually unmaintainable equipment arrangement.

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hJ77sdi-

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4 1,;

'i Attachment to W

AECM-84/0071 Page 2 y

M

The installed metering pumps are relatively high maintenance

-. components and frequent. access to the pump seals will be required

_! depending on service demands. Maintenance history for these pumps at GGNS indicates that the. reliability of the metering pumps is not

~ dequate for a single-pump-tank arrangement. Additionally, the a

~

< t:- t h radwaste building floor drain.and equipment drain filters cannot be

.decoupled from' the. waste holding tanks; thus the metering pumps must

_ foperate reliably to maintain filter operation. Although dependence on;the use of the. waste solidification system is greatly reduced as Ta result;of installing permanent piping to transfer wastes to a m

. contract solidification system (DCP-82/650) described in LAECM-83/670, dated November 3,1983, implementation of DCP-82/650

'i

has resulted in increased service demands and dependence on the finstalled metering pumps..

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Detailed Description of the Change s

'This DCP r_eplaces thk installed solid radwaste system " metering"'

. pumps'with centrifugal " transfer" pumps and relocates the pumps from

. the waste holding tank rooms. at elevation 124'-3 3/4" to rooms 4

directly below the tanks at elevation 118'-0".

Relocation of the metering pumps and associated valving to elevation 118'-0" below the concrete' slab at elevation 124'-3 3/4" will result in. improved ~

maintenanceLaccess and correspondingly-will minimize service times x'

and maintenance-incurred exposures. Replacement of the metering fpumps with" centrifugal transfer pumps will resolve equipment reliability-concerns and increase. system processing capacity to coincide with increased service demands.

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Since the original solidification system'is-no longer used, the primary function of this system is to transfer the contents of.the waste holding' tanks.(normally. liquid radwaste precoat. filter backwash) to the. mobile solidification station.in the railroad bay.

Three centrifugal transfer pumps will-be provided, each of which 1will normally.takejsuction from its respective tank and either discharge'to the same tank for' recirculation of the tank contents, c.

or to'a. common sampling or discharge manifold. Cross-connect lines

will be provided between pump suction.and' recirculation lines to

' improve system flexibility. Any of the three pumps will be capable 4 _

[of taking suction from,'and discharge to,'any of the three tanks.

2 Thisfarrangement will permit transfer of tank contents from'one tank

.to'anotheri'and will provide more than adequate operational flexibility in the event that any given pump is inoperable.

Although the common discharge manifold lis designed for s hgle pump operation, this will not prohibit use of:another pump in a dif ferent c

mode'of operation;-that'is,' recirculation, tank sampling, or E

. transferring one waste holding tank's contents to another waste V,

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' holding-tank.-

D.-

' Response t'o GGNS Technical Specification 6.15. (1.d), (i.e), (1.f),

and-(1d)

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Since this change involves ~only waste storage and transfer

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iconsiderations and'does not impact waste processing capabilities or

effluent. releases, predicted' releases'of radioactive materials in 1

Jiquid and gaseous effluents'and/or solid' waste quantities should 4-r 37f d2 '

,a;

.2

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s Attachmtnt to 2

AECM-84/0071 Page 3 not differ'as a'resultsof.this change. Accordingly, expected 3 maximum exposures to.an_ individual in the unrestricted area and to the general population are also unaffected by this' change. Since this : subsystem:is contained within-the radwaste building, any

. potential.for1 radiological consequences due to equipment failtre is fJ'

encompassed by.the existing, and still limiting. tank failure t

e

(

Lanalyses presented in the FSAR.. Shielding of components.and routing

.of associated piping"isiconsistentswith~the design radistien zones y

and ALARA._ principles. Therefore,'no additional exposure to plant

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operating personnel-is anticipated as a result of this change.

2.-

'DesignChangePackage(DCP)83/2[7RadwasteClurrySamplingSubsystem

'A. :. Summary of-10CFR 50.59 Considerations,

~

fThe. design change" described below does not involve the reduction of l

No significant increase in the probability or safety margins.

consequences of an accident previously cvaluated is.involred nor is

~the possibility of a new or different kind of accident from any accident previously evaluated created..The. postulated worst case

. failures (radwaste tank-rupture and piping leaks) analyzed in FSAR

-Section 15.7.2 and-15.7.3 are considered to envelope the occurrence

. and : consequence of: postulated accidents due to the design change.

iThe possibility-for 'an accident' or malfunction.of a dif ferent type than'any previously evaluated-in the. Final Safety Analysis Report

'will not be created because: fall potentially radioactive portions of 1

.the radwaste_ slurry sampling subsystem are located within the'

/

(radwaste. building. and. designs'were; developed-in accordance-with the-trelated guidance 71n. Branch Technical Position'ETSB 11-1 of }UtC

' Standard Review Plan 11.2. 'Therefore, use of:the waste slurry-

~

sampling subsystem will'not' result in releases which differ from those previously predicted in FSAR Sections 15.7.2~and 15.7.3 nor-wil11there be a change.to the maximum exposure to an individual in

'the' unrestricted area.

10he margin of. safety, as defined.in the basis for Technical SpecificationsLwill not be reduced because: The design change does 1

not change the_ limiting conditions for operation. applicability, actions, orl surveillance requirements as defined in-the basis -for

. Technical Specifications 3/4.11.1,f 3/4.11.3, 6.12, 6.13, and 6.'15.

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-B.

. Reason for Change The'radwaste slurry. sampling subsystem is required to provide ea-

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3+

indirect method'of' obtaining a representative sample for 10CFR 61

Waste < Classification Analysis

and.to. ensure plant operating lpersonne1' exposures are'. maintained at minimal' levels consistent with

~ALARA: guidelines.

C.. -Detailed Description of the' Change

'This DCP'provides for the ~ addition of.a radioactive waste slurry sampling subsystem for.the Liquid and Solid Radwaste Systems at.

'GGNS.

Isolok-M-57-A sampling' devices and peripheral accessories JJ77sd3'

Attachm:nt to AECM-84/0071 Page 4 (i.e. automatic controller, etc.) will provide an indirect method of obtaining slurry samples, in lieu of grab sampling, from the Reactor Water Cleanup Tank (RWCU), Phase Separator Decay Tanks, the Spent Resin Tank, the Evaporator Bottoms Collector Tanks, the Waste Holding Tanks, cnd the new Condensate Phase Separator Tanks. Design considerations and methods employed in the subsystem design to maintain ALARA radiation exposures include, but are not limited to the following:

1.

Operator exposure to radiation from other components (i.e.,

waste collector tanks, pumps, valves etc.) containing radioactive material, at the point where the sample is collected, will be reduced by providing shielded remote sampling stations. Exposure of personnel to radiation from the sample and the sample station will be reduced by providing shielding between the compon2nts that constitute radiation j

sources and the receptor.

2.

Potential doses to personnel 5

ing equipment containing radioactive sources has been r_

i by limiting, to the extent practicable, dead spaces or traps components where radioactive material may accumulate. To prevent radioactive accumulations in slurry piping, flow velocities will be kept as high as feasible to prevent settling of solids, piping will be butt welded without backing rings, and protrusions into the piping will be eliminated to the extent practicable.

Accumulations of crud or other radioactive materials that cannot be avoided within equipment or piping will be reduced by providing features that will permit condensate and demineralized water flushing.

.3.

The need to' decontaminate equipment and cubicles has been reduced by taking measures to reduce the spread of contamination from the source. Such measures include the use of stainless steel sample sinks routed to local drains and the use of sealants on surfaces where contamination is anticipated.

The design change also provides for installing heat tracing and insulation on the> sample lines from the Waste Holding Tanks and the Evaporator. Bottoms Tanks to prevent crystallization of waste solids.

D.

Response to GGNS Technical Specification 6.15, (1.d), (i.e), (1.f),

and (1.g)

Since this change involves only sampling devices and interface piping for the sampling of wastes'and does not impact waste processing capabilities (except to increase flexibility) or effluent releases, predicted releases of radioactive materials in liquid and gaseous effluents and/or solid waste quantities should not differ as a result of this change. Accordingly, expected maximum exposures to an individual in the unrestricted area and to the general population are also unaffected by this change. Since all of the equipment and piping is contained within the radwaste building, any potential for radiological consequences due to spills is encompassed by the existing tank failure analyses presented in the FSAR.

'J77sd4

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Attach 2 tnt to AECM-84/0071 Page 5 s.,

Use of the: sample devices will' inherently incur exposure to plant operating. personnel.', Based on the. anticipated sampling frequencies (i.e., twice per week at 10 minutes per sample) and the design configuration, a 25 mr/ month exposure is anticipated. Since a grab

' sampling system requires more intimate personnel contact than the new design configuration, a net reduction in exposure to plant operating personnel will result from use of the slurry sampling subsystem.

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E MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. B OX 1640. J AC K S O N MIS SIS SIP PI 3 9 2 05 February 15, 1984 NUCLEAR PRODUCTION 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-13 File 0260/L-835.0 Monthly Operating Report AECM-84/0071 In accordance with 10CFR50.36, Mississippi Power & Iight Company (MP&L) is providing twelve copies of the Monthly Operating Report (MOR) for Grand Culf Nuclear Station Unit 1 for January,1984, (Attachment).

The attached supplemer.t to the MOR provides detailed information pertaining to two proposed design changes to the CGNS-1 radioactive waste treatment systems. This information is provided in accordance with Section 6.15.1 of the Technical Specifications. These changes were reviewed and approved by the Plant Safety Review Committee on January 6, 1984, in accordance with the requirements of Section 6.5.1 of the Technical Specifications.

The 10CFR 50.59 safety considerations summarized in the attached supplement will receive a detailed review by our Nuclear Safety & Compliance Section in preparation for the annual report on 10CFR 50.59 safety evaluations.

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

Yours truly, L. F Dale nager of Nuclear Services CWD/JCC: sad Attachment cc:

(See Next Page)

IEl Member Middle South Utilities System

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AECM-84/0071

- MISSISSIPPI POWER O LIIHT CCMPANY Page 2

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

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

'Mr. T. B. - Conner (w/o)

Mr. G. B. Taylor (w/o) 1

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

~U S._ Nuclear Regulatory Commission Region II

- 101 Marietta St., N.W., Suite 2900.

Atlanta, Georgia 30303

Chief.'(w/2)

Office of Resource Management

'U. S. Nuclear Regulatory Commission Washington, D. C. 20555 4

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