ML20154D909

Monthly Operating Rept for Apr 1988

ML20154D909
Person / Time
Site:	Farley
Issue date:	04/30/1988
From:	Mcdonald R, Woodard J ALABAMA POWER CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8805200026
Download: ML20154D909 (17)

Text

_ _ _ _ _ _ _ _

.s OPERATING D M REPORT DOCKET NO.

50-348 DA'IE 5/4/88 COMPLE'ITD EY J. D. Woodard

'IELEPH0let (205)899-5156 OPERATING S'NIUS Notes

1. Unit Name Joseph M. rarley - Unit 1

2. Reporting Period:

April, 1988

1) Cumulative data since

3. Licensed Wermal Power (Mt):

2,652 12-1-77, date of

4. Nameplate Rating (Gross Mi4e):

860 comercial operation

~

5. Design Electrical Rating (Net Me): 829

6. Maximum Dependable Capacity (Gross Me):

852.6

7. Maximum Dependable Capacity (Net Me):

812.6

8. If Changes Occur in Capacity Ratings (Items Number 3 2 rough 7) Since Last Report, Give Reasons: N/A

9. Power Level To Which Restricted, If Any (Net Me):

N/A

10. Reasons For Restrictions, If Any:

N/A his Month Yr-to-Date Cumulative

11. Hours In Reporting Period 719 2,903 91,295

12. Number Of Hours Reactor Was Critical 0.0 2,040.8 67,257.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 3,650.0

14. Hours Generator On-Line 0.0 2,040.1 65,865.6

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gros 1 hermal Energy Generated ( MH) 0 5,400,491 167,823,810

17. Gross Electrical Energy Generated (%H) 0 1,763,232 53,930,770

18. Net Electrical Energy Generated (&H) 0 1,673,430 50,842,626

19. Unit Service Factor 0.0 70.3 72.1

20. Unit Availability Factor 0.0 70.3 72.1

21. Unit capacity Factor (Using MDC Net) 0.0 70.9 69.1

22. Unit capacity ractor (Using DER Net) 0.0 69.5 67.2 l

23. Unit Forced Outage Rate 0.0 0.0 9.4

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

N/A

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

5/14/88

26. Units In Test Status (Prior to Comercial Operation):

Forecast Achieved INITIAL CRITICALITY 08/06M7 08/09M7 INITIAL ELEClRICITY 08/20/77 08/18/77 comencIAL OPunAT!m 12/0147 12/0147

.! I l ' f Form 2/34 890520G026 880430

'/

PDR ADOCK 05000348

(*

R ND

D00WT No.

50-348 (MIT 1

DATE May 4, 1988 COMPIEITD BY J. D. Woodard TELEPHom: (205)899-5156 temi April CAY AVERAGE IAILY PCMER LEVEL DAY AVERAGE DAILY POM3t LEVEL (PHe-Net)

(M4e-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0.

10 0

26 0

11 0

27 0

12 0

28 0

i 13 0

29 0

14 0

30 0

15 0

31 l

16 0

INSnt0CTIONS on this format, list the average daily unit power lwel in M4e-Net for each day in the repotting month. Compute to the nearest whole megawatt.

Form 13/21

UNIT SWUTDeaWS AND PoutR REDUCTIOkh DOCKET 30.

54-3-?8 UNIT BASE J.

N.

FARI27 - 13 BIT 1 a

DATE MAY 4, 1988 CONF 12TED BY J. D. MDOOARD REPORT MDWTE APRIL TE12PMOst (2051899-5154 l

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F: Forced Reasons Methodz Exhibit G-Instructions S: Scheduled A-Equipment Failure (Emplain) 1-Manual for Preparaties of Data j

B-Raintenance er Test 2-Manual Scree.

Entry $beeta for Licensee j

C-Refuellag s-Automatic Scree.

Event Report (LER) File (NUREG-

]

D-Regulatory Restriction 4-other (Emplais) 0161)

E-operater Training 6 License Emanination F-Administrative Eahibit I -Same Source G-operational Error (Emplain) 49/71)

B-other (Explain)

EDN

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i 1

JOSEIH M. FARLEY NUCLEAR PLANT ADDENTAN CONCERNING REVISION 5101HE OFP3ITE DOSE CAlfULATION MANUAL a

Revision 5 to the Offsite Dose Calculation Manual (ODCN) was approved by the PORC on April 12, 1988. his revision clarified the requirement to thoroughly mix a liquid waste bat ~h prior to release.

It was detemined by the IG C that this change will not reduce the accuracy or reliability of dose calculations or setpoint deteminations.

he ODCN applies to both Unit 1 arxi Unit 2 at Farley Nuclear Plant.

4 i

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-_d

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FNP-0-M-011 April 4, 1988 i

Revision 5 i

l l

AIABAMA POWER COMPANY i

JOSEPH M. FARLEY NUCLEAR PIANT l

UNITS 1 AND 2 i

S A

F E

I T

Y OFFSIM DOSE CALCUIATICN MANUAL R

E l

L g

T E

D Approvedt r. L '; l'1s.- [/hl l

P Technical Manager Date Issued:

's - / t I'd List of Effective Page Page Rev.

i,ii 2

1,2 5

3-8 2

9-20,22-24,28-32,34-38 0

21,25-27,33 3

39,41,42,46,49 1

40,44,47,48 2

43,45,50,51 4

DN 00CM/3 t

t Y

i

FNP-0-M-011 Dose Calculation Due to Liquid Effluents I

4.11.1.1.1 4.11.1.1.2 4.11.1.1.3 4.11.1'.2 4.11.1.3.1 Liquid Effluents-Dose Calculations Prior to release, all tanks to be released as a batch are isolated from the source and recirculated two volumes to ensure adequate mixing. We batch tank is then sampled after the appropriate mixing. Recirculation time to ensure adequate mixing is calculated as follows:

tank content (gallons) x 2 recirc duration (minutes):

=

L recirc rate (gpm) m te dose contributions for the total time period I at l

3 1=1 shall be determined by the following calculation and a cumilative sumastion I

of these total body and any organ doses shall be maintained for each calendar quarter. Sese dose contributions shall be calculated for all 4

J radionuclides measured in liquid effluents released to unrestricted area using the following expression:

a D, = IlA, 1-1 at: C rit)

I i

it i

where j

We cumulative dose or dose conmitment to the total body or an D,

=

i.

organ T from the liquid effluents for the total time period j

m i

I at, in mrem.

3 l=1 the length of the l'" time period over which C,3 and r are I

at g

=

averaged for all liquid releases, in hours.

3 the average concentration of radionuclide i in undiluted liquid C,g

=

effluent during time period at from any liquid release, in I

i l

uCi/ml.

the site related ingestion dose and dose comitment factor to l

A,

=

the total body or organ t for each identified principal gama 1

l and beta emitter, in mrem /hr per uCi/ml.

1 A, = k,U,Br,Dr 1

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a o

f i

f i

i 1

Rev. 5 f

h f

L

FNP-0-M-Oll where:

+

unit conversion factor,1.14 x 105 (year /hr),(ml/1).(pci/yci).

k,

=

adult fish consumption, 21 kg/yr.

U, the bioaccumulation factor in freshwater fish for each measured Br

=

g radionuclide i, in pci/kg per pCi/ liter (Table 1).

the dose conversion factor for nuclide i for adults, in Dr

=

i arenVpci (Table 2).

the near field average dilution factor for C

'during any r

=

liquid effluent release. Definedastheratioofthemaximum 3

g undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 5.

(5 is the site specific applicable factor for the mixing effect of the discharge structure.)

For radionuclides not determined in each batch or weekly composite, the dosa contribution to the current calendar quarter cumlative sununation may be approximated by assuming an average monthly concentration based on the previous monthly or quarterly composite analyses.

2 Gen. 9ev. 5

.n

JOSEPH M. FARLEY NUCLEAR PIRTF UNIT 1 NARRATIVE

SUMMARY

OF OPERATIONS April, 1988

%e Cycle 8 - 9 refueling outage continued into the month of April.

We following major safety-related maintenance was performed in the month of April:

1.

The reactor was defueled. Visual inspections of the fuel revealed defects on seven fuel assemblies (F/As). Six of these F/As were scheduled to be used in Cycle 9.

Also, ultrasonic testing was performed on all off loaded F/As and selected reload candidate F/As from the spent fuel pool.

Based on the ultrasonic testing, six defective rods were identified in five F/As unloaded from the core. N o of these F/As with leaking rods were scheduled to be used in Cycle 9.

We core was redesigned to delete all leaking F/As and any assemblies with serious grid defects. A total of seven F/As were deleted. The fuel, including 68 f msh assemblies, was placed back in the reactor vessel.

2.

Eddy current examinations were completed on all non-plugged tubes in all three steam generators. Seventeen tubes were plugged:

four in the A steam generator, one in the B steam generator and twelve in the C steam generator.

3.

Ten Year Inservice Inspection activities were performed.

4.

Seventy-one 600 volt breakers are being inspected and repaired per NRC Bulletin 88-01.

5.

Testing of motor-operated valves in response to NRC Bulletin 85-03 is in progress.

6.

Miscellaneous corrective and preventive maintenance was performed on the diesel generators.

4

~

CFEMATING DAM REPORT DOCKET NO.

50-348 DA'11C 5/4/88 OCMPLE"ITD BY J. D. Woodard

'11CLEPHCNE (205)899-5156

_ OPERATING S MTUS Notes 10 Unit Name:

Joseph M. Farley - Unit 1

2. Reporting Period:

April, 1988

1) Cumulative data since

3. Licensed hermal Pcwer (Et):

2,652 12-1-77, date of

4. Nameplate Rating (Gross We):

860 comercial operation

5. Design Electrical Rating (Net $6): 829 60 Maximum Dependable Capacity (Gross We):

852.6

7. Maximum Dependable Capacity (Net We):

812.6

8. If Changes Occur in Capacity Ratings (Items Number 3 2 rough 7) Since Last Report, Give Reaso:is: N/A

9. Power Level To Whi d Restricted, If Any (Net We):

N/A

10. Reasons For Restrictions, If Any:

N/A Wis Month Yr-to-Date Cumulative

11. Hours In Reporting Period 719 2,903 91,295

12. Number Of Hours Reactor Was Crithal 0.0 2,040.8 67,257.5

13. Reactor Reserve Shutdown Hours 0.0 0.0 3,650.0

14. Hours Generator On-Line 0.0 2,040.1 65,865.6

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Wermal Energy Generated (MhH) 0

_5,400,491 167,823,810

17. Gross Electrical Energy Generated (!%H) 0 1,763,232 53,930,770 430 50,842,626 1,673, W

18. Net Electrical Energy Ger.Jrated (MhH) 0 72.1

19. Unit Service Factor 0.0

20. Unit Availability Factor 0.0 70.3_

72.1

21. Urit Capacity Factor (Usil1 MDC Net) 0.0 70.9 69.1

22. Unit Capacity F utor (Using DER Net) 0.0 69.5 67.2

23. Unit Forced Outaae Rate W

0.0 9.4

24. Shutdowns Scheduied Over Next 6 Months (Type, Date, and Duration of Each):

N/A

35. If Shut Down At End Of Report Period, Estimated Date of Startup:

5/14/88

26. Units In Test Status (Prior to Cornmercial Operation):

Forecast Achieved INITIAL CRITICALITY 08/06M7 08/09M7 INITIAL EIKIRICITY 0_8/20M7 08/1847 OtsetERC;AL oi1!lRATICH 12/0147 12/0lM7 Form 2/34

DOCKET No.

50-348 UNIT 1

DATE May 4,1988 COMPLETED BY J. D. Woodard i

TELErin E (205)899-5156 __

M0tml April DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (We-Net)

(We-Net) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

6 0

22 0

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 16 0

IAS77tttCTI0 tis Cn this format, list the average daily unit pcwer level in me-Net for each day in

[

the reporting month. Congrte to the nearest whole megawatt.

i i

Form 13/21

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

,I tT117 SHUTDOWNS AND POWER REDtWIONS DOCKET NO.54-348 UNIT BANE J.

N. FARKET - UNIT 1 DATE MAY 4, 3988

]

COMP 1.ETED BY J. D. UDOOARD REPORT MONTN F.TRIL TE1EPNONE (205)e99-5154 l

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l CAUSE & CORRECTIVE l

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l l DURATION l l SNUTTING l EVENT l 573*.4 l COMPONEAT l

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PREVENT RECURPI'JBCE l

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' Method:

Embibit G-Instructions F: Forced Benson:

S: Scheduled A-Equipment Failure ( Expl::in) 1-Manual for Properation of Data s-Maintenance or Test 2-Manual Scree.

Entry Sheets for Licensee C-Befuelang 3-Automatse Scree.

Event Report (12R) File (NUREG-D-Regulatory aestriction 4-Other (Explain) 0161)

E-operator Training s License Examination F-Administrative Exhibit I -Same Source G-operational Error (Emplain)

(9/77)

N-Other (Explaan)

M PbtIn M

JOSEPH M. FARLEY NUC12AR P1 ANT ADDENDUM CONCERNING REVISION 5 TO 'IME OFFSITE DOSE CA14UIATION MANUAL Revision 5 to the Offsite Dose Calculation Manual (ODOi) was approved by the i

PORC on April 12, 1988. H is revision clarified the requirement to thoroughly mix a liquid waste batch prior to release.

It was detemined by the PORC that this change will not reduce the accuracy or reliability of dose calculations or setpoint deteminations.

%e ODOi applies to both Unit 1 and Unit 2 at Farley Nuclear Plant.

I t.

7.-

FNP-0-M-011 April 4, 1988 Revision 5 AIAiNA POWER COMPANY JOSEPH M. PARLEY NUCLEAR PLANT UNITS 1 AND 2 S

A F

E T

Y OFFSITE DOSE CAkWTION 19NJAL R

E L

A T

E D

Approved d l' 1 s.. - ['hl c

Date Issued:

• /-/5

. d i

List of Effective Page Page Rev.

i,ii 2

1,2 5

3-8 2

9-20,22-24,28-32,34-38 0

21,25-27,33 3

39,41,42,46,49 1

40,44,47,48 2

43,45,50,51 4

DNODCV3 i

2

--.-e-7-,

FNP-0-M-011 r

Dose Calculation Due to Liquid Effluents J

4.11.1.1.1 4.11.1.1.2 4.11.1.1.3 4.11.l'.2 4.11.1.3.1 Liquid Effluents-Dose Calculations Prior to release, all tanks to be released as a batch are isolated from the source and recirculated two volumes to ensure adequate mixing. Se batch r

tank is then sampled af ter the appropriate mixing. Recirculation time to ensure adequate mixing is calculated as follows:

l i

tank content (gallons) x 2 recire duratior. (minutes):

=

recire rate (gpa) m he dose contributions for the total time period I at 1

3 1-1 shall be determined by the folicwing calculation and a cumulative sunnation of these total body and any organ doses shall be maintained for each

?

calendar quarter. %ese dose contributions shall be calculated for all radionuclides measured in liquid effluents released to unrestricted area using the following expression m

i 3 C,3 F33)

D, = IlA, 1-1 I at i

where r

ne cumulative dose or dose comitment to the total body or an e

D, organ t from the liquid effirents for the total time pericd m

I at,, in mrem.

1-1 the length of the 1" time period over which C and r are I

ot 33 g

=

i averaged for all liquid releases, in hours.

the average concentration of radionuclide i in undiluted liquid C,3

=

effluent during time period at f rcn any liquid release, in i

i vC1/ml.

3 the site related ingestion dose and dose comitment factor to A,,

=

the total body or organ T for each identified principal ganma and beta emitter, in. renvhr per vCi/ml.

A,, = k,U,Br Dr g

g 4

1 1

Rev. 5

rNP-0-M-Oll where:

unit conversion factor,1.14 x 105 (year /hr).(al/1),(pci/yci).

k, adult fish consurnption, 21 kg/yr.

U,

=

the bioaccumulation factor in freshwater fish for each measured Br' radionuclide i, in pCi/kg per pCi/ liter (Table 1).

the dese conversion factor for nuclide i for adults, in Dr

=

3 mrem /pci (Table 2),

the near field average dilution factor for C

'during any r

liquid effluent release. Definedastheratk3o of the maxirrum 3

undiluted liquid waste flow during release to the product of the average flow from the site discharge structure to unrestricted receiving waters times 5.

(5 is the site specific applicable factor for the mixing effect of the discharge structure.)

For radionuclides not determined in each batch or weekly composite, the dose contribution to the current calendar quarter cumulative sununation may be approximated by asening an average monthly concentration based on the previous monthly or quarterly composite analyses.

f s

t 1

)

i.

s 2

Gen. F.ev. 5 i

l

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.. ^

Alabama Porte$ Company 600 Norm 1M Wreet Post Othee Bec2641 Birmingham, Alabama 35291-0400 Telephone 205 2501835 e

kn"oTc*e"!,Teio.,,

&be he the soahern ewrc system

~

May 10, 1988 Docket No. 50-348 U. S. Nuclear Regulatory Costunission ATIN: Document Control Desk Washington, D. C.

20555 Joseph M. Earley Nuclear Plant Unit 1 Monthly Operating Data Report Attached are two (2) copies of the April 1988 Monthly Operating Report for Joseph M. rarley Nuclear Plant Unit 1, required by Section 6.9.1.10 of the i

Technical Specifications. Also attached is Revision 5 to the offsite Dose Calculation Manual (ODCM).

If you have any questions, please advise.

Yours very truly,

/

R. P. Mcdonald RPfVJGS:mab/1.5 Attachments xc: Dr. J. N. Grace l

i t

i 4

e JOSEPH M. FARLEY NUCLEAR PIRfr UNIT 1 NARRATIVE

SUMMARY

OF OPERATIONS April, 1988 he Cycle 8 - 9 refueling outage continued into the month of April.

2e following major safety-related maintenance was performed in the month of April:

1.

2e reactor was defueled. Visual inspections of the fuel revealed defects on seven fuel assemblies (F/As). Six of these F/As were scheduled to be used in Cyc'le 9.

Also, ultrasonic testing was performed on all off loaded F/As and selected reload candidate F/As from the spent fuel pool.

Based on the ultrasonic testing, six defective rods were identified in five F/As unloaded from the core. Two of these F/As with leaking rods were scheduled to be used in Cycle 9.

We core was redesigned to delete all leaking F/As and any assemblies with serious grid defects. A total of seven F/As were deleted. We fuel, including 68 fresh assemblies, was placed back in the reactor vessel.

2.

Eddy current examinations were completed on all non-plugged tubes in all three steam generators. Seventeen tubes were plugged:

four in the A steam generator, one in the B steam generator and twelve in the C steam generator.

3.

Ten Year Inservice Inspection activities were performed.

4.

Seventy-one 600 volt breakers are being inspected and repaired per NRC Bulletin 88-01.

5.

Testing of motor-operated valves in response to NRC Bulletin 85-03 is in progress.

6.

Miscellaneous corrective and preventive maintenance was performed on the diesel generators.

4 t

- - - -