ML20148E139

Monthly Operating Repts for Dec 1987

ML20148E139
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1987
From:	Crawford J, Jacqwan Walker TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8801250572
Download: ML20148E139 (71)

Text

o MONTHLY OPERATING REPORT BROWNS FERRY NUCLEAR PLANT TENNESSEE VALLEY AUTHORITY DECEMBER 1987 "Safety and Quality are Paramount" DOCKET NUMBERS 50-259, 50-260, AND 50-296 LICENSE NUMBERS OPR-33, DPR-52, AND DPR-68 Submitted by:

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TABLE OF CONTENTS PART I OPERATIONAL

SUMMARY

A.

Significant Operational Event s Summary........................... 1 B.

Fuel Performance and Spent Fuel Storage Capabilities Summary..... 2 C.

MSRVs (Main Steam Relief Valve) Summary..........................

5 D.

I s su anc e o f S p e c i al R e po r t s S umma ry.............................. 6 E.

L i c ens e e Ev ent s S umma ry......................................... 7 F.

Offsite Dose Calculation Manual Changes..........................

9 G.

R a dwa s t e S umma ry................................................ 10 1.

Total volume of solid waste shipped off site 2.

Nature of the waste (trash, resins, etc.)

3.

Gross curie activity 4.

Dates the material was shipped and the disposal facility to which the material was shipped.

5.

Estimated quantities of spent resin in storage.

6.

Estimated amount of spent resin that will be generated in the following month.

7.

Waste type and volume of radwaste containers that are onsite awaiting shipment.

PART II OPERATING STATISTICS A.

NRC Reports 1.

Operating Data Report.......................................

15 2.

Average Daily Power Leve1...................................

18 3.

Unit Shutdowns and Power Reductions......................... 21 B.

TVA Reports 1.

Plant Operating Statistics.................................. 24 2.

Unit Outagr and Availability Data...........................

25 3.

Reactor Histogram (2eactor Power Percent)...................

28

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TABLE OF CONTENTS (Continued)

Part III MAINTENANCE

SUMMARY

A.

El e ct ri cal Maint enanc e........................................... 2 9 B.

Ins t rumen t Ma in t enanc e........................................... 3 2 C.

Mechanical Maintenance...........................................

34 D.

Modifications....................................................

37 PART IV TVA GADS EVENTS REP 0RT............................................

39 PART V OTHER REPORTS A.

Chemistry Summary 1.

P r ima ry C o o l an t Ch emi s t ry.................................. 4 2 2.

Environmental Technical Specification Requirements.......... 45 3.

A i r b o rn e R e l e a s e s........................................... 4 6 4.

Liquid Releases.............................................

51 5.

Resin Usage Report..........................................

55 6.

Fuel Cladding Integrity Parmeters........................... 5 6 7.

Was t e Trea tment Sys t em Throughput s.......................... 5 7 B.

T e s t i ng S umm a ry.................................................. 5 8 C.

Reactor Vessel Fatigue Usage Evaluation..........................

60 D.

Change in Procedures.............................................

61 E.

Change in Facility Design (ECNs).................................

61 F.

Plant Instruction Revisions......................................

65 G.

Change in Plant Organization.....................................

66 H.

Accidents........................................................

67

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e OPERATIOXAL SCMMARY e

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SIGNIFICANT OPERATIONAL EVENTS

SUMMARY

p DECEMBER 1987 Unit 1 12/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.

12/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 6 refueling and modifications continues.

Unit 2 12/01/87 0001 Unit remains on administrative hold to resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.

12/31/87 2400 Unit remains on administrative hold to' resolve various TVA and NRC concerns, and end of cycle 5 refueling and modifications continues.

lhli.La 12/01/87 0001 Unit remains on administrative hold to resolve various TVA and PRC concerns, and environmental qualifications and modifications continues.

12/31/87 2400 Unit remains on administrative hold to resolve various TVA and NRC concerns, and environmental qualifications and modifications continues.

1

FUEL PERFORMANCE AND SPENT WEL STORAGE CAPABILITIES

SUMMARY

DECEMBER 1987 UTit 1 Unit 1 was placed on administrative hold in March 1985 to resolve TVA and NRC concerns. The unit also began its sixth refueling on June 1, 1985, with a scheduled restart date to be determined. The sixth refueling will involve loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 1 items are environmental qualification of electrical equipment (10CFR50.49), torus modification (NUREG 0661), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifications, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J), HPCI concerns, modification of PCIS logic (LER 259 85009),

replacement of plant process computers, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), RPS modifications (IE Notice 78-45), H 0 sample line modification (LER 81050), radiation 22 monitors modification (LER 80033), EECW carbon to stainless pipe change out, and all NRC commitment items except Anticipated Transients Without Scram (ATWS) modifications which is scheduled for next outage.

There are 0 assemblies in the reactor vessel. The spent fuel storsge pool presently contains 284 new assemblies, 764 EOC-6, 252 EOC-5, 260 EOC-4, 232 EOC-3, 156 EOC-2, and 168 EOC-1 assemblies. The present available capacity of the fuel pool is 1355 locations.

2

FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONT.)

DECEMBER 1987 Unit 2 Unit 2 was shut down on September 15, 1984, for its fifth refueling outage with a scheduled restart date to be determined. On September 3, 1985, the unit was placed on administrative hold to resolve TVA and NRC safety concerns. The fifth refueling involves loading 8x8R (retrofit) fuel assemblies into the core. The prior-to-startup unit 2 items are CRD SDIV piping modification (IEB 80-17), environmental qualification of electrical equipment (100FRSO.49), torus modifications (NUREG 0661), containment modification (NUREG 0737), electrical changes (Appendix R 10CFR50) (partial),

MSIV modifications, modification of masonry walls (IEB 80-11), addition of feedwater nozzle temperature monitoring (NUREG 0619), evaluation of the vent drain and test connections, VDTC, (LER 82020), valve modification (Appendix J)

(partial), D/G speed sensor installation (LER 81004), IIPCI and RCIC test: le check valve change out, modification of PCIS logic (LER 259 85009), HPCI concerno, seismic program review, and EECW carbon to stainless pipe change out.

There are 0 assemblies in the reactor vessel. At month end there were 304 new assemblies, 764 EOC-5, 248 EOC-4, 352 E00-3, 136 EOC-2, and 132 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the spent fuel p'ool is 1481 locations. All HDRs have been installed in the pool with the exception of two.

3

FUEL PERFORMANCE AND SPENT FUEL STORAGE CAPABILITIES

SUMMARY

(CONr.)

DECEMBER 1987 Unit 3 Unit 3 was shut down on March 9, 1985, and placed on administrative hold to resolve various TVA and NRC concerns with a scheduled restart date to be determined. The sixth refueling outage has been scheduled for September 21, 1988, and involves loading 8x8R (retrofit) assemblies into the core and ATWS modifications.

The prior-to-startup unit 3 items are environmental qualifica-tion of electrical equipment (10CFR50.49), containment modifications (NUREG 0737), electrical changes (Appendix R 10CFR50) (all), MSIV modifica-tions, modification of masonry walls (IEB 80-11), evaluation of the vent drain and test connections, VDTC,(LER 82020), valve modifications (Appendix J), HPCI concerns, replacement of plant process computer, seismic qualifications of piping (IEB 79-02/14), postaccident evaluation (NUREG 0737), addition of redundant drywell control air supply, RPS modification (IE Notice 78-45),

H0 sample line modification (LER 81050), radiation monitor modification 22 (LER 80033), replacement of jet pump holddown beam assemblies (IEB 80-07),

change out of switches in SBGT (LER 83018), EECW carbon to stainless pipe change out, and plant design upgrade to seismic qualification.

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There are 0 assemblies in the reactor vessel. There are 764 assemblies to finish EOC-6, 248 EOC-5, 280 EOC-4, 124 EOC-3, 144 EOC-2, and 208 EOC-1 assemblies in the spent fuel storage pool. The present available capacity of the fuel pool is 585 locations. All high density racks (HDR) have been installed in the pool with the exception of six.

4

MSRVs (MAIN STEAM RELIEF VALVE)

SUMMARY

No MSRVs were challenged in December 1987.

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ISSUANCE OF SPECIAL REPORTS The following special report was submitted to the NRC in December 1987.

87-37-05 Requirement was not met in that Browns Terry Standard Practice 14.4, Drilling, Chipping, or Altering Concrete or masonry and Excavation, dated October 16, 1985, contained an inadequate methodology for computing secondtry containment in-leakage resulting from core drilling operations.

I 87-37-01 The requirement was not met on October 13, 1987, when Residual 4

Heat Removal (RHR) pump suction valve 2-74-24 was inadvertently operated by a Reactor Operator.

i 87-37-04 An instrument mechanic improperly adjusted pressure gauge E82214 which was being used in a post-modification test instruction on instrumentation used by the Reactor Protection System and Emergency Core Cooling System.

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LICENSEE EVENT REPORT (S)

The following licensee event reports (LERs) were eported to the Nuclear Regulatory Commission in December 1987.

Q3scriotion of Event IJ3 1-87001 This revision provides additional details concerning Rev. 1 th* Personn?1 errors which caused fire watch violations.

1-87029 Rnrannpel Error _in Writina Eauipment. Tar-Out Clearance Results in Actuations of_ Engineered Safety Feature 14 On No,vember 5, 1987, at 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br />, a fuse was removed from a panel in ord'er to deenergize a primary containment isolation valve for modification activities. This action resultea in a primary containment ventilation isolation, auto start of two trains of the standby gan treatment system and one train of the control room emergency ventilation system. These engineered safety feature actuati;ns were the result of improper identification of the isolation boundaries.

Research into switching necessary to electrically isolate the valve was inadequate during preparation of the clearance. The individuals involved have been cautioned to check all prints carefully to ensure tnat no unexpected events occur. A critique of this incident has been prepared for review by operations personnel to reemphasize the need for adequate re9earch in writing a clearance.

1-07030 Eaulty Relav Coil Causes Auto Start of Control Room Emernency Ventilation System On November 24, 1987, at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br />, control room personnel observed that train B of the contrcl room emergency vaatilation (CkEV) system was running.

All three units were defueled and no refueling operations were in progress. The exact time of the CREV auto start is unknown. After verifying CREV train A operable and no valid initiation signal present, the licensed operator secured the system.

Following investigation by electrical maintenance personnel it was determined that a burned electrical coil in the unit 3 16A-K72 relay had caused the actuation. The faulted coil was assnssed as an end-of-life fai. lure and was replaced.

7

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Descriotion of Event (Continued)

LER i

3-87006 Unolanned Enmineerins,_ Safety Feature Actuations due to Relav Failure and Personnel Error Durina fdtnective MaintenartcL At 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />, on November 22, 1987, with all three units defueled, a relay coil in the Primary Containment Isolation System (PCIS) logic developed an electrical short and cleared the fuse protecting that portion of the PCIS logic. As a result, the in'uoard PCIS valves for the drywell floor and the equipment drain sump discharges isolated. The fuse and relay were replaced and all systems were retorned to their original status by 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />, on November 24, 1987. The cause of the relay coil failure is considered to be an end-of-life failure.

During the replacement of this relay, on November 24, 1987, at 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br />, the jumper which was installed as part of this corrective maintenance was inadvertently dislodged by maintenance craft.

This deenergized other PCIS relays. The deenergization closed the inboard isolation valve on the suction of the Reactor Water Cleanup (RWCU) system and tripped the running RWCU pump. The-jumper was replaced and the isolation was reset.

RWCU was returned to service 15 minutes after it isolated.

Corrective maintenance was completed by 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />, on November 24, 1987, and all systems were returned to their original status.

These individual valve closures are considered unplanned actuations or engineered safety features.

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DECEMBER 1987 i

0FFSITE DOSE CALCULATION MANUAL CHANGES No changes were made to the Browns Ferry offsite dose calculation manual during the month.

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e RADWASTE SUttiARY DECEMBER 1987 The radwaste system performed as designed. Approximately 6.92E+05 gallons of waste liquid were discharged containing approximately 2.47E-02 curies of activity.

There were five condensate / waste resin shipments and three trash shipments during December. All shipments were to Barnwell, SC.

10

Solid Radioactive Naste December 1987

. Condensate / Wast,e Resin Shipments (1)

Approximate volume of resin / sludge shipped: 20.4 Cu.M. (720 Cu.Ft.)

Total curies shipped: 24.8060 Principal Isotopes:

Cs137, Co60, Cs134, 2n65, Fe55 Date.3 hipped Disposal Facility 12/ 02/ 87 Barnwell, SC 12/ 11/ 87 Barnwell, SC 12/ 15/ 87 Barnwell, SC 12/ 18/ 87 Barnwell, SC 12/ 29/.87 Barnwell, SC Reactor Water Cleanup Rosin Shipments There were no reactor water cleanup resin shipments Drunned Shi pmen t s There were no drum shipments Boxed Shi pmen ts ( 1)

Total number of boxes shipped: 29 Volumes 80.0 Cu.M. (2826.2 Cu.Ft)

Total Curies Shipped: 1.0160 Principal Isotopes:

Fe55, Zn65, Co60, Cs137, Cs!34 Date Shipped Disposal Facility 12/ 02/ 87 Barnwell, SC 12/ 10/ 87 Barnwell, SC 12/ 17/ 87 Barnwell, SC

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Solid Radioactive Naste (Continued)

December 1987 Summary Shipped to Stored Approximate Proposed for Barnwell on Site Cost Next Month Compacted Drums O

Cu.F t. ( 2) 60 Cu.Ft.

O Cu. F t. ( 2)

Compacted Boxes 1209 Cu.Ft. (2) 465 Cu.Ft.

$50,740.19 1488 Cu. F t. ( 2)

Drums O

Cu.F t. ( 2) 2168 Cu.Ft.

O Cu. F t. ( 2)

Boxes 1617 Cu. F t. ( 2) 788 Cu.Ft.

$66,920.33 10 21 Cu. F t. ( 2)

CWPS Resin 720 Cu.Ft.(1) 1923 Cu.Ft.

$95,497.44 720 Cu.Ft.(1)

RNCU Resin 0

Cu.Ft.(!)

415 Cu.Ft.

O Cu.Ft.(1)

TOTALS 3680 Cu.F t. (2) 5819 Cu.Ft.

$213,157.96 3363 Cu. F t. ( 2)

Total volume of waste shipped during the month:

3680 Cu.Ft. (2)

Total volume of waste shipped year to date:

47889 Cu.Ft.

Unused 1987 burial volume allocation at Barnwell:

35891 Cu.Ft.

( 1)

Actual resin volume.

( 2)

Container buri al vol ume.

( 3)

Cost included are for containers, transportation and disposal.

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LIGUID RADWASTE MONTHLY OPERATING REPORT DECEMBER 1987 FLOW RATE (GPM)

DATA PLOTTF.

R H PRE 12 MONTHS TOTAL RELEASE (CI) 40.

2 nATE (GPM)_

HI 29.52 30.

LOW 11.62 AVG 19.67

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HI 0.05 LOW 0.01 10.

AVG 0.03 o FLOWRATE h.B

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UL AUG

,P bCT NOV EC VAN FILTER THROUGHPUTS

"" [,* """" ' ' ' '

5 GALLONS X 10 HI 0.35E+C7 6

LOW 0.8SE+0S AVG 0.19E+07

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HI 0.14E+07 LOW 0.49E+05 4

AVG 0.91E+0S LAUNDRY HI 0.11E+05 LOW 0.00E+00 2

AVG 0.61E+04 0

"' VAN FEB MAR APR MAY VUN VUL AUG SEP OCT t'0 V DEC COST OF OPERATION onende*lrnAun2)

THOUSANDS OF DOLLARS WASTE 13CL HI 0.68E+05 120.

LOW 0.12E+05 110.

AVn 0.39E+05 FLCOR DAAIN O-HI 0.57E+05 80.

LOW 0. $3E+C 5 70 -

AVG 0.33E+C5 60 50.

LAUNDRY 40.

s HZ 0.18E+03 h\\N LOW 0.04,E+00

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VAN FEB MAR APR MAY VUN VUL AUG SEP OCT NOV DEC WASTE COLLECTOR SYSTEM LAUNDRY SYSTEM FLOOR LRAIN SYSTEM STARTING 3-07 COSTS INCLUDE RESIN Ci.ISPOSAL i

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OPERATLXG STATISTICS l

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OPERATING DATA REPORT DOCKET 183. _50-259 DATE 01-01-88 CO ft.ETED BY J. D. Crawford tidPh0hE (205) 729-2507 OPERATING STATUS l Notes l

l.

Unit Names Browns Ferry Unit one l

l 2.

Reporting Period: Dece d or 1987 l

l 3.

Licensed Thermal Power (W t): 3293 4.

Nameplate Rating (Gross % ): 1852 l

S.

Design Electrical Rating (Not %) 1065 l

l 6.

hinun Dependable Capacity (Gross %).1098.4 l

l 7.

Maximum Dependable Capacity (Not W e) 1065 l

l 8.

If Changes occur in Capacity Ratings (items Nueer 3 Through 7) Since Last Report, cive Reasons:

N/A 9.

Power Level To Which Restricted, if Any (Not We):

N/A

10. Reasons For Restrictions, if Anyx N/A This Month Yr-to-Date Cunulative

11. Hours in Reporting Period 744 8760 117.600

12. Nueer of Hours Reactor Was Critical 0

0 59.521.38

13. ReAtor Reserve Chutdown Hours 0

0 6.997.44

14. Hours Generator On-Line 0

0 58.267.26

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (WH) 0 0

168.066.787

17. Gross Electrical Energy Generated (WH) 0 0

55.398.630

18. Not Electrical Energy Generated (WH)

_ -744

-14.233 53.706.402

19. Unit Service Factor 0

0 49.51

20. Unit Availability Factor 0

0 49.51

21. Unit Capacity Factor (Using M)C Net) 0 0

42.85

22. Unit Capacity Factor (Using DER Net) 0 0

42.85

23. Unit Forced Outage Rato 100 100 41.12

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

I

25. If Shut Down At End of Report Period, Estimated Date of Startup To be detsmined i

i

26. Units in Test Status

• Prior to Cognaccial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY C0f90ClAL OPERAT10N (9/77) 15

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OPERATlW DATA REPORT DOCKET NO.

50-260 l

DATE 01-01-88 CO WLETED BY J. D. Crawford TELEPHONE (205) 729-2507 OPERATl w STATUS INotes I

1.

Unit Names Browns Ferry Unit Two l

l 2.

Aaporting Period Decod ee 19tl7 l

l 3.

Licensed Thermal Power (Wt): 3293 l

l 4.

kameplate Rating (Gross % ): l152 l

l 5.

Design Electrical Rattag (Not %) 1065 6.

MaxM Dependable Capacity (Gross %) 1098.4 7.

Max ga Dependable Capacity (Not %)

1065 l

l 8.

If Changes Occur in Capacity Ratings (ltems Neber 3 Through 7) Since Last Report, Give Reasons:

N/A 9.

Power Level To Which Restricted, if Any (Not %):

N/A

10. Reasons For Restrictions, if Any:

N/A This Month Yr-to-Cate Cumulative ll. Hours in Reporting Period 744 8760 112.567

12. Neber of Hours Reactor Was Critical 0

0 55.860.03

13. Reactor Reserve Shutdown Hours.

0 0

I4.200.44

14. Hours Generator On-Line 0

0 54.338.36

15. Unit Reserve Shutdown Hours 0

0 0

I6. Gross Thermal Energy Generated (M) 0 0

153.245.167

17. Gross Electrical Energy Generated ( M )

0 0

50.771.798

18. Not Electrical Energy Generated (M)

-2.007

-34.470 49.183.833

19. Unit Service Factor 0

0 48.27

20. Unit Availability Factor 0

0 48.27

21. Unit Capacity Factor (Using M)C Net) 0 0

41.03

22. Unit Capacity Factor (Using DER Net) 0 0

41.05

23. Unit Forced Outage Rate

__ 100

_ l00 40.25

24. Shutdowns Scheduled Over Next 6 h ths (Type, Date, and Durati m of Each):

25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined

26. Units in Test Status (Prior to Ccemercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COM O CIAL OPERATION (9/77) 16

OPERATING DATA REPORT DOCKET No.

50-296 DATE 01-01-88 (DFLETED BY J. D. Crawford TELEPHONE IM) 729-2507 OPERATING STATUS INotes I

1.

Unit Name:

Bro..is Ferry Unit Three l

l 2.

Reporting Period h 1987 l

l 3.

Licensed Thermal Power (PWt): 3293 l

l 4.

Nameplate Rating (Gross % ): 1852 l

l S.

Design Electrical Rating (Not h) 1065 6.

Maxinnsa Dependable Capacity (4ross %) 1098.4 7.

Maximum Dependable Capacity (Not % )

1065 l

l 8.

If Changes Occur in Capacity Ratings (Items Nunber 3 Through 7) Since Last Report, Give Reasons:

N/A 9.

Power Level To Which Restricted, if Any (Not h):

N/A

10. Reasons For Restrictions, if Any:

N/A This Month Yr-to-Cate Cumlativa

11. Hours in Reporting Period 744 8760 94.992

12. Nun 6er of Hours Reactor Was Critical 0

0 45.306.08

13. Reactor Reserve Shutdown Hours 0

_ 0 5.149.55

14. Hours Generator On-line 0

0 44.194.76

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated ( M )

0 0

131.868.267

17. Gross Electrical Energy Generated (PWH) 0 0

43.473.760

18. Not Electrical Energy Generated ( M )

-4.397

-50 M 42.041.148

19. Unit Service Factor 0

0 46.52

20. Unit Availability Factor 0

0 46.52

21. Unit Capacity Factor (Using M)C Net) 0 0

41.56

22. Unit Capacity Factor (Using DER Net) 0 0

41.56

23. Unit Forced Outage Rate 100 100 43.54

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

l

25. If Shut Down At End Of Report Period, Estimated Date of Startup To be determined

26. Units in Test Status (Prior to Consnercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY CD9ERCIAL OPERATION (9/77) 17 m.nuco-erroe-m uwaw.uu.- - - mewes n-u =-

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-259 Unit one DATE 01-01-87 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH '

NOVEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Net)

(MWe-Net) 1

-1 17

-1 2

-1 18

-1 3

-1 19

-1 4

-1 20

-1 5

-1 21

-1 6

-1 22

-1 7

-1 23

-1 8

-1 24

-1 9

-1 25

-1 10

-1 26

-1 11

-1 27

-1 12

-1 28

-1 13

-1 29

-1 14

-1 30

-2 15

-1 31

-1 16

-1 INSTRUCTIONS on this format. List the average daily unit power level in MWe-Net for each day in the reporting month.

Compute to the nearest whole megawatt.

(9/77) 18

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-260 Unit Two DATE 01-01-88 COMPLETED BY J.D. Crawfg.01 TELEPHONE (205)729-2507 MONTH DECEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVRL (MWe-Net)

(MWe-Net) 1

-3 17

-3 2

-3 18

-3 3

-2 19

-3 4

-3 20

-2 5

-3 21

-2 6

-3 22

-2 7

-3 23

-3 8

-3 24

-2 9

-3 25

-3 10

-3 26

-2 0

11

-3 27

-3 12

-2 28

-2 13

-2 29

-3 14

-2 30

-4 15

-3 31

-2 16

-3 INSTRUCTIONS On this format, list the average daily unit power level in NWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 19

AVERACE DAILY UNIT POWER LEVEL DOCKET NO.

50-296 Unit Three DATE 01-01-88 COMPLETED BY J.D. Crawford TELEPHONE (205)729-2507 MONTH DECEMBER 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (NWe-Met)

(NWe-Net) 1

-6 17

-6 3

-6 18

-6 3

-6 19

-5 4

-6 20

-6 5

-6 21

-6 6

-6 22

-6 7

-6 23

-6 8

-6 24

-6 9

-6 25

-6 10

-3 26

-6 e

11

-6 27

-6 12

-6 28

-6 13

-6 29

-6 4

14

-7 30

-7 15

-6 31

-6 16

-6 INSTRUCTIONS on this format, list the average daily unit power level in NWe-Met for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 20

)

b 3,

UNIT SilUIDOWNS AND POWER REDUCHONS DOCKET NO. 50-759 UNIT NAME One I

DATE 01/01/88 COMPLETED sy

.7 n- (raufnra REPORT MONTH December e

TELEPHONE ( ?nci) 7?o_?s;n7 7,

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jE

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cause & Correceive

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Event g7 83 Action to Date hO Prevent Recurrence f

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744 4

Achninistrative hold to resolve (cont..

various TVA and NRC concerns.

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I: Forced Reaum:

Methal:

Exhibit C-Instructions S Stheduletl A 1 quip.nens Failure (Explain) 1 -Manual for Preparati.m of Data l

B-Maintenance of Test 2-Manual Scram.

Entry Sheets liar Licensee C Refueling 3-Autunusic Stram.

Event Repors (LER) Fde INilRI G-D-Regulator) Resiricisim 4-Other I Explain) 0161) 1 -Operator Trainmg & latense 1 xanunation F-Adinimsa rative 5

G-Operational I a ros IExplain t ITinbit I Same Source 08/77)

Il thher ll:xplain)

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DOCKET NO. W2@

UNITSilOTDOWNS AND POWER REDUCTIONS UNIT NAME Two DATE ni/ni/nn mW

_ n_ hM REPORT MONHf Decanher TELEPHONE (205) 729-2507

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305 12/1/87 F

744 F

4 Administrative hold to resolve (cont.

various TVA and NRC concerns.

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I: F..sced Reaum:

Method:

Exinbit G -Instructiims S Solicduteil A Iquipment Fadure! Explain) 1-Manual Ior Pseparati.m of Data H Maintenance or Test 2-Marraal Scra m.

Entsy Sheets for Licensee C Refueling 3 Au.eutic Eram.

Event Repius (LER) File (NURI.G-D Regulatos) Restriction 44)ihes (Expia' s) 0161i a

ILOperator Ts.smmg & Lnense Lununation t

F-Adnunastras sve 5

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I sinbit 1 Same Source 19/77)

II Other (L splauit g.:

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i UNITSil01 DOWNS AND PO'4ER REDUCTIONS DOCKET NO. 50-296 UNIT NAME

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DATE 01/01/88 REPORT MONilt Deconher COMPLETED BY J D_ crawford TELEPHONE f ?O'il 7 2 % ? 9 17 y

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Method:

Exhibit G-Insisuctiinis S. Stheduled A liguipment l'aduse(Lxplain) 1 Manual los Psepasatism uf them B-Maintenanceof Test 2-Manual Sciam.

1.nasy Sheces los I.icensee C Refueling 3 Automatic Sisam.

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p8/77) ll Ushes llNplaini

vva 7sasa toa**-all NUCLEAR PLANT OPERATINS STATISTICS Brevns Ferry Nuclear Piant Period Hours

'MA Month December 1987 Item No.

Unit No.

Unit 1 Unit 2 Unit 3 Plant 1

Averaes Hourly Gross Load. kW O

O O

O 2

Maximum Hour Net Generation. MWh 0

0 0

0 3

Core Thermal Enerov Gen. GWO (t12 O

o o

o 4

Steam Gen. Thermal Energy Gen., GWO (t)2 j

S Grow Electrical Gen., MWh 0

0 0

0 2

6 Station use. MWh 744 2007 4397 7148 7

Not Electrical Gen.. MWh

-744

-2007

-4397

-7148 c

8 Station Use. Percent O

O O

O 9

Accum. Core Avg. Exposure. MWO/Toni O

O O

O 6

10 CTEG This Month.10 BTU O

O O

O 11 SGTEG This Month,106 BTU 12 13 Hours Reactor Was Critical 0

0 0

0 14 Unit Use. Hours. Min.

0 O

O O

15 Capacity Factor, Percent 0

0 0

0 g

16 Turbine Avail. Factor. Percent 0

0 0

0 17 Generator Avail. Factor. Percent O

O O

O-d 18 Turbooen. Avail. Factor. Percent O

O O

O 19 Rameter Avail. Factor. Percent O

O O

O 6

20 Unit Avail. Factor. Percent O

O O

O 21 Turbine Startuos O

O O

O 22 Reactor Cold Startues G

O O

O 23 24 Gross Heat Rate. Btu /kWh O

O O

O f

25 Net Heat Rate, Btu /kWh O

O O

O E'

26 5

27 I

g 28 Throttle Pressure. osig 0

0 0

O g

29 Throttle Temocrature. *F 0

0 0

0 d

30 Exhaust Pressure, InHe Abs.

0 0

0 0

f 31 Intake Water Tenio.. *F 0

0 0

0 32 33 Main Feecwater, M lb/hr 34 35 w

36 37 Full Power Cacacity, EFPO f3)

(4)

(4)

(4) 38 Accum Cycle Full Power Days. EFPO (4)

(4)

(4) s 39 Oil Fired for Generation, Gallons 7,380 5

40 Olt Heatina Value Bru/ Gal.

139,700 41 o" c n.rmtion. MWh 46.2 as Max. Hour Not Gen.

Max. Day Net Gen.

Load

~

MWh Time Date MWh Date Factor. %

=

c3 0

0 0

3 Remartes: A For BFNP this value is MWO/STU and for SQNP and WBNP this value is MWO/MTU.

j 2(t) indicates Thermal Energy.

1 3Information furnisned by Reactor Analysis Group, Gnattanocga 3

4 Administrative hold.

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- )j11 ] s #1. i 3l1

REACTOR POWER PERCENT DECEMBER 1987 j

UNIT 1 1

PERCENT t00 N

M 70 M

ADMINISTRATIVE HOLD 40 30 to 10 0

N 4*

b * * * * *O%N @ O @ f %* 4 %* %* f + 9 9 9 f f & f f f +

UNIT 2 PEACENT 100 90 M

70 M

g ADMINISTRAT!YE HOLD 40 30 20 10 0

N T*

b *

• S * *%% %% @ %* %b @ %* NS % %*f@@@@ff4@@ff UNIT 3 PERetst 100 90 M

70 M

ADMINISTRATIVE HOLD 40 30 20 -

10 0

N S*

b * * *

• 90%% % @ Y @ %' 4 %%Of@@@@fffffft 28

)

1 4

MAIXTEXAXCE SCMMARY

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ELECTRICAL TECHNICAL SECTION MONTHLY REPORT DECE'CER 1987 I.

WORK TIME SCHEDULE l

Received /

Assianed Comole.ted QAtB Red Folders J

2 8

Orange Folders 1

2 8

Yellow Folders 0

0 1

Blue Folders C

1 1

Purple Folders 0

0 1

Active Engineering Assignments 0

0 21 Engineering Backlog 0

0 76 New Engineering Assignments 0

0 0

Completed Engineering Assignments 0

1 0

II.

COMMITMENT TRACKING Licensing Issues (NCO & SLT)

NCO 1

9 26 SLT 0

1 4

PORS Tracking Items (BFC) 0 0

1 CAQRs 2

8 8

Average Age of CAQRs Three months and five days Employee Concerns 0

0 1

Sc.fety Issues List 0

0 0

III.

STAFFING LEVELS AND TRAINING Personnel Anoroved Headcounts Current Headcounts ASP 24 24 ATL 2

4 HTL 0

0 Contractors n

_6 TOTAL 37 34 IV.

OVERTIME 4.2%

V.

PROCEDURES i

l 1 procedures PORC approved 8 procedures sent to Word Processing i

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29 L.

.- -.. ~. - -

- ~

- =,..,

2 Electrical T::chnical Secticn Monthly Report Review of unit-1 and unit-3 fuse data sheets have been prepared.

Valve status has been put on the computer system for all 106 valves involved in unit-two start-up.

Limitorque valve status sheets are now controlled by the electrical technical section. They were controlled by the mechanical technical section in the past. This status also includes a bar graph to the plant manager on physical work, testing and signature analysis to show present valve progress.

Revised work plan 2225-87 to allow completion of the vork plan..

Completing field sketch which will aid in the installation of terminal block on 2-TCV-01056.

Updated P/2 schedule for drywell coordination meeting to reflect all work on drywell values which will need to be complete before lead shielding removal can begin.

74-07 valve was declared functional on 12/21/87 to support restart test program.

69-02 physical work is complete except for grade 5 motor thru bolt replacement. Valve vill be functional by early January.

CAQR's BTP-870126 and BFP-870092 were closed by the valve group in the month of December, 1987.

I l

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4 30

+

. -. ; m-m m.

.--o m - - --

m-m.-

ELECTRICAL TECHNICAL SECTION MONTHLY REPORT DECEMBER, 1987 Unit Common Major Routine Activities --

Performed inspection of unit two generator bushing box for stator cooling leaks. Two leaks were located on the exciter end of tne generator. A purchase request has been issued to bring General Electric technicians in-house to perform leak repairs.

During the inspections, a dusting of rust particles was found to be coming from the ends of the hydrogen header at the top of the generator. A General Electric generator specialist was brought in to evalutte the generator condition and make corrective recommendations. A report on his findings and recommendations is expected by January 4, 1988.

A Brown Boveri representative is on-site to install anodes in the unit 3 generator breaker as part of vendor improvement to prevent stress corrosion cracking.

Successfully completed D/G-D load acceptance testing for Systems and Restart test.

Completed two year review and submitted permanent change to EMI-100.

Submitted permanent changes to EMI-107 EMI-111 and EMI-120.

Reperformed discharge test on shutdown board "B" battery bank.

Battery capacity increased from 85% to 125%.

CIRCUIT BREAKER RIBUILDS:

4160V 480/250V Total number of breakers to be rebuilt 303 497 Total number of breakers rebuilt 9

13 Completed this month 0

3 Electrical Technical engineer attended pooled inventory management meeting in Houston, Texas.

500KV Trinity #2 line grounding switch 5291G continues out of service for lack of materials to make repairs.

Major maintenance was started on 500KV power circuit breaker 5214 (Unit 1 -

transformer bank breaker).

Puse Control Program BF 6.12, SEMI-42, EMI-92 and EMI-110 are in revision.

13 fuse labels remain to be placed. Unit 1 and unit 3 data sheets can be completed for EQIS data base revisions. These revisions vill show up in revision "D" of the fuse engraving report along with some additions from the drawing review effort and DRE/ contractor information. Revision "D" is expected in April or May. The fuse engraving report will eventually be replaced with a DNE output document called the fuse tabulation.

In January, fuse engraving report revision B labeling vill be completed and a fuse control training program vill be set-up.

At this time, most tech-spec instrument fuses should be located and placed in the electrical equipment list.

31 s.w

~~m~ mew _

~~--

l

[

i I&C TECHNICAL DECEMBER 1987 4

I.

Work Item Schedule Received /

Completed Open i

Assigned Red Folders 0

0 3

3 Orange Folders 1

0 8

Yellow Folders 0

0 0

Blue Folders 0

0 0

i G

Total Assignments Active Engineering Assignments 10 17 52 Engineering Backlog 23 1

II.

Commitment Tracking Licensing Issues (NCO & SLT)

NCO O

O 18 SLT 0

0 6

PORS Tracking Items (BTC) 0 0

3 DR 0

0 2

CAR 0

0 0

CAQR (0nsite) 0 0

12 CAQR (Off-site) 0 0

0 Average Age of CAQRs 5.9 months Employee Concerns 0

0 0

Safety Issues List 0

0 0

i t

III. Staffing Levels and Training Anoroved Headeounts Current Headcounts 4

Persoring1

.t i

ASP 17 12 ATL 4

5 HTL 0

0 Contractors 4

{

l TOTAL 21 21 l

j J

IV.

Overtime 9.81%

I V.

Procedures 24 procedures were sent to Word Processing

{

t r

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32

I&C TECHNICAL DECEMBER 1987 SUMMA 7Y The major activities of the month involved preparation of procedurec to support the retest schedule and the scheduled NRC SI review. Scaling and Setpcint Documcnts to support theas procedures are also being issued.

l l

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33 t.

MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT '

? (UNIT 0)

DECEMb.: 1987 Common No major nonroutine activities.

1.

Closed the following commitments:

a.

SEQ LER 327-87-060 - Inadequate D/G start caused by inadequate procedure.

b.

INPO SER 87-035 - Non-Isolable Reactor Coolant System Leak, c.

NCO 860287004 - Leaks Identified During Walkdown Control Air System, d.

BFC 861084002 - Inspect Springs of all Atwood & Morrill MSIVs.

e.

BFC 861084003 - Inspect Springs of all Atwood & Morrill MSIVs.

f.

SLT 870010001 - Miscellaneous Hardware Problems - Main Steam Tunnel.

g.

G-29(RO) - 1.M.1.2-10 Sht 3 & 4(RO) h.

G-29(RO) - PS 4.M.4.1 Add. 4(R4) 1.

G-29(RO) - PS 4.M.1.2 Add. 3'RO)

J.

G-20(RO) - PS 4.M.1.1 Add. 9(R10) k.

G-29(RO) - GT 1.1-1(R1) 1.

G-29(RO) - GT 1.1.2(R4) m.

G-29(RO) - GT 88.0-7(RO) n.

G-29(RO) - PF 1062(R2) o.

G-29(RO) - GT-SM11-0-3C(R2) p.

G-29(20) - TB 107.107-10(RO) q.

G-29(RO) - GT-SM11-0-2A(R2) r.

N-PT-8(RO) - Liquid Penetrant Examinacica s.

N-UT-38(R1) - Ultrasonic Examination of Safe-End Crevices Regions t.

N-VT-2(R7) - Visual Exe.mination of AW3 Structural Welds u.

N-VT-6(R2) - Visual Examination of Structural Wcid Using NCIG-01 34

MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)

DECEMBER 1987 v.

NQAM,III,2.2 QN(RO) - Receipt, Inspection, Handling, and Storage of Materials v.

NQAM,II,5.3A(R4) - Training Certification Program for QC Inspectors x.

NQAM,II,6.1(R4) - Generic Procedure y.

NQAM,II,6.l(R4) - Generic Procedure (We received and closed this blue folder twice in this month) z.

BFC 870086010 - Trending Program.- Engine Oil Cooler Performance 2.

The following instructions were approved, revised, or cancelled, a.

MMI-100 - Maintenance of Reactor Building Closed Cooling Water Heat Exchanger b.

MMI-147 - Surface Indication Removal c.

MMI-162 - Radioactive Waste Transport Trailer Maintenance d.

MMI Testing, Inspection, and Maintenance of the Air Supply System for the Main Steam Isolation Valves and the ADS Main Steam Relief Valves e.

MMI Preventive and Corrective Maintenance of Limitorque Operators f.

MMI-170 - Fuel Pool Cooling (FPC) Pump Maintenance, Units 1, 2, and 3 g.

MCI-0-032-VLV004 - Control Air Supply to Dryvell Check Valve CKV-032-333; Disassembly, Inspection, Rework, and Reassembly h.

MCI-0-033-CLR001 - Service Air System Compressor Aftercooler, Joy Model WNOL 112E; Disessembly, Inspection, Rework, and Reassembly i.

MCI-0-075-VLV002 - Core Spray Check Valves VLV-75-537A, 537B, 537C, and 537D; Disassembly, Inspection, Rework, and Reassembly J.

MCI-0-082-BL0001 - Standby Diesel Generator Blower Bearings; DJsassembly, Inspection, Replacement, and Rerssembly k.

MCI-0-032-CLR001 - Standby Diesel Engine Water Coolers; Disassembly, Inspection, Rework, and Reassembly 1.

MCI-0-082-PMP001 - Diesel Engine Scavenging Lube Oil Pump; Disassembly, Inspection, Rework, and Reassembly m.

MCI-0-085-VLV001 - Scram Pilot Valves FSV-85-39A or 85-39B; Disassembly, Cleaning, Replacement, and Reassembly 25

,L

. ~

~

MECHANICAL TECHNICAL SECTION MONTHLY REPORT COMMON UNIT ONLY (UNIT 0)

DECEM3ER 1987 n.

MCI-0-085-VLV002 - Inlet Scram Valve Disassembly, Valve Packing, Replacement Actuator, Diaphragm Replacement, Valve Seat Replacement, and Valve Reassembly o.

MCI-0-085-VLV003 - Outlet Scram Valve Disassembly, Valve Packing, Replacement Actuator, Diaphragm Replacement, Valve Seat Replacement, and Valve Reassembly 3.

The following CAQRs (Conditions Adverse to Quality Reports) were closed, a.

BFP 87-1020 - MMI-184.was PORC'd, USQD has not been reviewed.

b.

BFP 87-414 - Unit 1 RHR Heat Exchanger

'lB'.

c.

DFP 87-741 - Lack of Procedural Guidance to Perform Base Metal Weld

Repair, d.

BFP 87-770 - Pilot Scram Valves are to be torqued during reassembly.

4.

The Mechanical Technical Section devoted 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> to training during the month of December.

0919G 36

o MODIFICATIONS MONTHLY REPORT DECEMBER 1987 MAJOR WORK PERFORMED ECN NARRATIVE Appendix R P0671 Continued modification of existing fire suppression system.

P0808 Continued conduit and cab 1_e work on control power circuits.

P0883 Continued work on fuse protection of 250V DC trip circuits.

P0885 Continued conduit and support work on RB fire detectors.

P0879 Continued structural and electrical work on Phase III fire door modifications.

Environmental Qualification P3145 Continued electrical conduit sealing activities.

P3205 Continued small piping and support work on H02 2 analyzer lines.

Saismic Issues P0370 Continued structural work on seismic qualification and designation of block walls.

P0361 SMKI rework of torus attached piping supports (RRR and core spray systems) continued.

l P0859 Continued work on non-CRD attachments and catwalks R9 and 13.

i P0207 Completed craf t work on RFCI/RCIC platforms.

P0933 Continued seismic qualification.of Unit 2 RB elev 593-621 conduit.

P0998 Drywell catwalk upper elevation work l

continued on a concerted basis.

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MAJOR WORK PERFORMED

.ECN NARRATIVE HVAC Upgrade PC697 Continued installatirn of conduit, cable, and TMI Mods P0324 Continued electrical wot- ;u ingh-range

?

containment radiatica monitors.

Appendix J P0792 Piping and valve work and hydres ccmpleted; remaining workplan in.closecut cycle.

P0795 Physical work (valves and piping in core spray system) complete; workplans in closecut.

P0959 Support installation continued on RBCCW system.

P0965 HPCI valve and support work continued.

P0963 Completed craft work on CAD valve and supports.

Other

. P0286 Continued work on yard security lighting.

P0284 Continued fabrication and installation of' seismic conduit supports for the acoustic monitoring system.

P0392 cont'inued SMMI rework of scram discharge volume supports.

P0569 Continued support work on RPV vent line.

P0720 Continued work of jet pump instrumentation lines.

P0956 Contit.ued installation of duct and duct supports for new shutdown board room HVAC.

PS291 Continued seismic support work on reac*.or water level instrument sensing lir...

P5434 Continued piping and suppott voix e,n tc;rus narrow range water level instrumentation.

38 i

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CHEMISTRY

SUMMARY

DECEMBER 1987 Primary Coolant Chemistry Unit 1 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month.

Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technfcal specification and fuel warranty limits for conductivity and chloride have not been exceeded.

Unit 2 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month.

Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conduccivity and chloride were exceeded in early May during vessel flood up after safe end repair as described in LRED 87-2-218 and LRED 87-2-220.

Unit 3 The conductivity of the reactor coolant remained within technical specification and fuel warranty limits during the month.

Chloride concentration and pH of the reactor coolant remained within technical specification and fuel warranty limits during the month. This calendar year, the technical specification and fuel warranty limits for conductivity and chloride have not besn exceeded.

l l

42

~.

- --->- - - seaw _ _ w. _ _ n m _ m n.--

\\

PRIMARY COOLANT CHEMISTRY DECEMBER 1987 Parameter Unit 1 Unit 2 Unit 3 1.

Gross Radioactivity a.

Crud (filter) (pci/ml)

High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A b.

Filtrate (pci/ml)

High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 2.

Milipore Iron (Fe. ppb)

High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 3.

Tritium (pci/ml]

High 8.28E-05 7.8SE-05 1.51E-04 Low 7.35E-05 7.07E-05 1.33E-04 Average 7.73E-05 7.55E-05 1.43E-04 4.

Iodine-131 (pel/ml)

High 0

0 0

Low 0

0 0

Average 0

0 0

5.

Iodine-131: Iodine-133 Ratio High N/A N/A N/A Low N/A N/A N/A Average N/A N/A N/A 43

1 PRIMARY COOLANT CHEMISTRY (Continued) i DECEMBER 1987

)

Parameter Unit 1 Unit 2 Unit 3 6.

Chloride (ppb)

High (10

<10

<10 Low

<10 (10

<10 Ave, rage

<10

<10

<10 7.

pH@25*C High 6.5 6.2 6.4 Low 5.8 5.8 5.8 Avers;c 6.0 5.9 5.9 8.

Conductivity (pmho/cm025 C)

High 0.19 0.92 0.45 Low 0.12 0.69 0.11 Average 0.15.

0.79 0.21 I

l l

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_m.

.m.

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CHEMISTRY

SUMMARY

(Continued)

DECEMBER 1987 Environmental Technical Soecification Reauirements The ambient upstream river temperature (24-hr. avg max) averaged 50.8'F andranhedfrom53.8'FonDecember1to48.7*FonDecember31. The dcwnstream temperature ranged from 53.7'T on December 1 to 48.6*F on December 31 and averaged 50.4*F.

The greatest temperature change was 1.4*F on December 8.

Maintenance work on the sedimentation pond dike (DSN102) continued in December.

It was necessary to discharge accumulated precipitation on December 28 and 29.

This discharge was in compliance with the UPDES permit limits.

Compliance problems were experienced with the discharge from the unit 1 and 2 office building drain (DSN110). Three non complying discharges on December 21, 25, and 27 had total suspended solid (TSS) concentration of 188, 117, and 457 mg/L exceeding the permitted limit of 100 mg/L.

The discharge from the sewage lagoon exceeded the NPDES permit limit of 45 mg/L for BOD n December 7 when the BOD e ncen ra n reac e 50 mg/L.

5 5

The average daily flow was 46,005 gpd and the maximum flow 60,192 gpd on December 8 BOD e neen rat n averaged 29 mg/L. The TSS concentrations 5

ranged from 24 mg/L on Decmeber 28 to 31 mg/L on December 7 and averaged 27 mg/L.

l 45

AIRBORNE RELEASES (1)

DECEMBER 1987 i

SUMMATION OF ALL RELEASES UNIT THIS MONTH A.

FISSION AND ACTIVATION GASES 1.

TOTAL RELEASE CI 3.14E-01 2.

AVERAGE RELEAUF RATE FUR PERIOD UCC/SEC 1.04E-01 3.

PERCENT OF TECH. SPEC. LIMIT (0.05 CI/SEC) 2.08E-04 B.

IUDINES 1.

TOTAL IODINE - 131 CI

< 3.50E-05 2.

AVERAGE RELEASE RATE FOR PERIOD UCI/SEC

< 1.16E-03 3.

PERCENT OF TECH. SPEC. LIMIT (0.40 UCI/SEC) 0.CJE-01 C.

PARTICULATES 1.-

PARTICULATES WITH HALF-LIFES > OR ' 'l0 8 DAYS CI 1 8SE-04 2.

AVERAGE RELEAUF RATE FOR PERIOD UCI/SEC.

6.23E-03 3.

PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 1.56E-02 4.

GROSS ALPHA RADI0 ACTIVITY CI 2.16E-06 D.

TRITIUM 1.

TOTAL RELEASE CI 2.00E-02 2.

AVERADE RELEA3E RATE FOR PERIOD UC(/SEC 6.63E-03 3.

PERCENT OF TECH. SPEC. LIMIT (2.19 UCI/SEC) 3.03E-01 4.

UROUNO LEVEL RELEASE CI 1.91E-02 0.

ELEVATED RELEASE CI 9.27E-04 (1)

REPORTIllu PERIOD 35 DAYS 46

AfRBORNE RELEASES (CONTfNUED)

DECEMBER 1987 ELEVATED RELEASES Ac FISSION GASES UNIT THIS MONTH KR-85M CI

< 7 50E-02 KR-85 CI 3 14E-01 KR-87 CI

< 6.97E-02 KR-88 CI

< J.21E-01 XE-133 CI

< 2.26E-01 XE-135M CI

< 2.55E-01 XE,135 CI

< 5.83E-02 XE-138 CI

< 4.38E-01 OTHERS(SPECIFY)

TOTAL FOR PERIOD CI 3.14E-01 B.

10 DINES I-131 CI

< 4.63E-06 I-133 CI

< 4.56E-05 I-135 CI

< 4.59E-02 TOTAL FUR PERIOD CI

< 4.60E-02 47

AIRBORNE RELEASES (COHTINUED)

DECEMBER 1987 ELEVATED RELEASES C.

PARTICULATES UNIT THIS MONTH SR-89 CI

< 3.29E-07 SR-90 CI

< 1.56E-07 CS-134 CI

< 1 49E-06 C3-137 CI

< 4.06E-06 BA-140 CI

< 1.15E-05 LA 140 CI

< 1.67E-06 OTHERS(SPECIFY)

TOTAL FOR PERIOD CI

< 2.00E-05 D.

TRITIUM CI 9.27E-04 l

48 m

.x._....

i___..

.,.... s.. c ;

., m, m

AZRBORNE RELEASES (CONTfHUED)

DECEMBER 1987 j

GROUHU RELEASES A.

FISSION GASES UNIT THIS MONTH l

KR-85M CI c 4.70E-01 KR-85 CI

< 1.30E 02 KR-87 CI

< 1.08E 00 KR-88 CI 9.71E-01 XE-133 CI

< 1.22E 00 XE-135M CI

< 6.81E-01 XE-135 CI

< 2.4DE-01 XE-138 CI

< :3. 70E 00 l

OTHERS(SPECIFY) i l

TOTAL FOR PERIOD i

CI

< 1.38E 02 B.

IODINES l

I-131 CI

< 3.04E-05 I-133 CI

< 6.80E-04 I-135 CI

< 8.86E-01 TOTAL FOR PERIOD CI 8.87E-01 l

l I

43 s

e..

AIR 80RtlE RELEASE:1 (CONTINUED)

DECEMBER 1937 GROUND RELEASES C.

,FARTICULATES UNIT THIS MONTH SR-89 CI

< 2.26E-06 SR-90 CI

< 1.56E-06 CS-134 CI

< 2.96E-05 CS-137 CI

< 2.60E-00 BA-140 CI

7.65E-05 LA-140 CI

< 2.70E-0G OTHERS.(SPECIFY)

CO-60 CI 1.SSE-04 TOTAL FUR PERIOD CI 1.38E-04 D.

TRITIUM CI 1.71E-02 l

t l

l l

l 50 u-

BROWNS FERRY NUCLEAR PLANT MONTHLY NEPORT CALCULATIONS LIGUID RELEASES DECEMBERs 19S7 RADI0 ACTIVE LIQUID EFFLUENTS 1.

GROSS RADI0 ACTIVITY UNITS a)

(OTAL RELEASE CURIES 2.47E-02 b)

AVERACE DILUTED CONCENTRATION RELEASED UCI/ML 2.40E-09 e)

PERCENT OF APPLICABLE LINIT (1E-07 UCI/hl) 2.40E 00 2.

TRITIUM a)

TOTAL RELEASE CURIES 4.98E-02 b)

AVERAGE DILUTED CONCENTRATION RELEASED UCI/ML 4.33E-0?

c)

PERCENT OF APPLICABLE LIMIT (3E-03 UCI/ML) 1.61E-04 (1) 3.

DISSOLVE 0 NOBLE GASES a)

TOTAL RELEASE CURIES

< 9.04E-04 b)

AVERAGE DILUTED C0ilCENTRATIOil RELE ASED UCI/ML s 8.77E-11 e)

PERCENT OF APP.ICADLE LIMIT (2E-04 UCI/hL) 4.37E-05 s

4.

GROSS ALPlA RADI0 ACTIVITY a)

TOTAL REL EASE CURIES 6.52E-04 b)

AVERAGE DILUfED CONCENTRATIUil RELEASED UCI/ML 6.32E-11 3.

VOLUME OF LIQUID WASTE TO DISCHARGE UANAL LITERS

?.6CE 06 6.

VOLUME OF DILUTION WATER LITERS 1.03E 10 (1)

INCLUDES X5-133, Xc-135, AND OTHERS

[

51

BROWNS FERRY NUCLEAR PLANT HONTHLY REPORT CALCULATIONS L IQU CI) RELEASES DECEMBER, 1987 ISOTOPES RELEASED UNITS CI CR-51

<. 2.1 C F. - O '

MN-34 3.65E-05 CO-58

< 1.87E-04 FE-39

< 3.58E-04 CO-60 3.19E-03 ZN-65 1.24E-03 NB-95

< 1.88E-04 ZR-9'S

< 3.47E-04 MOTC-99M

< 1.95E-04 I-131

< 2.96E-04 XE-133

< 7.50E-04 CS-134 4.52E-03 XE-135

< 1.54E-04 CS-137 1.57E-02 BA-140

< 9.98E-04 LA-140

< 9.63E-05 CE-141

< 3.38E-04 SR-89

< 3.50E-05 SR-90

< 3.43E-00 52

.,....+ <

.c....

~_

o BROWNS FERF.Y NUCLEAR PLANT MONTHL.Y REPORT CALCULATIOl4S LIQUID RELEASES DECEMBERi 1937 OTHERS UNITS

~

CI SS-125 1.76E-05 CE-144 2.70E-05 53

i BROWNS FERRY NUCLEAR PLANT MONTHLY REPORT CALCULAlIONS LIGUID RELEASES DECEMBER, 1987 LAUNDRY DRAIN VOLUME RELEASED:

11196.3 GALLONS FLOOR DRAIN VOLUME RELEASED 644601.7 GAL LONS UASTE SAMPt.E TAHK VULUME RELEASED:

3 6 3.1 3, 1 GALLONS DISTILLATE TANK VOLUME RELEASED:

0.0 0ALLONS LOC A TIull GTHER THAN RADWASTE VOLUME RELEASED:

0.0 GALLONS TOTAL VOLUME RELEASED TO THE RIVER:

692103:3 GALLONS HIGHE3T BATCH ACTIV(l'Y RELEASED FOR MONTH:

1.6SE-03 UCI/ML A/D LONGEST RELEASE TIME FOR MONTH:

345 lilNU T E S SHORTEu r RELEA3E TII;E FOR MONTH:

200 MINUTES TOTAL TIME OF RELEASES FDR MONTH:

.6810 MINUTES AVERAGE TIiW FOR BATCH RELEASES:

262 MINUTE 3 COMPOSITE INFORMATION:

COMPOSITE CI AFTER DILUTION UC(/ML RELEASED UCI/ML SR-89

< 2,10E-08

< 3.50E-05

< 5.3dE-12 SR-90

< 1.31E-08

< 3.43E-0U 3.33E-12 H-3 1.90E-05 4.93E-02 4.3dE-07 OROSS ALPHA 2.49E-07 6.52E-04 6.32E-11 NUilBER OF BATCHES REl. EASED:

26 NUMBER OF ADMINISTRATIVE LlHIT VIOLATIONS:

0 NUMBER OF TECHNICAL SPECIFICATION VIOLATIONS:

0 54

RESIN USAGE REPORT DECEMBER 1987 RESIN CONSUMED (CU.FT.)

"~

% of Total atad POWDEX ECODEX ECOSORB EPIFLOQ Total Radwaste Floor Drain Filter 43.9 0

78 0

0 36 114 Waste Demineralizer 0

0 0-0 0

0 0

Waste Filter 38.5 0

84 0

16 0

100 Fuel Pool Demins 7.7 0

20 0

0 0

20 Reactor Water Cleanuo Unit 1 0

0 0

0 0

0 0

Unit 2 6.1 0

16 0

0 0

16 Unit 3 0

0 0

0 0

0 0

Cond. Demins Unit 1 0

0 0

0 0

0 0

Unit 2 3.8 0

10 0

0 0

10 Unit 3 0

0 0

0 0

0 0

Totals 100 0

208 G

16 36 260 l

55

l 1

I FUEL CLADDING INTEGRITY PARAMETERS DECEMBER 1987 Unit 1 l

Reactor Water Iodines (uci/sec.)

l Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (uci/sec)

DAll E12M MH1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 2 Reactor Water Iodines (uci/sec.)

Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (uci/sec)

Date Flow HH1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage Unit 3 Reactor Water Iodines (uci/sec.)

Date I-131 I-132 I-133 I-134 I-135 Unit in Outage Fission Gases at Discharge of SJAE (uci/sec)

Date E12M MH1 Xe-138 Kr-87 Kr-88 Kr-85m Xe-135 Xe-133 Unit in Outage L

I l

56

s WASTE TREATMENT SYSTEM Tifl00GPUTS r

DECEMBER 1987 i

i FLOOR FLOOR FLOOR i

(

DRAIN DRAIN DRAIN

, 3,,,,

,,g.

b 1

GE: 6.61E+E COLLECTOR FILTER

~

SAMPLE GE: 6.45E+05 i

TANK TANK (23 art: 114.00 t

GAL: 6.61E+05 I

I M 5.14E+02 y

i f LAUNDRY g

S GAL: 1.59E+04 GPa 3.61E+02 l

DRAIN

,y,,,,gg,0 CANAL TANK R 2.23E 5 R 2.66Em f

GAL: 6.92E+05

,,, y o3 i

acrufD MTDs WD: 0.00E+00 l

~

GE: 0.00E+00 d

E l f UI f WASTE WASTE 4

WASTE WASTE GPa t. m 03

~

COLLECTOR SAMPLE f

GE: 3.63E W FILTER DEMINERALIZER TANK TANK (il cuFT: 100.00 (3) QFT:

0.00 Ga: s.42E+05 to art pomet 84.00.cuFT msIN & FIBER MIXTURE-0.00.cuFT Ec0 SORT 16.00 CONDENSATE 2.EW e an m 7s.00.aH RESM E FIBER NIXTURE: 36.00. AFT ECDSORB:

0.00 GAL.: 8.06E+05 STORAGE C3 BEAD mSIN TANK.

[

TESTING

SUMMARY

DECEMBER 1987 Surveillance Testing Unit 0 A total of 136 surveillance tests were completed per 48 different test instructions.

Unit 1 A total of 102 surveillance tests were completed on unit 1 per 36 different test instructioas.

Unit 2 A total of 167 surveillance tests were completed on unit 2 per 18 different test instructions.

Unit 3 A total of 101 surveillance tests were completed on unit 3 per 23 different test instructions.

Changes. Test. and ExDeriments Reauiring Authoritation From the NRC Pursuant to 10 CFR 50.59(a)

There was one revision for unit 1, 2, and 3 technical specifications.

58

t TESTING SUlftARY (Continued)

DECEMBER 1987 Channes. Tests. and Exceriments not Recuirinn Authorization from NRC Pursuant to 10 CPR 50.59(a)

There were three special tests completed for this month.

ST-8723 Test Descriptiont To obtain data on the diesel generator excitation system. This data will be used in completias the dynamic analysis of the diesel generator system.

(Refer tc sections 1.0 and 3.0 for additional description / purpose / test method).

ST-8729 Test

Description:

Test provides instructions for determining the optimum disposal technique for contaminated mops and rags utilizing the drum compactor.

ST-8735 Test

Description:

The basis of this special test is SI-4.9.A.1.b.4 diesel generator

'D' emergency load acceptance test. 4KV shutdown board

'D',

j Diesel generator auxillary board

'B', 4&OV shutdown board 2B and motor generator sets 2DA and 2EN unloaded will be the loads powered by diesel generator 'D' during this test.

d l

l 59

T"STING

SUMMARY

DECEMBER 1987 Surveillance Testina URjl Q A total of 136 surveillance tests were comp'eted per 48 different cast instructions.

Unit 1 A total of 102 zurveillance tests were completed en unit 1 per 36 different test instructions.

Unit 2 A total of 167 surveillance tests were completed on unit 2 per 18 different test instructions.

Unit 3 A total of 101 surveillance tests were ccepleted on unit 3 per 23 different test instructions.

Channes. Test. and Exoeriments Recuirina Authorization From the NRC Pursuant to 10 CFR 50.59(a)

There was one revision for unit 1, 2, and 3 technical specifications.

i 58

5 TESTING

SUMMARY

(Continued)

DECEMBER 1987 i

Channes Tests. and Exneriments not Reauirinn Authorization from NRC Pursuant to 10 CFR 50.59(a)

There were three special tests completed for this month.

ST-8723 Test

Description:

To obtain daen on the diesel generator excitation system. This data will be used in comp eting the dynamic analysis of the diesel generator system.

(Refer to sections 1.0 and 3.0 for additional description / purpose / test method).

$T-8729 rest

Description:

Test provides instructions for determining the optimum disposal technique for contaminated mops and rags utilizing the drum cor iactor.

ST-8735 Test

Description:

The basis of this spacial test is SI-4.9.A.1.b.4 diesel generator

'D' emergency load acceptance test. 4KV shutdown board

'D',

Diesel generator auxillary board

'B', 480V shutdown board 2B and motor generator seta 2DA and 2EN unloaded will be the loads powere; t:y diesel generator

'D' d'; ring this test.

I 4

4 59

REACTOR VESSEL FATIGUE USAGE EVALUATION The cumulative usage factors for the reactor vessel are as follows:

Usane Factor Location Unit 1 Unit 2 UniQ Shell at water line 0.00620 0.00492 0.00431 Feedwater nozzle 0.29782 0.21319 0.16139 i

Closure studs 0.24204 0.17629 0.14360 t

b l

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l l

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OPERATIONS SUMMARI (Ccntinued)

DECEMBER ~1987 Channe in Procedure There were 130 revisions to plant instructions during the month; 122 instructions were changed primarily for correction, and the remaining 8 revisions related to safe operation of the plant.

ChADie in Facility Design Packare NqmhgI Description Safety Related ECN P5016 - Reactor (WP 2079-35) - Documented the removal Recirculation System -

of the 4" bypass line and tne associated Unit 2 saubbera SS-9 Loop A and B which were removed under ECN L1633. Also, documented the removal of the. snubber support brackets which were removed by MRs to facilitate veld overlay repairs.

Based on the results of DNE calculations, the pipe break analysis is still valid, and the seismic analysis was not adversely affected by the modification.

The ECN was completed for unit 2, was previously completed on unit 3 but was only partially implemented on unit 1.

ECN PS309 - Cable Tray Support (WP 2184-85) - Performed modifications System - Unit 2 required to seismically qualify affected cable tray systems for unit 2 9tartup and interim operation. This work plan covered the cable tray supports at the Intake Pumping Station and the unit 2 Cable Spreading Room.

W. P. 2180-85 covered from the cable tray tunnel (rectangular portion of tunnel from the intake structure to the plant).

The modifications assure that the affected cable trays meet the seismic qualifications of seismic class I cable tray / supports for unit 2 start-up and interim operation.

The ECN was completed.

61

(

=

OPERATIONS

SUMMARY

(C ntinued) 4 DECEMBER 1987 i

Packare Numhgr Descriotion Safety Related ECN P0896 - High Pressure (WP&IR 2149-86) Prefabricated supports at Fire Protection System -

ASC0A fab shop for installation in the unit 2 Unit 2 reactor building.

(WP&IR 2150-86) - Installed piping and supports in t!e unit 2 reactor buildings, elevation 59?.

(W?&IR 2098-87) - Fabricated and installed rigid supports in unit 2 reactor building, elevation 593'.

The additional pipings, sprinklers, and supports did act degrade safety related equipeent. Since the modification improved fire protection in the unit 2 reactor buildings, the margin of safety was not reduced.

The ECN was completed.

ECN P0894 - High Pressure (WP&IR 2144-86) % Installed piping and Fire Protection System -

supports in the unit 2 reactor building, Unit 2 elevation 541'.

The additional piping, sprinklers, and supports did not degrade any safety related equipment. The modification improved fire protection in the unit 2 reactor building, therefore, the margin of safety wau not reduced.

The ECN was completed.

l J

62

_= = m e, m - cm_m =-#m m m ~,

m e w ~.sm m,

--;c

~ m

~.

e OPERATIONS

SUMMARY

(Ccntinusd)

DECEMBER 1987 Packaae Number Dr_w rintion

__ y Saf.?ty Related ECN P0895 - High Pressure (WP&IR. 2146-86) - Prefabricated supports at Fire Protection System ASCOA fab shop for installation in unit 3, Unit 2 (WP&IR 213.7-86) - In. stalled piping and i

aupporta in unit 2 reactor building elevation 565'.

(WP&If 2097-87) - Fabricated and inG:alled rigid supports insta11atica in unit 2 reactor

butiding, The installation of the automatic sprinklers provides direct fire protection for' equipment located in unit 2.

No fedu:tidn in the margin of safety is foreseen.

Ihe EON was completed.

h 0

-~

4 9

OPERAr.'ONS

SUMMARY

(Continued)

DECEMBER 1987 Easkare Hungt Descrintion

\\

Non-Safety Related ECN P5432 -

(WP&IR-0044-86) - Pulled fiber optic cable Communications Common from communications in Control Bay to medification building and the new training

center, i

The ECN was not completed.

DCN B0001'A - Plant (WP&IR 00,.-87) - Replaced 120V time delay Non-Preferred 120V relay "W".n the Plant Mon-prefett.d transfer AC Battery Board-Common switch with a 240V relay.

The DCN was totally compelted.

I d

7 l

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.g

... g w -..

o PLANT INSTRUCTION REVISIONS DFCEMBER 1987 Catenorv Ins t ruc tion Reason for Reouest Change in.

SDSP 2.1 Site Procedurs Implement Technical Specification Response to and Instructions Admendments 138 (U1),134 (U2), and LER, IE 109 (U3) providing for Technical Bulletin, NRC Review or certain procedures Inspection instead of PORC review.

RCport, OPQA Audit, etc.

SDSP 2.11 Implementation Implement Technical Specification and Change of Site Procedures Admendments 138 (U1), 134 (U2), and and Instructions.

109 (U3) providing for Technical Review of certain procedures instead of PORC review.

SDSP 12.1 Restart Test Incorporate SDSP 27.1 Corrective Program actions for CAQRs BFQ-870534 and BFQ 850541, and procedure imprevements from Incident Critig :o 87-041.

SDSP 12 2 Development of Incorporate SDSP 27.1 Cctrective System Test Specifications actions for CAQRs BFQ-870534 and BFQ 870541, and procedure improvements from Incident Critique 87-041.

SDSP 23.2 Radioactive Source Change responsible section from Control Chemical Technical to RADCON clarification per NRC/C LER 259/87017.

SI 4.8.B.2-2 Airborne To add attachments for alpha Effluent - Particulate activity calculations and steps F41ter Analysis (monthly to tie the SI to the CI.

To delete gross alpha).

ITC-02. NRC/C IE report 87-30.

RWI 151 Verification of New procedure to provice for the Radioactive Waste Package Inspection of radwaste packages Contents (Non-Compacted) containing non-compacted materiti in order to ensure compliance with all applicable re clations and a

requirements.

RWI 152 Verifi, cation of New procedure to provide for Radioactive Waste Package the inspection of radwaste packages Contents (Compacted) containing compteted material in order to ensure compliance with all applicable regulations and reruirements.

65

-e s

t CHANGES IN PLANT ORGANIZATION 1

DECEMBER 1987 4

There vere two changes in plant staff for those positions designated as key i

supervisory positions, Donald E. Hosmer, Project Manager, Site Director's Staff, Mark B. Whitaker, Jr., Manager, Operational Readiness Review Staff.

1 J

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i 66 L.a c. - - -,.. - _. - a - + ;_ - = - - = ~..,,

.__e--

0 1

ACCIDEffrS There was one inss-of-time accidents during the month.

67

.