ML20032E362

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Monthly Operating Repts for Oct 1981
ML20032E362
Person / Time
Site: Surry  
Issue date: 11/09/1981
From: Dunn S
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20032E358 List:
References
NUDOCS 8111200464
Download: ML20032E362 (40)
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Text

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l VIRGINIA ELECTRIC AND P0k'ER COMPANY SURRY POk'ER STATION MONTHLY OPERATING REPORT REPORT NO. 81-10 OCTOBER, 1981 APPROVED BY:

hk)t 6R T STATION MANAGER l

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8111200464 811113 PDR ADOCK 05000280 R

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Section P_,ag e Operating Data Report - Unit #1 1

Operating Data Report - Unit #2 2

Unit Shutdowns and Power Reductions - Unit #1 3

Unit Shutdowns and Power Reductions - Unit #2 4-Load Reductions Due to Environmental Restrictions - Unit #1 5

Load Reductions Duc to Environmental Restrictions - Unit #2 6

Average Daily Unit Power Level - Unit #1 7

Average Daily Unit Power Level - Unit #2 8

Su= mary of Operating Experience 9

Amendments to Facility License or Technical Specifications 11 Facility Changes Requiring NRC Approval 12 Facility Changes That Did Not Require NRC Approval 12 Tests and Experiments Requiring NRC Approval 14 Tests and Experiments That Did Not Require NRC Approval 14 15 Other Changes, Tests and Experiments 16 Chemistry Report 17 Description of All Instances Where Thermal Discharge Limits Mere Exceeded 18 Fuel Handling Procedure Revisions That Changed the Operating Mode Described in 22 the FSAR Description of Periodic Tests Which Were Not Completed Within the 23 Time Limits Specified in Technical Specifications 24 inservice Inspection 25 Reportable Occurences Pertaining to Any Outage or Power Reductions Maintenance of Saf ety Related Systems During Outage or Reduced Power 26 Periods - Unit #1 - Mechanical Maintenance Maintenance of Saf ety Related Systems During Outage or Reduced Power 28 Periods - Unit #2 - Mechanical Maintenance t'

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Maintenance of Safety Related Systems During Outage or Reduced Power 30 Periods - Unit #1 - Electrical Maintenance tuintenance of Safety Related Systems During Outage or Reduced Power 32 Periods - Unit #2 - Electrical Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 34 Periods - Unit #1 - Instrument Maintenance Maintenance of Safety Related Systems During Outage or Reduced Power 36 Periods - Unit #2 - Instrument Maintenance Health Physics Sitmary 38 Procedure Deviations reviewed by Station Nuclear Safety and 39 Operating Committee af ter Time Limits Specified in T. S.

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OPERATING DATA REPORT DOC.527 NO. 50-280 DATE 11-09-81 CDA!PLETED BY Sue D. Durat TELEPHONE (804)357-3:84 J

OPERATING STATUS Notes Surry Unit //1

1. Unit Naine; -

10-01-81 through 10-31-81

2. Reporting Period:

2441.

3. Licerned Thermaj Power (MWr): __

847.5

4. Nsioeplate Rat.ing (Grou MWe): _

788

5. Design Eleerrical Rsting (Net MWe):

811

6. Muimum Dependable Capacity (Grou MWe):

775

7. Sluircum Dependable Capacity (Net MWe):
8. If Changes Occur in capacity Ratings (Irems Number 3 Through 7) Sine: ! ss: Report. Give N/A
9. Power Level To Which Restricted If Any het MWe):

N/A

10. Reasons For Restrictioru,If,Any: -

2 This Month Yr to-Dare Cumubtive r

745.0 7296.0 77664.0

11. Hours in Reporting Period 617.1 2339.8 44878.3
12. Number'Of Hours Redctor Was Critical 3731.5
13. Rescror Reserve Shutdown Hours -

O s0 612.4 2277.5 43946.3 3736.2 14.- Hours Genentor On-Line O

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15. Unit Reserve Shutdown Hours 1474194.0 5278025.8 101667426.8
16. Cron The: mal Energy Generated (MWH) 466025.0 1686980.0 32988723.0
17. Grou Electric 2! Energy Generated (MWH) 441630.0 1591181.0 31291105.0
13. Net Elecrical Energy Generated (MWH) l l
19. Unit Service Facror 82.2%

31.2%

61.4%

f

21. Unit Cspecify Factor (Using 5!DC Net).

76.5%

28.1%

52.0%

0.WnAM:W b etor l

22. Unit Capacity Factor (Using, DER Net) 1.5%

5.1%

25.5%

23. Urti Forced Outs;e Rare I
24. Shuidowns S:heduled Over Next 6 Months iType.Date. mad Durstion of Eschi:

Spring Maintenance 19 10 days

25. If Shut Down At End Of Report Period. Estimated Date of Sr.strup:

I Forecas Achie,ed

26. Units In Test Surus (Prior so Commercial Operari*nli INITI A L CRITICA LITY

\\

INITIA L ELICTRICITY

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COMMERCIAL OPER ATION l

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OPERATING DATA REPORT DOC.527 NO. 50-281

. D.2TE 11-09-81 C05fPLITED SY ue D. Dunn S

TELEPHONE (804) 357-3184 OPERATING 5TATUS Notes Surry I! nit #2

1. L.. N. rut. s.m e:

i 10-01-81 throuth 10 ti n1

2. Reporting P:riod: _

2441 I

I

3. Lic: rued Thermal Po-cr (MW ): __ 847.5

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4. Namep12tc Rat.ing (Cross 3!We): _

'/55

5. Design Electrical Rating (Net.41We):

811

6.. Maximum Depen 6ble Capacity (Cross Siwe):, 775 4
7. 512ximum Depen 6ble Capacity (Net afWe):
8. If Changes 0: cur in Capscity Ratings (Items Number 3 Through 7) Since Last Report. Give Reason N/A N/A f
9. Power Levello Which Restricted,If.Any (Net MWe):
10. Reasons For Restrictions,If Any: -

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This Month

. Yr to-Date.

Cumu!stive v

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i 745.0 7296.0

. 74544.0

11. Boun In Reporting Feriod -

745.0 6864.8 44648.5

12. Number'Of Houn Re5ctor Was Crit.ics! -
13. Reactor Reserve Shutdown Houn -

0 0

745.0 _

6824.4 43961.0

14. Houn Genentor On.Line 0

0 0

15. Unit Reserve Shutdown Hours 1788172.0 16489466.4 102944127.4
16. Cross Thenna! Energy C-nerated (MWH) 576755.0 5324420.0 33563414.0

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17. Gross Electrics! Energy Generated (MWH) 545305.0-5042855.0 31521373.0 1S. Ne: Electrics! Energy Generated (MWH) 100%

93.5%

59.0%

19. Unit Service Factor 100%

93.5%

59.0%

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21. Urdt Capacirv Factor (Using.\\lDC Net).

94.4%

89.2%

55.1%

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20. Unit Availability Factor

'*2A i

22. Unit Capscity Factor (Using DER Net) 0%

1.0%

17.3%

23. Uni Forced Outa2e Rate
24. Shuidowns Scheduled Over Next 6 Months (Type.Date.snd Durstion of Esch):

).

Refueling 06 42 days y

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25. If Shut Down As End Of Report Period.Esiimated Date of 5ts tup:

Forecast Achiesed

26. Uniis in Tes Status (Prior io Commerris] Operationi:

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INITI A L CRITICA LITY INITIA L ELIC731 CITY i

COMMERCIAL OPER ATION i

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50-280 I)oCKET No.

UNIT SilUII) OWNS AND l'0WER REI)UC110NS UNII NAME -Surry Unit #1 l

IDATE _11-03-31

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COMPLETED ilY Sue D. Dunn REPORT MONill OCTOBER, 1981 1ELEPil0NE (804)357-3184 ext. 477

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$E 3

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Licensee

$g Cause & Corrective l

No.

Date Q

53 235 Event y

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Action to Repori**

wU Present Recurrence

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1 81-15 10-01-81 S

123.1 11 4

continuation of shutdown for Auxiliary Feedwater System leak repairs which began 09-20-81.

81-16 10-06-81 F

9.5 11 3

"A" Main feed regulating valve stuck open while increasing power a eter startup causing trip on "A" y

S/G high level. The problem was corrected and the valve tested prior to reactor startep.

81-17 10-15-81 F

0.0 11 4

Loss of turbine power experienced due to problem vith EllC System.

l Problem corrected and power returned to 100%.

l 2

3 4

f: forced Reason:

Method:

Exhibit G. Instructhms 5: ScheJuled A Equipment failure (Exrlain)

I. Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling

3. Automatic Scum Event Repore (LER) File (NURI.G.

D-Regulatory Restviction 4-Other IE xplain) 01611 E-Operator Training & IJcense Examination F Administrative 5

Eshibit I - Same Seura G-Operaimnal Error (Explain) l's/77 )

ll Other (Esplain t

i 50-281 UNIT SilUlllOWNS AND POWER REDUCTIONS DOCKET NO.

UNII NAME Surry Unit #2 liA1E TI-U3-Ul REPOR1 MONill OCTOBER, 1981 COMPl.ETED RY Sue D. Dunn TEl.EPIIONE 7 804) 357-3H4 ext. 477 s

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7sM l.icensee 5%

5"L e

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_m e Cause A Corrective

-o No.

Date r;

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Action to jg Repost,e

,# 0 u

$E Prevent Recurrence e

d 81-15 10-11 F

0.0 11 4

Three brok.n wires on #1 GV Valve for the main turbine caused valve to co closed causing loss of 7

turbine power from 655 We to 278 We The wires were replaced.

I 2

3 4

l': Forted Reason:

Method:

Exhibit G-Instructhms S Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data n Maintenance of Test 2-Manual Scram.

Entry Sheets for I.kensee C. Refueling 3-Automatic Scrar.i.

Event Repint II.l:R)l'ile INURI.G-D Regulatory Restriction 4-Other (Explain) 0161)

E Operator Training & IJeense Examination F. Administrative 5

C Operational Error (Explain)

Exhibit 1 Same Soorte p8/77)

Il Other I E xplain) el

LOAD REDUCTIONS DUE TO ENVIR0hMENTAL RESiRICTIONS UNIT NO.1 MONTH: OCTOBER, 1981 i

fDATE TI!E HOURS LOAD, W REDUCTIONS, W WH REASON None du-ring this reporting period.

MONTHLY TOTAL 0

i 1

LOAD REDUCTIONS DUE TO ENVIRONMD;TAL RESTRICTIONS UNIT NO.2 MONTH: OCTOBER, 1981 DATE TIME HOURS LOAD, E' REDUCTIONS, ML' mkt REASON s

None during this reporting pe riod.

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MONTHLY TOTAL 0

DOCKET NC 50-280 UNIT SURRY I DATE 11-1~81 COMPLETED BY SUE D. DUNN AVERAGE DAILY UNIT PWER GVEL MONTH: OCTOBER 81 AVERAGE DAILY PWER MVEL AVERAGE DAILY PWER LEVEL DAY (W E-NET)

DAY (WE-NET) 1 0.0 17 736.5 2

0.0 18 736.8 3

0.0 19 734.4 4

0.0 20 735.0 5

0.0 21 734.0 6

142.9 22 733.4 7

647.1 23 735.0 8

734.8 24 735.1 9

735.0 25 764.3 10 736.3 26 732.0 11 734.9 27 729.0 12 735.4 28 728.6 13 7 37.0 29 727.5 14 735.3 30 731.9 15 697.6 31 732.0 16 738.1 D4ILY UNIT PWER LEVEL FORM INSTRUCTIONS ON THIS FORY, LIST THE AVERAGE DAILY UNIT PWER LEVEL 1N WE-NET FOR EACH DAY IN THE REPORTING N0la"IH. THESS FIGURES VILL BE USED TO PLOT A GRAPH FOR EACH REPORT-ING NONTH. NOTE THAT BY USING MAXIMUM DEPENDABLE CAPACITY FOR THE NST ELECTRICAL RATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAILY AVERAGE P W ER EXCEEDS THE 100 */s LINE (OR THE RESTRICTED PWER LEVEL LINE). IN SUCH CASES, THE AVERAGE DAILY. UNIT PWER OUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANOMALY.

DOCKET NO 50-281 UNIT SURRY II DATE 11-1-81 COMPLETED BY SUE D. DUNN AVERAGE DAIM UNIT PW ER LEVEL MONTH: OCTOBER 81 AVERAGE DAIU PWER LEVEL AVERAGE DAIU PWER LEVEL DAY (WE-NET)

DAY (WE-NET) 1 738.5 17 744.6 2

738.8 19 749.4 3

742.5 19 748.5 4

744.4 20 746.8 5

741.6 21 748.3 6

740.9 22 749.5 7

738.9 23 748.3 8

742.9 24 747.9 9

743.4 25 778.2 10 729.7 26 742.6 11 540.3 27 742.6 12 583.9 28 743.2 13 740.9 29 745.9 14 739.8 30 745.8 15 741.7 31 744.7 16 746.8 DAIU UNIT PWER LEVEL FORM INSTRUCTIONS ON THIS F015, LIST THE AVERAGE DAIU UNIT PWER LEVEL IN WE-NET FOR EACH DAY IN THE REPORTING MONTH. THESE FIGURES UICL BE USED TO PLOT A GRAPH FOR LACH REPORT-ING NONTH. NOTE THAT BY USING MAXINUM DEPENDABLE CAPACITY FOR THE NET EL&.TRICAL RATING OF THE UNIT, THERE MAY BE OCCASIONS WHEN THE DAIU AVERAGE PWER EXCEEDS THE 100 */= LINE (OR THE RESTRICTED PWER LEVEL UNE). I?/ SUCH CASES, THE AVERAGE DAIU UNIT PW ER CUTPUT SHEET SHOULD BE FOOTNOTED TO EXPLAIN THE APPARENT ANCMALY.

SUMMARY

OF OPERATING EXPELJENCE OCTOB ER, 1981 Listed below in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents.

UNIT I October 1,_

- This reporting period begina with the unit at cold shutdown for repair of auxiliary feedwater system leaks.

October 4

- Left cold shutdown condition (>200 F) at 1905.

October _5,

- Left 350 F/450 PSIG at 0955. Reached hot shutdown condition (547 F) at 1912.

October 6,

- The reactor was critical at 0028. The generator was synchro-nized to the line at 0308. At 0333 a reactor trip occurred due to a high level in "A" Steam Generator. The high level was a result of control system problem with the "A" main feed regulating valve. The control system problem with the "A" MF regulating valve was repairsd'and the valve tested at 0610. The reactor was critical at 1035 and the generator was synchronized to the line at 1243. The rate of power increase was reduced to 3% per hour at 1400 with the unit at 30%.

October 7

- The unit reached 100% cower at 1200.

October 15.

- When closing the #3 Governor Valve for the main turbine for repair of the LVDT Core Rod for the position indication the valve closed immediately and the #4 Governor Valve did not open as designed. This caused a loss of approximately 200MWe.

The LVDT Core Rod was replaced for #3 Governor Valve and the valve was re-opened at 0135. A power increase was commenced at 3% per hour and the unit reached 100% power at 1100.

October 31

- This reporting period ends with the unit at 100% power.

~

UNIT II October 1,

- This reporting period begins with the unit at 100% power.

October 10,

- Commenced decreasing power to 80% to remove "4B" feedwater heater from service for repairs. Stopped power decrease to 80% at 2225.

October 11, At 1835 turbine power dropped from 655 HNe to 278 MWe when #1 Governor Valve went closed. Conditions were stabilized with the unit at 49% power and a power increase began at 1930. At 1958 #1 Governor Valve was found to be swinging. At 2003 all governor valves were swinging and turbine power was fluctuating from 580MWe to 245 MWe.

Ran valve position limiter back to close

  1. 1 Governor Valve. Stabilized power at 51%, 350 MWe in turbine manual. At 2050 electro-hydraulic control

SUMMARY

OF OPERATING EXPERIENCE (COh7INUED)

UNIT II fluid to #1 Governor Valve was isolated and instrument techt. 'cians were called in to find and correct problem with EHC System. At 2307 instrument technicians reported problem was three broken wires on #1 Governor Valve.

The wires were replaced and valve position indication for #1 Governor Valve verified correct at 2345.

Opened #1 Governor Valve at 0005 and #3 Governor Valve October 12 closed back to compensate. At 0027 commenced raising power to 80% at 150 MWe per hour. Stopped power increase at 80% power, 615 MWe at 0219. Commenced a power increase at 2121 after returing "4B" feedwater heater to service. The unit reached 100% power at 2307.

October 30,

- Commenced V0PEX Emergency Plan Drill at 1044. Secured from V0PEX drill for the day at 1730.

October 31, V0PEX Drill recommenced at 0500. V0FEX Drill terminated at 1525. This reporting period ends with the unit at 100% power.

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AMENDMENTS TO FACILITY LICENSE OR TECHNICAL SPECIFICATIONS OCTOBER, 1981 None during this reporting period, t

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FACILITY CHANGES REQUIRING NRC APPROVAL OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL OCTOBER, 1981 D/C 80 Modification of Masonary Walls Unit The following portions of this design change were implemented 1&2 in response to IE Bulletin 80-11.

D/C 80-86A Modification of Masonary Walls AB-45-10-6 and AB-45-10-9.

D/C 80-86B Modification of Masonary Wall SB-27-0-10.

D/C 80-86C Modification of Masonary Wall AB 6-1.

D/C 80-86E Modification of Masonary Walls AB-27-6-33 and AB-27-6-34.

D/C 80-86G Modification of Masonary Wall AB-27-6-32.

D/C 80-861 Modification of Masonary Walls 1S-21-2-1 and 1S-21-2-2.

D/C 80-86J Modification of Masonary Wall AB 6-35.

D/C'80-86K Modification of Masonary Walls AB-15-0-1 and AB-15-0-4.

D/C 80-86L Modification of Masonary Walls SB-9-6-1, 2, 3, 14, 15, 16, and 17.

D/C 80-86M Modification of Masonary Walls SB-9-6-6 and SB-9-6-8.

D/C 80-86N Modification of Masonary Walls SB 6-11, 12 and AB-27-6-8.

D/C 80-86P Modification of Masonary, Wall SB-27-0-3.

D/C 80-86Q Modification of Masonary Walls SB-27-0-8 and AB-45-10-21.

D/C 80-86R Modification of Masonary Wall AB-27-6-7.

D/C 80-86S Modification of Masonary Walls AB-27-6-19 and AB-27-6-20.

Summary of Safety Analysit The completed modifications will have no effect on the operation j

of safety related equipment.

D/C 81 Addition of Isolation Valve to Aire Start System Unit This design change added a 1 1/2 in. isolation valve to each of 1&2 the air compressors of the air start system for the emergency diesels. The isolation valves in each of the compressor discharge lines are downstream of the check valves. This will allow work on the check valves without removing s.'y of the air supply from service.

FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL OCTOBER. 1981 D/C 81 Summary of Safety Analysis Unit This modification installed the isolation valves in close 1&2 proximity of a support, thereforc, negating any increased seismic loading of the pipe. As a result of this design change, there is no effect on the operation of any safety related equipment.

D/C 81 Reserve Station Service Load Shed Scheme Unit This design change installed a load shedding scheme to reduce 1&2 the margin of overload on the RSS system in the event of simultaneous loading of both units on the RSS system. The automatic scheme includes manual override. This design change is an interim change pending resolution of a permanent solution to present NRC GDC17 guidelines.

Summary of. Safety Analysis This modification improves the voltage available from the offsite power source under certain postulated conditions.

There are no changes to system design or operation for any safety or non-safety equipment.

TESTS AND EXPERIMENTS REQUIRING NRC APPROVAL OCTOBER. 1981 NONE DURING THIS REPORTING PERIOD.

TEST AND EXPERIMENTS THAT DID NOT REQUIRE NRC APPROVAL OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

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  • INDICATES CDRRECTICN FACILITY CHANGES '11RT DID NOT REQUIRE NIC APPPOVAL September, 1981 (continued)

D/C 79-41 New Fuel Elevator Modification 1

This dasign change installed a key lock switch on the up button for the new fuel elevator to prevent raising the elevator without the key which is under the control of tle Shift Supervisor.

SLPNARY & SAErrl ANALYSIS

' itis modification provides an increased margin of safety during fuel handling opemticns.

D/C 79-69 Aux,11ary Shutdown Panel / Main Control Board Isolation Itdification 1

This design change provides emplete electrical isolation between circuits in the Main Control Board and the Auxiliary Shutdown Panel as required by the NBC issued, Fire Protection Safety Evaluaticn Report, dated Swu=Ler 19, 1979.

SIMRRY OF SAFETY ANALYSIS This nodificaticn does not create a safety problem, since e

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. this upgrades safety related circuits naMM for safe shutdown.

This mnaification does'not degrade the functierung of cny other-safety related systems.

This design change provided a methcd for replacing teflon Insert check valve bearings with stainless steel bearings.

The teflonbearingswere not qualified for the estimated total integrated radiation dose due to the valve locations. The overexposure of these valve bearings could have resulted in failure of the valve to operate properly.

SIMRRY OF SAFETY ANALYSIS The Service Water System and Cmponent Cooling Water System capability and operation raadiness is not affected. There are no safety implications created by this design change. This modification increases the reliability of the check valve to operate after an accident.

D/C 80-55 Replace Mechanical Seal-Charcinc Pump Cooling Water Pump 1&2 This design change replaced the mechanical seals on the Charging Pump Cooling Water Pumps secondary seals. The teflon

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secondary seals were not qualified to the 40 year normal plus post-accident integrated radiation doses. The replacement x

material (ethylene propylene rubber) meets or exceeds the environmental requirements for the original teflon seals.

OTHER CHANGES, TESTS AND EXPERIMENTS OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

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. og g rg t*p'j SURRY TO'.EA STATID_N CHDfISTRY REPORT OCTOBER,,, 19 81 T. S. 6. 6. 3. d 4

PRIMARY COOLANT UNIT NO. 1 (D)

UNIT NO.

2 (C)

ANALYSIS

)

MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMLil AVERAGE

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Gross Radioact., UCi/ml 2.33 9.44 1.05' 2.80 ~1 1.201 2.06-1

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Suspended Solids, ppm o.1 0.1 0.1 0.1 o.1 0.1

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~1 Gross Tritium, UCi/ml 2.16 6.96~

1. 4'3 1.18 1.04 1.10 Iodine-131, UCi/ml 2.63( )~1

-2 1.43-1 9.59 2.72-3 4,49-3

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3.60 (E)

I-131/I-133

,7479

.2069

.4505 2.0200

.B416 1.4369 (A)

Hydrogen, cc/kg 46.6 4,9 27.7 57.0 32.4 45.4 Lithium, ppm 1.67

' o,47 -

1.22

.96

.34

.64 Beron-10, ppm +

389.84 162.68 183.84 28.03 7.64 15.67 Oxygen-16, ppm 4.40 (0)

.000 l'.67

.000

.000

.000 Chloride, ppm

<.05

<.05

<.05

<.05

<.05

<.05 pH 0 25*C 7.76 5.50 6.48 7.86 5.95 7.38

+ Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL RELEASES, PCCNDS (F)

T. S. 4.13. A. 6.

Thosphate Boron 504 Sulfate Chromate

.10 Chlorine 5'):.' NaOH Es= arks: (A) Reflects Unit #1 startup 10-6-81 (B) High values due to suspected fuel failures (C) Unitrarpdownto5]% power 10-10-81.orfeedwaterheaterrepairs.

(D) Unit start-up 10-6 Unit runback from 100% to 71% power.

(E) High values due,t o. suspected pin-hole leaks in fuel.

(F) These levels of chemicals should represent no major adverse environmental impact.

(G) Unit at cold Shutdown.

DESCRIPTION OF ALL INSTANCES WHERE THERMAL DISCliARGE LIMITS WERE EXCEEDED OCTOBER. 1981 Due to the impairment of the circulating water system on the following days, the thermal discharge limits were exceeded as noted.

October 7, 1981 Exceeded 15.0 Exceeded 15.0,F AT across station

  • October 8,1981 F AT across station
  • October 9, 1981 Exceeded 15.0 F AT across station October 10, 1981 Exceeded 15.0 F AT across station
  • October 11, 1981 Exceeded 15.0 F AT across station
  • October 12, 1981 Exceeded 15.0,F AT across station
  • October 13, 1981 Exceeded 15.0 F AT across station October 14, 1981 Exceeded 15.0 F AT across station October 15, 1981 Exceeded 15.0 F AT across station
  • October 16, 1981 Exceeded 15.0 F AT across station
  • October 17, 1981 Exceeded 15 0 F AT across station
  • October 18, 1981 Exceeded 15.0 F AT across station October 19, 1981 Exceeded 15.0 F AT across station October 20, 1981 Exceeded 15.0 F AT across station October 21, 1981 Exceeded 15.0 F AT across station 0ctob er. 24,,1981 -

Exceeded 15.0 F AT across station

  • October 25, 1981 Exceeded 17.5 F AT across station October. 2 6 ~,.19 81.,

Exceeded 15.0 F AT across station

  • c October 27, 1981 Exceeded 17.5 F AT across station
  • October, 28. 1981.

Exceeded 15.0 F AT across station October 29,.1981.

Exceeded 15.0 F AT across station October-31,;1981.

Exceeded 15.0 F AT across station

  • Indicates dates where station AT was 15.0 F or less across station for sometime during the day.

l The AT excursions were allowable under Technical Specification 4.14.B.2.

There were no reported instances of adverse environmental impact.

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. a FUEL IwfutInc 1

OCTOBER, 1981 i

4-

. Sixty-eight (68) new fuel assemblies and Sixty (60) new BPRA's i.

were received this month for Unit 2 Cycle 6 refueling.

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-19,

FUEL HANDLING' OCTOBER, 1981 i

DATE NO. OF

' ANSI NO.

NEW OR SPENT FUEL SH3EEWX/ RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICIDiENT SHIPPING CASK ACTIVITY LEVE i

09-30-81 8

LM09PF/3.6

<2.5 HR/hr.

LM05Y6/3.6

<2.5 MR/hr.

i LM05XW/3.6

<2.5 MR/hr.

LM05YN/3.6

<2.5 MR/hr.

I i

LM05XL/3.6

<2.5 MR/hr.

LM05XP/3.6

<2.'5 HR/hr.

i LM05YL/3.6

<2.5 MR/hr.

l LM05YS/3.6

<2.5 MR/hr.

i 10-08-81 12 LM05YM/3.6

<2.5 MR/hr.

LM05YT/3.6

<2.5 MR/hr.

LM05YE/3.6 2.5 MR/hr.

i LM09PD/3.6

<2.5 MR/hr.

LM05Y9/3.6

<2.5 MR/hr.

LM05YU/3.6

<2.5 MR/hr.

l LM05X5/3.6

<2.5 MR/hr.

i LM05YS/3.6

<2.5 MR/hr.

LM05YD/3.6

<2.5 MR/hr.

l LM05YR/3.6

<2.5 MR/hr.

l LM09PB/3.6

<2.5 MR/hr.

LM05XM/3.6

<2.5 MR/hr.

i l

L

' FUEL HANDLING OCTOBER. 1981 DATE NO. OF ANSI NO.

NEW OR SPENT FUEL MFf9M@/ RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASK ACTIVITY LEVE:

10-15-81 12 LM05XY/3.6

<2.5 MR/1.r.

LM05Y0/3. 6

<2.5 MR/hr.

LM05X2 /3. 6

<2.5 MR/hr.

'LM05Y3/3.6

<2.5 MR/hr.

LM09PG/3.6

<2.5 MR/hr.

LM05YB/3.6

<2.5 MR/hr.

LMOSX4/3.6

<2.5 MR/hr.

LM09PE/3.6

<2.5 MR/hr.

LM05YA/3.6

<2.5 MR/hr.

N LM05XA/3.6

<2.5 MR/hr.

LM05XF/3.6

<2.5 MR/hr.

LM05XH/3.6

<2.5 MR/hr.

10-22-81 12 LM05YG/3. 6

< 2.5 MR/hr.

IM05XX/3.6

<2.5 MR/hr.

l LM05JX/3.6

<2.5 MR/hr.

LM05XE/3.6

<2.5 MR/hr.

LM05XB/3.6

<2.5 MR/hr.

LM05XU/3.6

<2.5 MR/hr.

<2.5 MR/hr.

LM05YH/3. 6 LM05XQ/3.6

<2.5 MR/hr.

LM05YK/3.6

<2.5 MR/hr.

LM05XD/3.6

<2.5 MR/hr.

LM05XV/3.6

<2.5 MR/hr.

LM05Y7/3.6

<2.5 MR/hr.

=

-21.

FUEL HANDLINO' OCTOBER. 1981 1

i DATE NO. OF ANSI NO.

NEW OR SPEhi FUEL SH2PPED/ RECEIVED ASSEMBLIES PER SHIPMENT INITIAL ENRICHMENT SHIPPING CASE ACTIVITY LEVE 10-28-81 12 LM09PC/3.6

<2.5 MR/hr.

LMOSX3/3.6

<2.'5 MR/hr.

t LM05YF/3. 6.-

<2.5 MR/hr.

LM05Y2/3.6"

<2.5 MR/hr.

LM05XG/3.6

<2'5 MR/hr.

l LM05XT/3. 6

<2.5 MR/hr.

LM057N/3. 6

<2.5 MR/hr.

4 LM05YJ/3.6

<2.'5 MR/hr.

' M05YP/ 3. 6

<2.5 MR/hr.

LM05YQ/3.6

<2.5 MR/hr.

LM05X7/3.6

<2.5 MR/hr.

i LM05YC/3.6

<2.5 MR'/hr.

l i

10-30-81 12 LM09P9/3.6

<2.5 MR/hr.

j LM05XK/3.6

<2.5 MR/hr.

LM09PH/3.6

<2.5-MR/hr.

LM05Y4/3.6

<2.5 MR/hr.

LM05X9/3.6

<2.5 MR/hr.

LM05XR/3.6

<2.5 MR/hr.

LM05XB/3.6

<2.5 MR/hr.

LM09PA/3.6

<2.5 MR/hr.

LM05X6/3.6

<2.5 MR/hr.

LM05XC/3.6

<2.5 MR/hr.

LM05Yl/3,6

<2.5 MR/hr.

LM05YS/3.6

<2.5 MR/hr.

PROCEDURE REVISIONS THAT CHANGED THE OPERATING MODE DESCRIBED IN THE FSAR OCTOBER. 1981 L

None during this reporting period.

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i DESCRIPTION OF PERIODIC TESTS WHICH WERE NOT COMPLETED WITHIN THE TIME LIMITS SPECIFIED IN TECici1 CAL SPECIFICATIONS 1

OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

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INSERVICE INSPECTION OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

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g 1 REPORTABLE OCCURRENCES PERTAINING TO A!:Y OUTAGE OR POWER REDUCTIONS OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

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Maintenance of Safety Related Systems During-Outage or Reduced Power Periods i

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%.1 TOTin!NT4 13/01/31 99 PtRTS R9-r-19 CRFCK NFCTI SEATS CM l'IPT'S SMAll Colip ACKSSERLK AT THIS TIME 1

1010919'G 10/01141 nw

'K7V NOV-lW-15tE VRlVE !!AS ROTW RONNFT LEAM RErlACED CASKET 1

109300110

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10/01/31 C's V41VR 1-Cit-11 1 VAlVM STE1r WESSEMC Kl'WFWD BCHNTT ASST 1

10n3011%1 100 10/01/nt CS V0V

  1. 9V-1018 VALVE LEATS VAST SEAT CrtMED AMO CilFCKFD VATVT INTVRMAl.9 1

1090r1011 110 10/03/at &

FitV IMO F1-SV-100A Tl w INDICATOR LEAKS EXCESS LFVFLTD FlW IMfflCATOR 1

109301G00 s1 10/03/81 SJ VAlVR t-M -1G1 11RARIK TO CTClK VAlVK

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10/0%/81 CS rtoT 1-CS-r-1A INNOAhn IEC!! SEAL IIAWS REPLACED WlCM SEAL 1

1010nor,1%

%e 10/0%/81 CS rimer 1-CS-r-tA Mf.Cil SFALS 110Til LEAKlWC REPAlR MCC!! SF4L 1

  • 110031330 11 10/0%/nt St V11VR t-SE-1's t flNPOLT AMit RF.1t0VK nonNET CrTNTI TREM REASSEwrlE 1

11003tnR9 25' 10/0%f81 CS TIR41' 1-CS-r-1M C0tirlR lilMr 70 SMTOR ROLTED CorfrllMC 1

1100%1115 1

t 11/01/at M rirIRC l'VS-18-13G~'~ FIBER CLASS IINE EFAt!WC'

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RFrlACFD KT)R1V ~ '

~1' 109151059 193 10/01/48 N

lt/*T 1-N-r-tC KIT'ACK RTTACEFD 1

110051%05 JE to/01/81 SJ ETRM' t-SV-r-10M RFI'ACK ADDED Pact!WC 1

110051%0th 31 ppp. TOTAL

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i Maintenance of Safety Related Systems Dur g J

Outage or Reduced Power Periods UNIT #2 Mechanical Maintenance.

MAINTENANCE OF SAFETY RELATED SYSTEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT #2 MECHANICAL MAINTENANCE OCTOBER, 1981 i

NONE DURING THIS REPORTING PERIOD.

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    • R T47T!'/NT4 l.. t 19/01/81 KC VAfVE MCV-155GA VI.T
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1091919nn 95 10/01/01 14 at0V POV-IV-15 t r MOV iMPECATE Cl0GFn (DCAT.E.Y

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11n011150 s

10/M int Cs Pt9tt' MTR t-CS-l'-1 A CMECK M TOR MNilYE

  • MECCER MTOM 7t10W Ntt' GEADE 1 1100%l011 1

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MAINTENANCE OF SAF2TY RELATEi' f.YSIEMS DURING OUTAGE OR REDUCED POWER PERIODS UNIT #2 ELECTRICAL MAINTENANCE 4

OCTOBER, 1981 i

NONE DURING THIS REPORTING PERIOD, f

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- MAINTENANCE OF SAFETY RELATED SYSTEMS DURING O'JTAGE OR REDUCED POWER PERIODS UNIT #2 INSTRUMENT MAINTENANCE OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

  • HEALTH PHYSICS 4

OCTOBER, 1981-There was no single. release of radioactivity or radiation exposure specfically associated with an outage that accounted for more than 10% of 'the allowable annual. values in 10CFR20.

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PROCEDURE DEVIATIONS REVIEi7ED BY STATION NUCLEAR SAFETY AND OPERATING CO?D11TTEE AFTER TUE LIMITS SPECIFID IU YECENICAL SPECIFICATIONS OCTOBER, 1981 NONE DURING THIS REPORTING PERIOD.

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