ML20041G172

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Monthly Operating Repts for Dec 1981
ML20041G172
Person / Time
Site: Surry  Dominion icon.png
Issue date: 01/14/1982
From: Saunders B
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20041G169 List:
References
NUDOCS 8203190353
Download: ML20041G172 (59)
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{{#Wiki_filter:* ',.A e VIRGINIA EI.ECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 81-12 DECEMBER, 1981 APPROVED BY: //c !ITATION MANAGER e O 8203190353 820114 PDR ADOCK 05000280 R PDR

i ,', e Section g_ Operating Data Report - Unit il I Operating Data Report - Unit #2 2 Unit Shutdowns and Power Reductions - Unit #1 3 Unit Shutdowns and Power Reductions - Unit #2 0 ~ Load Reductions Due to Environmental Restrictions - Unit #1 5 Load Reductions Due to Environmental Restrictions - Unit 42 6 Average Daily Unit Power Level - Unit il 7 Average Daily Unit Power Level - Unit #2 8 Summary of Operating Experience 9 Amendments to Facility License or Technical Specifications 12 Facility Changes Requiring NRC Approval 13 Facility Changes That Did Not Require NRC Approval 13 Tests and Experiments Requiring NRC Approval 23 Tests and Experiments That Did Not Require NRC Approval 23 Other Changes, Tests and Experiments 24 Chemistry Report 25 Description of All Instances Where Thermal Discharge Limits Were Exceeded 26 Fuel Handling 27 1 Procedure Revisions That Changed the Operating Mode Described in l the FSAR 28 Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 29 Inservice Inspection 30 Reportable Occurrences Pertaining to Any Outage or Power Reductions 32 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit il - Mechanical Mahtenance 33 Maintenance of Safety Related Systems During Octage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 35 l l

-11 s Sectiou g Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintanance 39 Maintenance of Safety Related. Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 01 Maintenance of Safsty Related Systems During Outage or Reduced Power Periods - Unit i1 - Instrument Maintenance 40 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance 46 Health Physics Sussnary 48 Procedure Deviations reviewed by Station Nuclear Safsty and Operating Committee after Time Limits Specified in T. S. 49 e

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CPERATING DATA REPORT 2,- CC:rr:ct d C;py i for November Report DOCKET,NO. 50-281 p DATE 17 DEC 81 COTPE.ETED By Vivian H. Jones EElEPN0//E 804-357-3194 /, / .fPERATIhGSTATUa N

1. UNIT HAVE SURRY UTlIT 2
2. REPORTIt.G PERIOD 11018: TO 113081
3. LICE 2aED THElif.fAL POWER (.WT) 2441 l

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4. ?;AMEPLA2E RATING (GR0da WE) 847.S lNOTEa l

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5. PEaIGil ELiCIRICAL RATING (NET WE) 788
6. NAXTHUM DEPENDABLE CAPACITI (CR0aa WE) 811
7. VAXI40V DEPENDABLE CAPACITY (NET WE) 77S
9. IF CriaNGEd CCCUR IN CAPACITY RATINGa N/A (ITE4a 3 THROUGH 7) SI?lCE LAa7 REPORT. GIVE REASONd
3. PMER LEVEL TO WHICH REOTRICTED IF AVY N/A (t.s?14'E)
10. R2A3003 FOR REaTRICTIOlla. IF Ah7 N/A TRIa M0!!TH YR-TO-DATE CUNULATIVE
11. EDURJ Ih REPORTING PERIOD 720.0 8016.0 75264.0
12. NUVBER OF HOURa REACTOR WAS CRITICAL 144.4 7009.2 44793.2
13. REACTOR REaERVE 39UTDOVN HOUEd 0.0 0.0 0.0 tu. HOURa GENERATOR ON-LIllE 144.4 6968.8 44105.4

'7,IT REdiRVE SHUTDOVN HOURa 0.0 0.0 0.0 1E

15. Gnosa THEWAL S//ERGY GENERATED (WH) 347730.0 16837196.9 103291857.4-
11. Gh033 ELECTRICAL E!!ERGY GE4ERATED (.WH) 112325.0 5436745.0 33675739.0
18. NET ELECTRICAL EllERGY GENERATED (.WH) 106122.0 5149007.0 31927495.0
19. UliIT aEhVICE FACTOR 20.1 e/o 86.9 e/o S8.6 ele
20. UNIT AVAILABILIH FACICR 20.1 e/o 86.9 */*

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21. Uh1T CAPACITY FACTOR (UaING '.'PC NET) 19.0 e/o 82.9 e/o 54.7 */*
22. UliIT CAPACIH FACTOR (UaI.7G DER NET) 18.7 */o 81.5 ele 53.8 ele
23. UtIT FORCED CUTAGE RATE 0.0 0.0 0.0 l 24 aliUTDW.'.3.:iC4EDULED OVER llTXT 6 MONTna REFUELING 06 42 DAYa (2YPE.DATE. AllD DURATION OF EAC11)
25. IV 071UT DO!N AT END OF REPORT PERIOD.

EcTI4nTE DATE OF STARTUP l 26. UNITJ I.'i ZEa7 OTATUa FORECAST ACHIEVED (PRIOR TO CO.vMERCIAL OPERATION) I!!ITIAL CRITICALITY INITIAL ELEC.TRICIH C0YMERCIAL OPERATION

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l. 0'!?LETED BY Vivian H. Jones TELE
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1. L7,:T oli? E SUri3Y l. WIT 2
2. l'i?:o.C':;.'G PElll2D 120181 TO 123181

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5. DFS:GU ELEC"R: CAL EAT:CG (!!ET WE) 788
5..t'AX::'t!'.' OEFinDAhLE CAPA::TY (GROSS WE) 811
7. *.*AX:.*ll*>* C??i'1DABLE CAPAC:TY (7ET WE) 775
3. II C7Ai'GES GCCU:t ::: CAFAC:TY RAT:NGS

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13. 1:EASO:lt F]n RESTi::CT:2IIS, :F A:1Y RfA TH:S NO?lTH Yis-TO-DATE CU.vulAT:7E
11. VOURS ::. REPORT:i/C PFN:0C 7s s.0 8760.0 75008.0 ee
12. !;U'? bed GF NOU!ES EEA:7JE n/AS CE:T: CAL 67.5 7076.7 44860.7 13.1:2 ATTJi EESEliVE Si!UTDeWl.' HOURS 0.0 0.0 0.0 1 s*. EC'JRS UEEEEATOE C'I-LI?!E 6.3 6975.1 44111.7
15. Ut:7 tiFSEEVE SllUTD0n7 I!JURS 0.0 0.0 0.0
15. CEOSS T.5ET<AL E;.E.7 Y GE.??EATED (.~.;E) 5428.0 168s2624.9 10329728S.4 e
17. Cl.]SS ELE:7t:: CAL El/EEGY GEYERATED ('.~'Y) 1440.0 Sa381RS.0 33677179.0 e
13. ?;ET ='LFC:h' CAL EGERGY GElEEb7ED O*JH) 1220.0 5150227.0 31923715.0 0.3 ele 79.6 ele 53.0 ele 13.17:t Si'hV:CE FA:: d
20. U:.:T AVA L15:L:TY FACT 2R 0.8 ele 79.6 ele 58.0 ele
21. N;:7 CAPAT:TY FA:TOL (US::iG '@T ?!E2) 0.2 eie 75.9 ele 54.2 ele
22. C'.:: CA! AT:TY FACTOR 'US:.?G DER liET) 0.2 ele 7s.6 ole 53.3 ele e
23. U:,:T l'e'in:ED QUTAGE.? ATE 0.0 1.0 eje 20.9 eje 2s. E'!UT W?.S SC?EliULEl; OVEit DEXT C TO::T'!S ST?: llc '.'A:!lT. 07-C 2 t 2 YDE.(*lTE, A'! liUCATIC:l OF ' AC4) 10 DAYS E

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d 4 50-280 l UNIT SilU1 DOWNS AND POWER REDUC 110NS DOCKET NO. UNirNAME _ Surry One g 1 2-31-81 DATE COMPLETED gy Vivian Jones REPORT MONTil DECEMBER. 1981 1ELEPilONE (804) 357-3184 ext. 477 4 "y Licensee Eg k )sxEf !E 3 Cause & Corrective tb. Daic i ii ; 2 Event g'ir '8 Action to [E E 3gc Report a mO u Prevent Recurrence F-o u c5 81-23 12-01-81 F 260.0 A 3 Continuation of shutdown which began 11-29-81 for "A" RCP motor repairs. Motor was replaced prior to startup. s 81-24 12-16-81 F 19.8 G 3 Reactor tripped while attempting to change "A" SS transformer taps under load. "A" SS transformer was electrically disconnected and unit will operate with power supplied by "A" RSS transformer. Personnel have been instructed concerning transformer tap configuration and procedure for changing item. i 1 2 3 4 F: Forced Reasmi: Method: Exhibit G. Instructions S: Stheduled A-Equipment Failure (Explain) l-Manuel for Preparatism of Data B Maintenance or Test 2 Manual Screm. Entry Sheets for 1.icensee C Refueling 3-Autornatic Scram. Event Report tLER) File INURI.G-D-Regulatory Restriction 4 Other (Explain) 0I,61) E-Operator Training & License Examination F Administrative 5 G Operalismal Etrur (Explain) Exhibit I. Same Source 19/77) Il-Other (E xplain) i

e 50-281 UNIT SIIUTDOWNS AND POWER REDUCTION 3 DOCKET NO. ' NIT NAME Surry Two ~ DATE 12-31-81 REPORT MONT1g DECEMBER, 1981 COMPLETED BY Vivian Jones TELEPilONE (804) 357-3184 ext. 477 "E c re 3 us : 5 EX Lkensee 5% k% Cause & Corrective Ee E 7 No. Date { ii ? 4 2s5 Event uy 'g 'Acthm to dE E j ig g

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@G u p,,,,,, g,y,,,,,,, 6 i 1 81-17 12-01-81 S 737.7 C 3 continuation of refueling shutdown which commenced November 7, 1981. x-i t 2 3 4 F: Forced Reasim: Method: Exhibit G. Instenctions S: Scheduled A Equipment Failure (Explain) 1-Manual for Picparation of Data B-Maintenance of Test 2 Manual Scram. Entry Sheets fo IAensee C Refueling 3 Automatic Scram. Event ReposI(LER) File INtIREG-D-Regulatory Restiletion 4-Other (Explain) 0161) E-Operator Training & IJceng Examinatiu.t i F Administrative 5 G-Operational Error (Esplein) Eshibit I-Same Source l's/77) Il Other IExplain) J l i

w k 5 LOAD REDUCTIONS DUE TO ENV _ UNIT NO 1 DAR TIE _ HOURS _ LOAD. MW REDUCTIONS. M NONE DURING THIS REPORTIN t t e HONTHLY TOTAL 3 m

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a 8 UG~EET NO 50-281 U:i:7 SUFRY :: DAT? 1-1-R2 C0'.'PLETE,7 EY VLvtan H. Jones AVERAGE DA:LY U?;:T PXFr7 LD'EL \\ 21tTF: DECE6:BER 31 AVERAGE Da:LY iWEn LEVEL AVERAGE DA:LY POWER LD'EL CAY (WE-NET) DAY (YWE-NET) 1 0.0 17 0.0 2 0.0 18 0.0 3 0.0 19 0.0 0.0 20 0.0 5 0.0 21 0.0 5 0.0 ?? 0.0 7 0.0 23 0.0 3 0.0 24 0.0 9 0.0 25 0.0 10 0.0 26 0.0 11 0.0 27 0.0 12 0.0 28 0.0 .c 13 0.0 29 0.0 14 0.0 30 0.0 15 0.0 31 50.8 16 0.0 LA::.3' UVIT POJER LEVEL 70RV li:STRU:T:OtlA O!! TEIS FOly, L'ST THE AVERAGE DAILY UN:T POVEi? L2'='L lll %'E-!!ET FOR EA:H DAY :n TVE l!EV9RT:liC !.!O!!TH. THESE F:CUEE3 W:LL EE USED TO P10T A GRAPH FOR EACH REPOPT-

57 '.7%:9. l.GTE THAT PY US:':C "D NU" DEFENCAELE CAPA::TY POR T'!? 'IET EL?:TE' CAL h AT:llC 9F 5'NE llii:1, T?ERE DAY FE OCCA3:07:3 L!Eli T?? CAILY AVERAGE PWER EXCEEP3 I?E 100 *ie L:.VE (On THE RESTR:27FC FOVEh LE'!EL LD;E). Z*i SU:H CASES, THE AVETAGE LA:LY U.7:7 FNEE OUTPUT G7EET S!!OULD EE FOOT::0TED T2 EX?LA::! TlE APPAEETI A40 VAL}'.

9

SUMMARY

OF OPERATING EXPERIENCE DECEMBER, 1981 Listed below in chronological sequence by unit is a sammary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents. UNIT ONE December 1, 1981 This reporting period begins with the unit at cold shutdown for repairs to the "A" Reactor Coolant Pump (RCP) Motor. December 9, 1981 Repairs to "A" RCP Motor complete and unit filled and vented at 1952. December 10, 1981 Lef t cold shutdown condition (>200 F) at 1406 and exceeded 350 F/450 psig on primary system (RCS) at 1800. December 11, 1981 Reached hot shutdown conditions (HSD) at 0400. The reactor was critical at 1803 and the generator on the line at 2000. December 12, 1981 Reduced power increase rate to 3% per hour at 0200 with the unit at 44% power. Discovered No. 1 Turbine Governor Valve (#1 GV) closed at 0332. Isolate EHC fluid to #1 GV while investigating problem. Stopped power increase at 70% power at 1200until "B" H.P. heater Drain Pump is returned to service and #1 GV problem is resolved.

  1. 1 GV repaired and reopened at 1719. Started power increase at 3% per hour at 1725. Stopped ramp at 867 at 2257 to investigate suspected tube leak in the "4B" feedwater heater.

December 13, 1981 Isolated 2B, 3B & 4B feedwater heaters at 0117. December 14, 1981 2B, 3B & 4B feedwater heaters returned to service at 0041. Started power increase at 3% per hour at 0100. Reached 100% power at 0655. December 16, 1981 The reactor tripped at 0130. The cause of the trip was an "A" phase differential generator trip signal due to attempting to change the "A" station service transformer taps under load. The reactor was crJ*.ical at 0245. The "A" SS transformer was dise nnected electrically and the generator placed on the line at 2120. Reduced rate of power increase to 37 per hour at 2248 with unit at 39% power. December 17, 1981 The unit reached 100% power at 2040. December 25, 1981 At 2050, the steam driven auxiliary feed pump (1 iW-P-2) started when SOV-MS-102B f ailed to open. The SOV failed to open due to a diaphragm leak on the pneumatic operator. Steam was manually isolated to the AFP at 2125.

10

SUMMARY

OF OPERATING EXPERIENCE DECEMBER, 1981 (continued) UNIT ONE i December 27, 1981 The load on the "A" Reserve Station Service transformer exceeded 2000 aspe at 0647 when the "2A" RCP was started. The load dropped to <2000 amps at 0749 when the "2A" ,RCP was secured. The "2A" RCP was restarted at 1031 and the "A" RSS transformer load exceeded 2000 amps. December 31, 1981-The "A" RSS transformer load decreased to <2000 amps at 1812 when the Unit Two electrical loads were transferred to the ss..acion service transformers. UNIT '1WO December 1, 1981 This reporting period begins with the unit at cold shutdown for refueling. December 4, 1981 The tensioning of the reactor vessel head was completed at 0630. December 15, 1981 Conssenced increasing containment pressure for the " Type A" leakage test. i December 16, 1981 Reached " Type A" test pressure (61 psia) at 1111. December 19, 1981 The " Type A" test was completed at 1134. December 22, 1981 The "C" S/G secondary side hydro was compeleted at i 0211. Stopped "C" RCP and. isolated "C" RCS loop for repairs to the pump seals at 0252. December 24, 1981 Repairs compelete and "C" RCP started at 1708. December 26, 1981 RCS temperature exceeded CSD condition (200 F) at 2320. December 27, 1981 RCS temperature and pressure exceeded 350 F/450 psig at 0605. Reached hot shutdown condition at 2125. December 28, 1981 The reactor was critical at 1745 and Low Power Physics Testing commenced at 1755. December 31, 1981 Low Power Physics Testing was compelte at 0136. At 0202, the reactor was shutdown to allow stopping "C" RCP for a balance move. The balance move was completed and "C" RCP started at 1110. The reactor was critical at 1150. At 1411, the instrument air line broke for TV-CC-205B and the valve failed to close causing a loss of component cooling to the "B" RCP. Stopped "B" RCP at 1428. Tripped the reactor at 1455. Started "B" RCP at 1523 after installation

11

SUMMARY

OF OPERATING EXPERIENCE DECEMBER, 1981 ) i (continued) UNIT TWO December 31, 1981 of a temporary air line to TV-CC-205B. The reactor was critical at 1555. The generator was on the line at 1744. Stopped the ramp at 35% power at 1840 to establish secondary chemistry. Chemistry was satisf actory and a power increase at 3% per hour started at 2000. This reporting period ends with the unit at 40% power. O l l l l I

.at 44E Du l"c No OR c r R:gulc emb:r 1981 s De TECHNIC an. 72 c No.d 2 cd n AL 73 to 82 Th to tha Opery Co 3 cha ating Licem is io, o m nge The s hav s r n se am e be THI-2 endm n September e ts in en design ted ns Le areas n e for Sur sso a n Le instr of co ,h um erge ned rpor ar em s Technica a fe dw entatio ate e ny category "heA"requir et c t ater o nf pow utside 5 er ntainsystems,or inadequupply r itens s e co me ts for im n In ad n ate equir. m addi They spe ifi et the inplem n 3.B core tio and eme t plen n of n to to co ling,s, v lv follow :the Oper t e c o accur entatio the a c ll a s r e ately deter i n c (Unit a ing Licequir o tainme tpo n s of tii em pr e ts n ogr n The Te hnic1) "B. Te h s for Unithe Te hni airboms to n ense of a ne Am c rec e dm n c c rn Sp cnic l t I No.l a e iod. shall ent a ca e if 2, l S and 7,e ific tio Spe if oper c 2 a c ic tio r espe tiv lyi

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a re he ns a c t co ns The Te hni r by in ntained e e ity in Am c co co da atedin Appe d rpo e dm c n ca Sp cnic l r et No.l ac shall n a n ix A r S in the lic, as 7,e ificatio nce ope e if c 3 r ic tio with ate the fa iliar her by i a ns.revis d e ns o tained the Te hni e ns c e e n c e cal The lii c n ty in corpor in Appe dix Spe if acco da ated c n r within the lic, as nce A ns.revis d the Te hni e e e The lice c thr cal Spe if m c ica 9

  • D.

Dg 1 c. FACILITY CHANGES THAT DlD NOT REQUIRE NRC APPROVA NOVEMBER, 1981 D/C 80-53 Insert Check Valve Replacement Bearings (C

SUMMARY

OF SAFETY ANALYSIS The Service Water System and Component Coo capability and operation readiness is not are no safety implications created by this modification increases the reliability of operate after an accident. D/C 81-22 Installing Halfunction Alarm On Radiation i This design change provides an audible ala a loss of power to the Radiation Monitorin! annunciator will alert the operator immedid of power to this system.

SUMMARY

OF SAFETY ANALYSIS This modification does not effect the auton the radiation monitor and it will improve 1 of the system. D/C 81-39 Fire Protection For Temporary Clean Change This design change connects the fire protec i sprinklers in the temporary clean change tr adjacent to the auxiliary building.

SUMMARY

OF SAFETY ANALYSIS This modification reduces fire hazards in t change trailer and does not lessen the capa rest of the fire protection system. D/C 81-i8, Unit #1 Auxiliary Feedwater System Cavitati Modification This design change replaced 3" 600 psi care type flanges with 3" 600 psi stainless stes flanges. This design change eliminates a m condition and any thermal expansion problem seating surfaces.

SUMMARY

OF SAFETY ANALYSIS This modification enhances the integrity o9 System and should reduce the occurance of 1 gaskets at the flanges. 9

13 FAC2LITY CHANGES REQUIRING NRC APPROVAL DECEMBER, 1981 NONE DURING THIS REPORTING PERIOD. ~. FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL DECEMBER, 1981 Unit D/C 78-40 RCS RTD Isolation Valve Removal 2 This design change removed four manual isolation valves in each RCS RTD bypass loop. The talves which incorporate an adjustable stem packing have proven to be a source of uncontrolled RCS.'.eakage through the stem packing. The valves were originally installed such that the RTD manifolds could be isolated for maintenance purposes. However, because of the leakage problem associated with the valve, they were more of a maintenance problem than the RTD's. The four valves in each RCS RTD bypass loop were replaced with straight pipe.

SUMMARY

OF SAFETY ANALYSIS The removal of the RTD bypass system insolation valves' reduces the amount of maintenance performed on the RCS. Consequently, the number of personnel exposures j to high radiation is also reduced. This further insures the safe and efficient operation of the unit. D/C 79-69 Auxiliary Shutdown Panel / Main Control Board Isolation 2 This design change provides complete electrical isolation between circuits in the Control Board and the Auxiliary Shutdown Panel as required by the NRC issued, Fire Protection Safety Evaluation Report, dated September 19, 1979. l

SUMMARY

OF SAFETY ANALYSIS l This modification does not create a safety problem, since this upgrades safety related circuits needed for safe shutdown. This modification does not degrade the functioning of any other safety related l systems. 1 1

14 FACILITY CHANGES THAT \\ DID NOT REQUIRE NRC APPROVAL DECEMBER, 1981 (continued) D/C 79-26 Instrument Air Isolation-Main Regulator _ and Bypass Feedwater .U"1.t. This design change provides for 2 main and the bypass feedwater regulatorsegregation of the controllers. If necessary valve would allow for partial sys, tem reindividual isolation repairs are being made to the area covery while

SUMMARY

OF SAFETY ANALYSIS of failure. This modification increases th system by allowing the air controlle versatility of the main or the bypass feedwater regul t ers on required individually rather than h either the a or valves to be of valves inoperable. margin of safety. Therefore, there isaving both sets D/C 79-68 a greater Fire Protection Modification R For Alternative Shutdown Capabilemote Monitoring Panel itv (ASC) This design change provides shutdown 2 an and control devices. control room and auxiliary sables

SUMMARY

OF SAFETY ANALYSIS n panel monitoring ~ i The installation of the remote any safety problems. associated field equipment and matmon D/C 79-76 erials does not create RCP Oil Collection the containment by us'ing aThis design change re 2 otential for fire in reactor coolant pump motors. collection system on the temporarily stores The system collects and of the RCP motor lube any lubricating oil which leaks out oil system. S_U_ MMARY OF SAFETY ANALYSIS RCP motor oil collection system leaks in pressurized linesproof can under oil bearing com ents to contain equipment; therefore, there arenot affect the opera a ety related caused by this modification. no safety problems +"9 Wa* wa=u.4 4D6e ta Nguns asgem entg.gg e-ee p qg>m ee we - r w-

15 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL 4 DECEMBER. 1981 (continued) 1 D/C 80-51 Post-Accident Monitorina and Control Panel This design change provides Post-Accident Monitj Indication and Control in tie control room as re by TMI-2, RREG-0578 and subsequent clarificatio) contained in the NRC letter dated October 30, 1 SU) MARY OF SAFETY ANALYSIS This modification does not affect normal statia operation of any safety related systems. The Technical Specifications and FSAR are not affec' by this design changa. ~ D/C 80-56 Relocate Service Water Radiation Monitors This design change switched the locations of ttb Unit 1 and Unit 2 Recircualtion Spray Cooler so water monitors. This will ensure low-backgroul radiation for the accident unit monitors.

SUMMARY

OF SAFETY ANALYSIS This modification increases the reliability of monitors under accident conditions. The relo gn of the monitors will not affect station operat9 or operation of the Recirculation Spray Cooler service water monitors. D/C 80-58 Replace Charaina Pump Bearina Gaskets This design change replaces the oil paper gas c with a pure-graphite gasket material. The pur: graphite material is being used to fabricate : thrust bearing cover-to-housing and sight flow The pure-gaskets material meets or exceeds the-environmental requirements of the original oil gasket material.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect station ope operation of the charging / safety-injection p will increase the reliability of the safety r pumps under accident conditions. i

16 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL DECEMBER, 1981 ^ (continued) Unit D/C 80-60 Replacement of Post-Accident Sample System Valves 2 This design enange replaced air operated trip valves for the RCS and RHR samples with direct acting solenoid valves. The function of the valves have not changed. An additional direct acting solenoid valve was added to the RHR sample line inside containment and functions as a containment isolation valve.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect normal station operation or the operation of any safety related equipment. Replacement of these containment isolation valves improves the capability of the valves to open after an accident to obtain required samples. D/C 80-65 Post Accident Radiation Waste Connections 1&2 This design change provides flanged connections that would enable the removal o.f radioactive vaste resulting from an accident. An external process system would be designed once an accident occurred. Connections to the Vent and Drain System, Liquid and Gaseous Waste Disposal Systems and the Boron Recovery System would enable the removal of radioactive gases and fluids to external process systems without having to enter high radiation areas.

SUMMARY

OF SAFETY ANALYSIS This modification does not lessen the performance of an orderly reactor shutdown and would be used only during the recovery phase of an accident. The installation of these connections does not affect normal station operation or the operation of any safety related equipment. D/C 80-69 Outside Recirculation Spray Suction Valve Modification 2 This design change removed the teflon sleeves and packing and repalced them with sleeve and packing made of X0M0XF.

SUMMARY

OF SAFETY ANALYSIS This design change introduced no safety problems and significantly decresases the likelihood that the sleeves and packing will fail in a radiation environment. l

. at. NRC THAT e DE M ER 1 ROV CEMB APP s AL 98A AW (ce S nt stem Cavi inu d) e Th N is de ign tatin of s the thr change nturi Ve The v e e tu add the I affe riee inch n Addi SU}M or MFLB cted will AW ed s tio c n S in.avitating v l to the inin is de am ARY ste r e trict es s OF to i SAFETY loops.ain ge ta t ah entu cont e nerato the f c c r r steam g AN e t) pe(r.e.lo m ALYSIS n i w of g. This l mit, lo fed $ e pr the Auo if :st ting op with of md i gre te D/C oc du xil io a e n do r williary Fe d a 8 -8 uxil res 0 es Modif iary fe dw 6 e not ha w dir r flowe to beater Systee e v c ic tio ate a t m mod al The fol n Ma ate. ified tho ge of r to ugh the imple lowing sona ope ops m in rtio Walls r fle t e ted e rat 19 n po c the) ns re D/C spo of 80-8 ns th 6U e to IEis de ign

SUMMARY

D/C Mod s Bulle::in 8 0 if 8 -8 cha ic ta io OF ModAB-27-6-2 6V nge SAFETY if of 0-11. w n ere AN AB-13-0-7ic tio Ma ALY a son D/ The SIS ary Wall n of Ma co C 8 -9 ope 3 atiompleted ary Wall son 0 r n mdo if Div of ic ta io s fety r l er a _Lo, ops sif o ns in e Po ated will er Su equipmhav w Th is de ign e no 1 ent. effe t T s Ca to T nd T cha 3 and Pu c mps u lo on ad ops,nge T the cir n separ Re betwculatio a so n by theny vital tha ate a to c SUMM loops.e s e bu,t with the r Co la n the T 'and ARY o s pow nt OF u use the a lo er SAF s ETY ss up lp ie T of ope the d ato Re r of Co ANALY n s.f le iffe r a to c SIS at c can the 2 This r Co lant re v at s tw ntial e ify n r o modif it o do a totempe atu re ic t def es a c r rl in not to a r atu n ed re co lant in cr in 10 o e te cr a e a as CF e R5.5n "u s the 0 9 nr e iew dsyste v e m rle iab s fety a ilit que -mew w.. stio "y and n ..m. as m 4.s-e< marw=*e, i e \\ = *

  • a a=

l

otRE .s3 THAT NRC ,_D DE fC,__8 _92 CEMB APP 9 ER ROVA 0 1 Bs r (c 981 catin one u d) e Bu Po tio s Unde r / implem sA n r SUM vl o MARY (degr ded) de te, inv l n B ta a and e Pr OF D o of ote tc io SAFETY u derv lving the is de ign n Moe n th ANALY o SIS tage addi s This pr tio cha ote tion c of nge 1. m dif Spe if n o c ic ic a dafin d atio atio system.es s n in luded in 1 e ns on Faddr D/C c esses in th0CFR50 59in l s fety 80-9 a 9 a change Safety An l qu i e tio.s de ign s Co tainm n s, no s to Te h n ne of a ysis Repor ent change the c quickThis de ig Su ct mdo if m co s Pun nt t. ic tio change Re la s itute a n dis harge h dis 4 an no

SUMMARY

c conn c u a ement nrc cce ec pr s, ts fo s ib o OF o ide v s SAF il e r ETY ity for s the a ti tip ing ofele tric l n c ANALY pr p a ope m inte a SIS r This wiring a dmp c pu nan D f_C_81-13 the c. pu 1 or modif e mp and theapa ityt n c ic tio a e ope a ie pu s Mete rta ion will n r mp 4 o r lo ic l o of not data to bThis de ig Mo i s fety r la a alte a r s n e the to in ted stat r ba kup to n e trchange U equipm io

SUMMARY

c n Appe d e t. ope r de ans it pr a n r wer n ix 2 s to thetedovide atio OF m SAF n dir s fo ETY of NUREG r the AN e co 654. r lctly fr ALY nt o m This SIS 0 ete o o roo o mdo if m inm the r logic l capab m in a a ic acc il a r du da tity ofatio orda ad _D/,C,__8 -14has n e C n n do nce 1 s fety r l a es with 1, pr n not evio source e af u ly be LHS s of ated fe t I c m and systemthe en ORS av eteoro rle iab Th Fu ailable. logic l is de ign Casin oper tio n ili LH a a SI s n. ty or data to and no w being uORS cha Re tr ints It nge s that all o ly n sdpump c epla r a ap lp ic b cd which pr deter e e ovide min d a le is TORLONa ing r s integr e trthe teflo s e ated not pr s ope tie. r Thisaints. plugs n rd to be a iatio qu la if s of mat The u n do iedteflo.e ial sd e r new in 2 n m se e ts m te ialthe a theto the Teflo at e r or n c lc lated pu exc a was mp lo u e ds e c tio. total a n l t

O

  • FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL l

DECEMBER. 1981 (continued) Unit D/C 81-14 UlSI and ORS Pump Casing Restraints (continued) 2

SUMMARY

OF SAFETY ANALYSIS This modification will increase the reliability of the safety related pumps during accident conditions. D/C 81-18 Relocation of Undernround Utilities 1&2 This design change relocated existing undergrourd utilities in the area of the new Machine Shop Replacement Facility. This design change also monitored settlement of the Condensate Polishing Building and Distillation Tank caused by the construction of the MSRF.

SUMMARY

OF SAFETY ANALYSIS The relocation of underground utilities does not impose any restrictions or obstruction to station operations and fire protection capabilities to safety related equipment was maintained. D/C 81-19 Machine Shop Replacement Facility 1&2 D/C 81-19A Foundations for Machine Shop Replacement Facility, was implemented. This portion of the design change constructed foundations to support the required building and equipment for the Machine Shop Replacement Facility. Included with the proj ect was the electrical ground system and ground floor slab with embedments.

SUMMARY

OF SAFETY ANALYSIS The addition of the MSRF does not minimize the safety of operating units or effect the operation of safety related' equipment. D/C 81-21 Channe Hydraulic Tubina of Six Inch and Twelve Inch Pathon Snubbers to SS. 2 This design change installed Stainless hydraulic tubing, valves, and reservoirs on 6" and 12" Pathon snubbers in place of existing Carbon Steel tubing to increase corrosion resistance. .. e ,,_,_,,,,_.,,..,,.__,.,.._,_,,.g.,,,,

20 FACILITY CHANCES THAT DID NOT REQUIRE NRC APPROVAL DECEMBER. 1981 (continued)* Unit D/C 81-21 Channe Hydraulic Tubina'of Six Inch and Twelve Inch Pathon Snubbers to SS (continued). 2

SUMMARY

OF SAFETY ANALYSIS This modification provides additional seismic protection for the Reactor Coolant System. It does not affect the station operations or the operation of safety related equipment. D/C 81-54 Relocation of Steam Generator W Flow Indicators 2 This design change removed the horizontal orientation of the Steam Generator Feedwater Flow Indicators and replaced them in a vertical orientation. The change provides consistency throughout the Steam Generator Section on the vertical board in the control room.

SUMMARY

OF SAFETY ANALYSIS This modification provides the operator with a consistent Steam Generator Indicator Section and does not affect the operation of any safety related equipment.- D/C 81-58 Prevention of Tripping Transfer Breaker 15F1 1 This design change added a B.E. SAM timer in the trip circuit of transfer breaker 15F1 to pievent loss of power on Transfer Bus F for an undervoltage condition on Emergency Bus lH and Emergency Bus 2J.

SUMMARY

OF SAFETY ANALYSIS This modification does not affect the operation of any safety related equipment. D/C 81-107 Main Steam Line Trip Valve Modification 2 This design change modified the control circuits of the Main Steam Line Tt.n Valvas by adding a new contact deck j to each of the trip sive control switches and a new limit switch to each trip valve. A new limit switch contact in series with the new cr ntrol switch contact was connected into the existing train "B" control circuitry to provide a " seal-in" function similar to that existing in the train "A" portion of the circuit.

I I ocoRITY NOT QUIRECHANCES RE NRC THAT APPROVAL DECEMBER, 198 D/C 1 81-107

SUMMARY

Main S (continu d) e te OF SAFETY am Lin ALYSIS e Trip Valv AN This e Modific tio a to itsmodification (co n ESF sign l, whethnon safety will Therefo prev a position duri ent r, this s fetyr liability and the e e er v lv or a D/C nt estion. dom dificatio a pow ng the e fro o o 81-108 m qu not n iner is lostres tti es e Additio creas nstitute es theintr)' co n of Lo a an syst This design cl a un CC He d review tank a ee lev l change Tank instrument indi adds Lev l e e a a lo Ind ov erflowing theloop.c tor to the ic tio a c l component a

SUMMARY

can be n Through existing surg coolin av ided. tank OF o S the AFETY du ing m use r AN of e tank ALYSIS anu l this lo lev a This filling ofcl a ind 81-110 componmodific tio this t D/C a ent n do Refu ling Watco ling w ter o es not e a This design er Sto systemaffe t c the age Tank statiooperation or r to he ders to fm ke them identchange n of a Spr y Noz l oper tio the

SUMMARY

a a a ic lreplac d z ns. OF e e Modific tio SAFETY ALYSIS acilitate perito tho a three AN no a odic testinge in the Co s n This n ea h c ainm RWST s fety relatedmodific tio D/C a a ent 81-112 n do Spray es Co de equipm not n ent. affect ns The inleter Tubeshe t the oper tion e Co ting a co de a n side of nsers w alu in any This de ipitting and w m ere um-bro s orming effe texperien ing e tube he t nz " SPEC 0AT" gn s c change s

SUMMARY

co pr blem. e the tubesherro ion i 2 o to c co ted of s SAFETY eliminate the the inlet a s OF m in a e form ANALYSIS et pres The ent andtubenhe ts su fac.of r e e futu with cre teco ting of corr re a a o ion s the a origin l \\ s fety a cond a \\ oper tio de ign problem.enser inlet s a n oper tiocriteriaThe or a and systemtubeshe ts d \\ e of do was n es oes s fety r lat affectr built not a not e equipmplantto its e ed ent. \\ ,, - ^

22 FACILITY CHANGES THAT DID NOT REQUIRE NRC APPROVAL DECEMBER, 1981 (continued) Unit D/C 81-113 Reroute of Pressurizer Relief Tank Vent Sample Line 2 ~~ This design change rerouted sample line 3/8"-SS-399-I-C-N9 from penetration #55 to penetration #57. SIMMARY OF SAFETY ANALYSIS This modification does not create any safety problems. l I l l l

8 IRING g MNE Sa DURING uat THIS REP ORTIN G pgRIOD S7-13g Q 1 Test 18 2

  • M8 fo r Periodic 12 3

( \\ O l i (

Q ~~~a ~~ Rtp0RT'NC P g,0 _ i O g9

l 25 SURRY pokTA STATIO:; 9 6p, o n r.: ' CP.D!ISTRY rep 0RT December,19 HL T.S. 6. 6. 3.d PRIMARY COOLANT UNIT NO. 1 (F) UNIT No. 2 (GI ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERACI Gross Radioact., UCi/ml 1.92 (A) 4.80 ~ 8.46-1 2.44 ~1 4.37~ 3.67 ~ Suspended Solids, ppm 3.45 (D) 0.1 0.1 5.10 (D) 0.1 0.9 ~1 -2 -2 -2 -2 Gross Tritium UCi/ml 1.45 8.16 y,13 4.68 4.21 4.44 ~ Iodine-131, UCi/mi 8.12 (A) 2.40 1.60~1 9.30 2.69 5.47-5 -5 -5 ~ I-131/I-123 .9247 .3966 .5753 NA NA NA Hydrogen, cc/kg 34.8 1.5 12.9 NA NA NA Lithium, ppm 1.50 .19 .77 NA NA NA Enron-10, ppa + 399.8 148.2 240.2 536.1-272.1 393.,6 (C) (C) 0xygen-16, ppm 3.2 .000 '.4 3.1 .000 .4 Chloride, ppm .06 <.05 <.05 .14 (D) <.05 <.05 pH @ 25*C 6.75 5.52 6.07 5.28 4.89 5.02 l l + Boron-10 = Total ~ Boron x 0.196 NON-RADIOACTIVE CIEMICAL l RELEASES, POUNDS l T.S. 4.13. A. 6,- (E) Phosphate 96 Boron 1643 Chromate 0.48 Sulfate Chlorine 502 NaOH l Rcmarks: (A) High values due to suspected fuel failures (B) Reflects Unit #1 start-up & Degassing upon shutdown (C) Unit at cold shutdown (D) Mixed Bed diverted for N H2 4 addition turbitity due to N2H4 levels being high for oxygen removal-Cl hiah due to inadequate purification flow (E) the levels of these chemicals should creat no adverse environmental 1 pact (F) Rx critical @ 1803 12-11-81-Rx trip @ 0130 12-16-81-Rx critical @ 0240 12-16-81 (G) Rx critical @ 1150 & 1555 for unit #2 start-up 12-31-81. lL

26 DESCRIPTION OF ALL INSTANCES WERE THERMAL DISCllARGE LIMITS WERE EXCEEDED DECEMBER. 1981 Due to the impairment of the circulating water system on the following days, the thermal disharge limits were exceeded as noted. December 14, 1981

  • Exceeded 15 F AT across station December 23, 1981
  • Exceeded 15 F AT across station December 24, 1981
  • Exceeded 15 F AT across station December 26, 1981
  • Exceeded 15 F AT across station.
  • Indicates dates where station AT was less than 15.0 F across station for sometime during the day.

The AT excursions were allowable under Technical Specification 4.14.B.2. There were no reported instances of adverse environmental impact. The temperature change at the station discharge exceeded 3 F per hour on December 16, 1981 due to a reactor trip on Unit One. The temperature change at the station discharge exceeded 3 F per hou. on December 26, 1981 when the "1C" water box was removed from service for r, leak in the circulating water outlet piping. These events were allowable in accordance with Technical Specification 4.14. There were no reported instances of adverse environmental impact. e 1 1

27 IUEL HNmIInc DECEMBER, 1981 UNITS oNE Mm Wo NONE DURING THIS REPORTIN e e l I i l 1 l l

28 PROCEDURE REVISIONS THAT CHANCED THE + OPERATING MODE DESCRIBED IN THE FSAR DECEMBER, 1981 NONE DURING THIS REPORTING PERIOD. O 9

29 DESCRIPTION OP PERIODIC TESTS _ COMPLETED WITHIN THE TLE R _SPECIFIED IN TECHNICAL SPEC DECEMBER, 1981 NONE DURING THIS REPORTING PE7 i l 1 I f s o a l I e O

30 INSERVICE INSPECTION Decenber. 1981 UNIT ONE No inservice inspections vere conducted this month for NDE. UNIT TWO The Westinghouse Program for inservice inspection was completed for this refueling outage (No.5). There were several minor penetrant and visual indications noted. These indications were all repaired and re-examined and found to be acceptable. There was one ultrasonic indiention that was noted, but was evaluated to be within acceptable code linits. This indication will be monitored in the future for any characteristic changes to insure component reliability. An evamination of all ASMC Class III component supports and hangars was perforned. Minor indications were noted and hate been subnitted for repair as station maintenance scheduling permits. An eddy current evenination was performed on A, B, C, and D recirculation spray coolers. No indications vere noted. Also addy current was performed on A and B steam generators. Approximately 16% of the tubing was exanined in each generator. There were no defects noted. As required by Surry Technical Specifications, an examination was performed on verious sections of sensiticed stainless steel piping. No reportable ind. cations were found. Prior to Unit start up, a hydrostatic test meeting the requirements of ASME Section II 1974 edition thru sunoer of 1975 addenda, was performed on the entire class I identified cooponents and piping. No evidence of leakage was noted at places other than where it could be expected '(ie. valve stem packing pump seals, etc.). The evanination was found to be acceptable. l

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32 REPORTAB1.E OCCURRDICES PERTAINING TO ANY OUTAGE OR POWER REDUCTIONS DECEMBER. 1981 l NONE DURING THIS REPORTING PERIOD. t t f 4 l d f i r I

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l s e g.. _. N N. _ _. 1> e URira-d- . (M. A_ INT.ERACE Of._ SAFE. TT.RELATED.STSTMS DURERC_ _QU._TM..E OR REDtR~ED.FWER PER1005) O RETSERVDT STS COWP MARKRO SM MARY VKPERT D MR TOTT%iR1w e ~' tillkli1 ' M ~~REMT H kr%6VE AND 1h3 fall NRfDETtlJb lihiill k:Rf6R kik5 ~ ~ ~ 2 iliT555&i '~ ibbi ~ ~ ~ ~ 12/12/81. M SRUMBER 2-RSS-N-38 SRf!B N R 1RSTAllED BACRVARDS TintRED SRIABMER ARRXIRD 2 111111111 s03 ~ f.) ' 12/12/81 NC FLAME TE-2%92 FLAME STit) REAVILT CORRODED REPLKED CASKET ARD ALL STtR15 2 111182121 518 kk/lilii' ~ M SRUBBER 2-RSS-E*18% REMVE SRURSER REPA! RED 9 UMBER 2 1120612%$ 152 12/12/81 RSS SRUBBER 2-SRP-RSS-35A SRUBMER LFAK! M 0-rat!UD SRURNR 2 112081119 105 12/12/81 RSS SRURSER 2-S!!P-RSS-3 5R SRUBBER timinc 0-RAtit. ARD TESTED 1RSTALL 2 112081120 105 12/13/81 43 VALVE 2-#S-378 P KKinC EAAK AfPACRFD VALV8 ~~ '- - " ~ 2 tl265I5si l%i ~~ 12/13/81 BD VALVE tv-BD-200E VALVE RAS A 9 TALL PKKERC LEAR Rt' PACKED VALVE 2 112100800 31 12/1%f81 MS VALVE RW!R AS REETED MAntifACTintt PKKinC CLARD RinC 2 1120913%$ $23 $2/t%)Si ~it5 MilV5' 2Y:M5'201C kkPk55 LEAK 59 5EE.55 ~ ~ ADNO PKKIRC 2 182100002 11 3 12/1%/81 MS VALVE 2*lS-311 BTPASS VALVE LEAKS REPKKED 2 112100803 1% 1 t2/t%/81 RC-Ellil 2466I i M U5f'd# h5P5Cf ~ ~ ~ ~ AN UM PACKlid 2 il2i6isil P!PinC 1-nc-P-LC REPAIR SEAL WATER 1R TE.ANCE REPL KED CASRET ii/ii/Ei' ~M -~ 2 ii1801602 91 ~ ~ ~ ' 3' ~5 12/1%/81 NC VALVE 2ns08 ANUST OR REPKK ANUST PACK!RC 2 St2 tots %9 ss ) 9 12/t%f81 R9 PtNP 2-M-P-tA REPA!R C0t!PLERC REPAIRiv NECRMICAL SEAL 2 1ittti2%Q 53 52/i%/81 "kN ' ~ NNP ~ 'i:liit-P-in ~ L5Akl56 55CE555VELT REPhlN5b it55b5fdbl*$5kl ~ ~ 2 112t22301~ ~ 55 ~ ~ ~ ~ ~ J 12/15191 C RV 1RSTAll/Rr'MYE REKTOR CAVITT SEAL C0wPLETE 2 110090158 8%8

t t2/15/81 C STUDS RMOVE/RE!RSTALL REKTOR VESS StilDF C0wPLETE 2 t10090n0t 8%9

' lillilif' 3 58 ~ 5NilBIGR H Rtbh4 5kUhh5N fl5Kfl6Nkl$ T25ftD'SRUNDER9 ifME6h6b5?iEl19 P 2 tib690312 8%% -~ ' ] 12/15/81 RSS SRUBBER 1RSTALL FilRCE + Filt. RTR VALVE BLEK NR VfLE 2 110290930 8%1 ~ '1 12/15/81 NSS SRUBBERS R*R V4 VIE MLOCK 1RSTALL PtntCE + TELL RTR VALVE RLOCK MR WTLE 2 11029493L 8%S 15/t5/61 Rss ~ Shuhst M ~1kSthll nikC2 + till ~ ~ " ' RTW VJLV2'hlMi Nk irits 2 816i56455 ~ ~iii ~ ~ ~ ) 12/15/91 N VALVAR 2-N-89 REPLACK VALVE REPLACED CRsCE VALVE 2-N-89 2 s10290941 5s5 [ ) ~ 12/15/81 VC VALVE TV-DC-208A VALVE EAMS OVEMAtiLED VMVC 2 115132311 303 ~ ' lillSlii ~Re VALVE 2-hit-%1 VJLVi~h6hirTithUnC 153fkllEb'Riii ChSRET t tU141460 308 ~~ ) i2/15i81 NC RAMER R*1 REPLACE CORRODED U-BOLTS REPL C D U-BOLTS 2 1112309%1 50% ,1 12/15/81 VS VALVE

  1. 0V-VS-2000 M V-VS-200M LEAKS REPA! RED VALVE SEAL 2 112081801 111

15/1S/6t ' 31 ' VALVE 2-31-15% bHR VALVE ' ~~~ ORilbiblVE ta N69fbt r~ldiiFin 2 11209t059 1%9 J 12/15/81 WS VLAVE 2-45-ins BODT 10 80ERET LEM REPERED VALVE 2 11209134s 1%2 ) 12/15/81 VS DtA~Tinc NOV-VS*200C RDt0VE DtK11RC RMOVE DtA~TinC INSTALL BLARK FLARCE t 112121231 10 ~- ' IillSli1 ~ ~ Vs ~TnW ~ MV-V3;2000 VALVT ERAT L%hi3 B Y55 1R3FeiflD hi5'ELEhith'51x ARD SEAT 2 112130138 59 ~ t2/ts/81 BS MAINAT REPA!R NR RA1CR REPAIRED TLATE OR MAA8/AT 2 112131330 %8 l, Ellis!% R* PuvP.. __2-mf ta _ set tzM _ _ _ _ _ _ __ _._ _ _.. rinED_SEntt._ 2 1t2131500 %8 12il5/81 VS MOV NOV-VS-201 VALVES LEntS 81 AT 25 SCFR Ril'LKED SEAT 2 1521%0309 %2 12/11/81 SV PtMP 2-M-P-104 PLMP LOCKED UP REPLACED RN EMPELLER WITR Cln ORE 2 1121st310 to 12/18/81 AC VALVE SV-2551-B PERF09t DtP-CM-Ot t COvPLETE 2 11009t%O0 855 liliflii Tt3 VJLV2 tV'3ti'io1C ikif F6f2 f# FlV fli3 CatPLEr8 2 11%151008 %D 12/23/8t CC VALVE 1Y-CC-2094 THIS VALVE ERAMS REVOMED VALVE 2 109050100 10%1 ? i2/23/81 N VALVE NOV-w-203A itiLL VALVE TEST ARD REIRSTME. St!MBtE TESTED 2 t102910$s tots ~ 12/23/ik SV 'lfklik 56 -N-ib55~ ~l'till V' hlVi f5ST bid kkii$Thil' NUBBl[f55T55~ ~ ~ ~ 2 ti559555i 1555 ~ 12/23/81 N VALVE MOV-N -203C PULL VALVE TEST MD REIRSTALL BURMLE TESTED 2 110291100 1035 ~ 12i23/81 SV VALVE NOV-SV-2030 Evit. VALVE TEST ARD REIRSTMt. BUBBt2 TESTED 2 11029110% 1035 n 11/53/45 N ~ VALV2 ~ ~ ft0V6kb5A Mill V4Lil f5St kh5' HEN 5fkil~ RMOVED BVMHN TEST GNASED REIRSTAL 2 11029t120 986 u = 12i23/81 N VALVE NOV-N-205R ti/LL VALVE TEST ARD RKIRSTME, RDt0VED BtfRBLE TESTED CREASED REIRST 2 11029tt3s 981 12/23/81 M valve MV-N-205C PULL VALVE TEST ARD REIRSTML REw VE ntlBMls TEST CREASED REIRSTAE.L 2 1t0291t%8 181 6 12123181 SV ' 'FALV2 ' NOV M 2D50 Pull VALV2 TEST AMI REIRSTAlt~ M0VZn ntlRRLR TTETEM'CHAsih H1 RET 2 11hiiliis i12 12/23/81 51 MOV NOV-2ns1C NOV-28s1C ARD at0V-28s1D E2M RM CASKET + PKK!8C 2 tit 0023%5 in3s j !

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P8C COvPQTK W E2/02/91 SV NOV M V-N -2034 Dix ARD RK0W POR NEOF RE0ERETED NOV 2 (p993Q639 }?t _ 2 1110%K502 5%9 12/01/81 SV NOV NOV-W-203R DIK eRKOM NRNEM RK0ENCTED NOV 2 1110%1103 569 12/02/81 MS VW TV-NS-totB val,VE D!D ROT CEDSE NO PROCEDr g _ U198$111 _t_,___ ~ 12/02/81 14 VAWE W*IA-2018 DIZ/RK0W NW NER DIK + RK0W FOR N20t 2 111331100 181 1 8 12/03/81 SV 40V SV-201A iMS PEFostKD MS 08 NOV-W-201A SAT 2 109030630 18 12/03/81 _SV NONR MV-W-201A T10R_CR0tAFDED_ RMA! RED N010R_SATMi&D VALVE SAT 2 11Donst 12 12/08/81 W MOV N 2038 MP W-E/C1 SV-NOV-K/A1 + C2 MS CGrPLATK 2 109090501 549 12/09/81 CM PtNP 1-CR-P-20 PtMP VILL NOT RUN 1R AUTO OPERAT100 Of W 11CR 15 SAT 2 111210%25 1 12/10/81 DC VALVE

  • W-DC-208A VA W E VILL NOT NOVE REPLKED M SAT

~ tilib/8i ~ 55 Q i &i ~ ~ jV-S5-20mA Vidt V5Lf, M0i d5CLR Vi&5 bPDktii ~ ~ 2 112080901 91 ~ ~~ 2 1125908i5~~5~ 2 12/10/81 Rs VALVE CN EK OUT VOLTEK 2V 8113 REPLAr RMLEKD*Riftst#dD F0 SENVTCK 2 112101220 1 [ 12/11/91 SE NOV NOV-2861D ELE T. N OBEDt ANUSTBD LEWITS 00 NOV-38610 SAT 2 111111230 11 ~ ~ ~~ ~~li/fi/it ST NOV NOV-28ssC EE.kW.~hidei,as Aw&SnD unsTS On NOV-18&C 3AT 2 1i51i1231 st ~ 12/12/81 SV NOV NOV-N -2028 NOV PLOODED Ot!T DEK00EETED AWD RE08EET SAT 2 112091000 91 [ 12/12/81 SV NOV NOV-N-tota NONR GR0t/WDED D1% AND RE00 SAT 2 tittttt35 30 ~ ~ e Lt/ttlit~ St~ VALV2~W;31;ibla ' VALV2'DFENs FWl'06 Mdit JhT0iTEWlNHT0lER 2 tiil16138 30 12/12/91 04 VAWK W-DA-2005 CREK LIMITS CR8CKED UWITS OPERAT8D SAT 2 112120910 12 ~ t2/12/81 DA VAWE 2-DA-200A AN UST f.141T A N USTED LENETS ~~ 2 11tt18600 2 11/1blii *

  • F3^RMIET2-VS-r EA RUJ1f As RREs@tt RWA 1WUkhs'AhT0iTsD aHMER 20 s 2 ilti6ilI2 so 12/13/81 r RELAr m-mPr RzPLes C0rr, RaPf,EED C0fL If RELAF SAT 2 112130645 29 7

12/14/81 M NOV NOV-2593 RErter wr0R a7r IsSTAtrao st=0 STrar, u r 2 108191=31 s 'li/is/il"E iidV miF;E-2592

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108191=32 8 + 12/st/81 m wr wV-2591

  1. Ff,ACK N010# Pfff04 KPr REPL E8D N0f0R PINION RKT SAT 2 108191433 0

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  1. 0v-2590 REPtxt wNR Pin 10E Rav EsPixED Pinson Rsr SAT 2 10819tm3%

so if/islii E Nor af 2590 Tiri-~ - ---' FiFdivs0 M5 biiv0r-r-2590 SAr 2 16isiO9c9 25 r 12/1t/81 e er E 2591 INS FrarmerED MS ce mor-2591 SAT 2 109010910 8 s. !?/l*/81 aC __ wr _. _ aC ggy . _. MS _., . 12/14/81 E NOV E 2592 MS mPtsT MS 2 _ 1910ltfl2 19_ COP 8PC2TED MS SAT 2 109010915 8 12/in/81 RW NTR 2-RM-P-SA DIX + RE06 NONR RKORRETED 2 112t31501 18 ik ' _ _. !?/I"/88 _F8 __M.'M. _.._.NW-VS-301 SET UTITS,0# #0V-VS-201 ANUS 11D UNITS 2 1121M991 4 $2/15/81 M NOV MV-2595 ROLME wNRFIR100KET 1RSTAllED %1%D STEEL RET 2 108191438 12/15/81 E MOV AC 2595 rws CowPfETED MS 2 109010914 4 12/$1/81 SV _ NONR _, 2-W-P-10A _ _. DIK *RK00_M10R NRNER DIK_t RK00 N_R NER_ 2 111101530 185

== {' 12/18/81 R9 l%P NTR 2-RM-P-1A RiTlKE TilK LOVER ATO REPLKED RTO 2 112t50529 5 12i21/81 MS NOV RS 200A E9ts PERVORwKD INS 06 NOV-RS-200A SAT 2 109010900 3 a f 1 3,

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.1 PEM 0LotEn._ Pus _ on n0V.-us-sonn SAT _ _ 2__,__tg9eto901 _. 12/21/e1 ns n0V as too: Pts 2 109010918 2 82/28tst Rs NOV Rs soon PwS Nar0mED Pvs on mov-m-212oA SAT 2 109010919 3 12/21/et As McV m 21204 Ms NMOMED NS OW MV-M-titon SAT 2 tiltinog _.121_._._.._ _ __. 12/31181 M NOV M 21200 PMS VALVE OPERATES SAT 2 112230ess e pi23/s2 N NOV NOV-N-1stC inTEMEDIATE inDICAT100 VALVE cuscuEn SAT 2 $o0210132 59 12hilst CS mTOR 2-Cs-201 A uno cRounO VALVE CRCEES SAT ANUsT80 UNITS _ _1.._$$\\112$39._____39 x VALVE WILL MT CTCE2 POR PT 18.88 RBt0VED REAT TAPG AED PVT BKK 02 12/2%f81 sS VALVE 27-ss-20tB 2 112221o45 3 RE40VE HEAT TR King 90R VALVE RO fir 06 tar Pat /#D L2/2?l*l.. SE._ RT _2-S!-9 CN-2115D WILL NOT STAT OPEN ADJUSTED UN!Ts 06 SV-NS-to1C SAT 2 1122s1650 t r 12/26/81 CT LM C#-21150 2 100310131 tone ANUST UNITS OR 2Y-Ms-201C PEM0 min 1905 OR BREAKERS ~ ~ ~ ~ ~ 2 165ii6332 1069 12fts/81 MS VALVE tv-Ms-totC 12/21/81 RS N010R 2-Rs-P-2.8 P45 tM NAF0mED PVS MP-f/itf ~ 2 1122e19eo 60 '- ' lihilil~ ' #s NoiUR 2-RS-P-25 1995 '1 5 REPAIRED NO20R SAT 2 1122113o1 3 12/21/91 N NOV t-N-206D RD00VE N010E REPL K ED DVERLOAD ass 0tBLT ~ ~ ~ ~ 2 1122entos e 11/21/81 SE MOV NOV-2065C REPLKE OVERLOAD ASSFtRLT RrPtxEn REur t 1122611%9 to ~~ ' 'lil5bli1

  • TC ~~RRkf'~Fc^;iis~YA RarucE raut.TT REuT ant /STED UMITS SAT 2 te92so2tt 231s 12/29/81 Ms 50V

$0v-MS-2028 RDt0VE-s0V-Ms-202M no Pn0else rovr0 RESET VinRATron Picr OP 2 tito2o12s t L instr 2-Rs-P-sn CLEARS 0 Aum 2 111111506 1 w .otiottez _ Rs ts-DA-12tn VALVE PIT is DRT*Aum is zu CE2Akan Aum ollb5les DA instr VALVE PIT l'tPTT ALAm STILL 1R ttio3/92 DA S11CN LS-DA-St98 29e66 bh'_T NTAL er 41 -en.e 'l 2 i, 4 -pwN + " * * '

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44 Maintenance of Safety Related Systems During Outage or Reduced Power Periods UNIT #1 s Instrument Maintenance e l l l l l l

e en e e e e e S , }.y e ~. y 3 DURt9C CVrACE t*4 RBDtKED 90VER PER1006} m wrwm j'. i ter!rt-(NAJErNAECE M sATEr1 RElkrED s1SW)e s-ssseseeee - so ,l unscsr a une w 1 2Hmm ,,:( 69 ran rene-svicE -nsanusm emotwer test - snnem is W AWM s2Mi#r s noesnwe naanno sts cowe smsms sis rnses am ancs snernsue - --n -tsreste=s msanvor srs - - nale3tes m -mainn--m-ce-tesises-sarmint antasiC# Aum s# NIM NW r0 M W nartA:Ea erracm titt311ss 93 -. ain c.3nt varun to srAnr RD' LACED Ol%RialR$100 CARO u

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48 3.* HEALTH PHYSICS DECEMBER, 1981 There was no single release of radioactivity or radiation exposure specifically associated with an outage that accounted for more than 10% of the allowable annual values in 10CFR20. e

i.\\ As PROCEDURE DEVIATIONS REVID7ED BY STATION IUCLEAR SAFETY AND OPERATING CO:21ITIEE AFTER TUIE LUiITS SPECIFIED IN TECDiICAL SPECIFICATIONS DECEMBER, 1981 NONE DURING THIS REPORTING PERIOD.

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