ML20041G172
| ML20041G172 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| 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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VIRGINIA EI.ECTRIC AND POWER COMPANY SURRY POWER STATION MONTHLY OPERATING REPORT REPORT NO. 81-12 DECEMBER, 1981 APPROVED BY:
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O 8203190353 820114 PDR ADOCK 05000280 R PDR
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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
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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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l CPERATING DATA REPORT 2,- _ ' CC:rr:ct d C;py i for November Report I DOCKET,NO. 50-281 p DATE 17 DEC 81 COTPE.ETED By Vivian H. Jones , EElEPN0//E 804-357-3194
.fPERATIhGSTATUa N ,-
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- 1. UNIT HAVE SURRY UTlIT 2
- 2. REPORTIt.G PERIOD 11018: TO 113081
- 3. LICE 2aED THElif.fAL POWER (.WT) 2441 l l
- 4. ?;AMEPLA2E RATING (GR0da WE) 847.S lNOTEa ~
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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 1E '7,IT REdiRVE SHUTDOVN HOURa 0.0 0.0 0.0
- 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 */* S8.6 e/o
- 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
2 l* :,'?EiAT:7G DATA 17E?OET DOCKET 20. 50-2C1 DATE 09 .T4!' c
- l. 0'!?LETED BY Vivian H. Jones TELE
- HONE 804-357-319s lH7AT:.. STATUC
- 1. L7,:T oli? E SUri3Y l. WIT 2
- 2. l'i?:o.C':;.'G PElll2D 120181 TO 123181
- 3. L,', :a..o.r.,D :..,cn - ,A., POL. .c is ,. ..s.. .,, ) 2s41 l----------- --l ,,
4 *eA'?E?Li2E nAT::!G (GEOSS %!E) B47.5 lllOTES l
- 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 !i/A
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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 7sees .0 8760.0 75008.0
- 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 e 33677179.0
- 13. ?;ET ='LFC:h' CAL EGERGY GElEEb7ED O*JH) 1220.0 5150227.0 31923715.0 13.17:t Si'hV:CE FA:: d < 0.3 ele 79.6 ele 53.0 ele
- 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 e 53.3 ele
- 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 E ' AC4) 10 DAYS 2S. :F SHU:' D0k'll AT EdD OF TiEPOET PER:0D. EET:*' ATE ') ATE OF STAT 5'UP
- 25. Ul.:CS ll TE: STATUS FORECAST ACH:EVED il-5:-)il TO C3 '.<EEC:AL O!'EEAT:0ll)
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d 4 DOCKET NO. 50-280 . UNIT SilU1 DOWNS AND POWER REDUC 110NS l UNirNAME _ Surry One g DATE 1 2-31-81 COMPLETED gy Vivian Jones 4 REPORT MONTil DECEMBER. 1981 1ELEPilONE (804) 357-3184 ext. 477 "y tb. Daic i
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Licensee Event Eg g'ir k '8 Cause & Corrective Action to F- [E E 3gc Report a mO u o u Prevent Recurrence 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. 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 DOCKET NO. 50-281 - UNIT SIIUTDOWNS AND POWER REDUCTION 3
' NIT NAME Surry Two
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DATE 12-31-81 REPORT MONT1g DECEMBER, 1981 COMPLETED BY Vivian Jones TELEPilONE (804) 357-3184 ext. 477 "E c re 3 us : 5 Ee E EX Lkensee 5% Cause & Corrective No. Date { ii ? 4 7 2s5 Event uy k%'g u
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- 1 81-17 12-01-81 S 737.7 C 3 continuation of refueling shutdown which commenced November 7, 1981.
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,* 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) i E-Operator Training & IJceng Examinatiu.t F Administrative 5 G-Operational Error (Esplein) Eshibit I- Same Source l's/77) Il Other IExplain)
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, 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 _
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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 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. i December 22, 1981 The "C" S/G secondary side hydro was compeleted at 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 I DECEMBER, 1981 ) I 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 Nos an . 72 Duc l"c De c OR cd n r R:gulc TECHNIC AL No.d822 Th 3 73 to emb:r 1981 to change tha Opery r m Co s
These am THI-2 Le endm n s hav e be atingnLicem is io , o ns areas sso e ts in en design a n ted September instr of n Lear co emerge ned rporate e for a Sur ,h e um ofe dw entatio ny c t s Technica et ater nf powcategory er s "heA"requir 5 utside co e In ntainsystems,or inadequupplynr itens n ad met n ate equir . me ts for im addi 3.B of tio core n to and the to inplem oeme tThey spe n c plen ifie follow :the Oper t s the r accur co entation ling,s, c n v a lv e c ll a of pr s (Unit a ing Licequir em n e ts ately deter o tainme n nei ogra n tpo tii ense of The Tea hnic1) Am n c Tech "B. s for Unithe airboms rn rec to e dm shall ent Sp cnica l S t I c Te ca hni e iod. oper No.l72 ,e ec if a and 2, lr Spec if a ifications (Uni t re he e ic tions co espe tiv lyi c a
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The Te hni e dm n ca Te c hate the facil cnica l S i r by in co ty in ntained rpo ac cor dar atedin Appe d shall ope et rNo.l Sp e if c nce n ixlicA, as ate 7 ,e ificatio 3 e ns c a ic tio in the with e n i ns c ns .revis d e the fac iliare her by the Te hni e ty in nocorpor tained cal The lii ac in Appe n dix Spec if cordance ated A within the lic e
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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 i This design change connects the fire protec 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.
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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 j RCS. Consequently, the number of personnel exposures 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
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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 main design change provides for 2 and the bypass feedwater regulatorsegregation of the controllers. If necessary valve would allow for partial sys, tem reindividual isolation repairs are being made to thecovery area while
SUMMARY
OF SAFETY ANALYSIS of failure. This modification increases th system by allowing the air controlle versatility of the main or the bypass feedwaterers regul on t either the required of individually rather than valves inoperable. a orh valves to be 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 an 2 ; and control devices. control room sables and auxiliary n panel monitoring
SUMMARY
OF SAFETY ANALYSIS ~ 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 2 the containment by us'ing aThis otential for fire in design change re reactor coolant temporarily pump motors. collection system on the stores The system collects and of the RCP motor lube anyoillubricating system. oil which leaks out 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,athere arenot affect the opera 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 -
- - - - - - - - - _ . , , ,, -. - 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
e M DE . at. NRC THAT s CEMB APP
' ROVAL ER 1 98A
. AW S (cent inued)
N Th stem Cavi of is design tatin The the Ve v n thre change nturi the e tu I affe riees inch add S c Addi tio n SU}MARY or MFLB cted will AW r s ed l ste ines.avitating v i OF to the inin is de ta t cont am ge e trict to e SAFETY AN c ner loops.ainm nator the f ah c entu r w steam g.g i ALYSIS e t) pe(r .e.lo of This l mit , lo fede
. of md ting op with prothe Auo ifi :st gr D/C a cedu xil io eater 80-8 uxil res n do es 6 williary Fe e w dnot Modif iary fe e dw ha v dir c a ate r flowe mod to beater Systee t t
ic tion m al The fol imple of Ma r ate. ified tho to ugh ge the m lowing sona e ope ops ented in po rtio Walls r flect rat 19 D/C respo ns of the) 80-8 ns th 6U D/C Modif e to IEis des ign
SUMMARY
OF 80-8 change SAF ETY 6V ic ta ion ModAB-27-6-2 if of Bulle::in 8 0-11. were AN a Ma ALY son SIS D/C The oper co AB-13-0-7ic tio . n of Ma ary Wall 80-93 atiompleted son n of mdo if ary Wall Diver a _Lo,o ops sif in s fety r liceta ions Th Po w ated will er Su equipmhav e no TCa is design 1 ent. Pumpsnd T cha to T effec t n u loops,nge 3 and T on cir ad s the betwculatio a so epar Re c e s a to SUMM ARY OF loops.e n by theny vital bus ,t with the thapowate r Coo lant SAF n the T 'and u use of the ope a lo ss er s ETY T up lp ie AN Con the d rator of Re ALY SIS at le iffe re can varto c s c.f the 2 This ats it do es modif two ntial e ify n o lant rea totemper Co noticcrt ton defin a c r atu a ed r atu rerl ea te incre
, o in 10CF a as e co lant R50 .5n9 "u nr sv the e iew edsystem sa fetyrle iab -mew w ..
que ilit stio n"y and
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,_D DE NRC.s3 THAT 0 9 APP fC,__8 _92 CEMBER 1 ROVA 981 Bs r (cc atin one ued)
Bu
/ Por tio s Under implemn sA SUM vlo MARY n B ta OF (degr a ded) and de Dte , inv e Prl SAF o of ETY n th ote tc io AN ALY SIS u derv o lving thesis de nign tage Moe This pr addi tio o n ofcha ote tion nge 1.
Spec ifm dific c a s daf ic c ined atio ns ation system.es D/C 80-9 9 sin a luded in 1 on Faddr fety qu a esses in s th0CFR50 i
, noSafety An 59inchange l
, n Co tainm e tio n.s design ne of a l change the s to Te cth ent c Sum ysis co mdo if Repor quickThis de ig s Pun nt t.
4 c dis n Re la s itute icanationo
SUMMARY
adis harge cce s conn hchange ec pr v c ement u nrc OF SAF s ib il se , ts fo r o ide o
- ETY ity foran ti c s the pr D This ANALY SIS a tipp ingaofele m intenan oper tric l pu f_C_81-13 1 or themodif c.e puwiring a mp and n dmp cc a
ope ic tio e theapa pu ityt n as ier mp 4 Meteo o rta ion ofwill a not r lo ica l Mo n i s fety r ela alter data c s ton bThistode rin ig U ted the stat
SUMMARY
ba kup toe trchange equipm ion ent. oper OF Appe d wer ans m it pr r ade atio SAF n ix 2 of n s to thetedovide co dir es fo r the ETY AN ALY NUREG0 654.nt or lctly fr m SIS eteo roo o cThis o apab mdo if m inm themarinlogica l a e il ic acc adn C orda _D/,C,__8 1 1, -14hasr pr dun dan tity ofatio a n does nce with evio s sousrce fety re lnot af LHS I u ly be of m ated fec t and en Th ORS av eteoro systemthe Fun ailable. logica l oper rle iab a tio ili LHSIis des ign Casin ty or no and nge s data ton. It allw beingsdpump uORSccha r epla e Re tr ints a that on ly deter ap lp ic b e s cd which pr ovides integrmin e d a le is TORLONa s ing r ated not proper tie . e trthe teflo n rd to be s Thisaints. plugs a iatio qu la ifof mat r The u e n do se iedteflon .e ial m new sd a in 2 at e r theto pu the Tefloa e n ts m or te ialthe mp lo u was exc e c alc lated e ds c tio .n total 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.
,,_,_,,,,_.,,..,,.__,.,.._,_,,.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 RE
. QUIRECHANCES NRC THAT DECEMBER, APPROVAL 198 D/C 1 81-107
SUMMARY
Main Ste (continu e d) OF S am Lin AFETY AN e Trip Valv ALYSIS This e Modif ication to itsmodification ESF (co sign l, whethnon Therefo e a prev safety will ent e r , this erposition or nt the duri va lv D/C s fetyrquliability oand a o pow ng the e from 81-108 Additio n estion. dom es not co ndificatio iner is lost tti creas res e of Lo cl a nstitute an es theintr)' syst a CC un This design tank Hea d reviewee leve l change Tank Leve l Ind instrument indi ov a adds a lo c anerflowing be theloop.c tor a to the ication
SUMMARY
OF S o Through c l component AFETY AN av ided. tank duringthe m existing use of surg coolin ALYSIS anua l this elotank cl lev This filling of a ind D/C componmodific tio 81-110 ent a n do es this t o not Refu ling Watco e a ling w ctert systemaffe or the toThis a design er Sto rage Tank statiooperation n of l oper tions. the a a a
SUMMARY
OF S he ders to fm icke them alreplac dthr e identchange Spr y Noz z AFETY AN ee ALYSIS acilitate perito s tho no e Modific ntioa D/C This a odic testinge . n ainm in eachthe Co RWST a ent 81-112 s fety relatedmodific n do es tio Spray Condens equipm not ent. affect the The inleter conde side e Tubeshe a Co ting t opera tion of nsers w any ere alumin s This de s ipitting and um-bro wnz
" SPEC 0AT" change o to gnorming effe c c
texperien co s s e ing e tube he t
SUMMARY
OF pr blems . coa ted of 2 SAFETY ANALYSIS eliminate presthe the the tubesherro inlet et e form r ma in ion in ent andtubenhe e su fac e.of ts The a futu re with createcoa ting of corr s \ origina l sa fety the cond o ion \ oper tion de ign problem.enser inlet a s or The \ opera tiocriteria n of and dosystemtubeshe e ts d a es was oes not e not s fety r late affectr built ed equipmplantto its _ 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
g 8 Sa IRING MNE DURING uat THIS REP ORTIN G pgRIOD S7-13g Q &, 1 Test 18 2 *M 8 fo r Periodic 12 3 ( \ O l i (
~~Q ~~~a Rtp0RT'NC Pig,0 _
O g9
l 25 SURRY pokTA STATIO:; 9 6p, o n r.: ' ,, l
. CP.D!ISTRY rep 0RT December ,19 HL T.S. 6. 6. 3.d PRIMARY COOLANT ANALYSIS UNIT NO. 1 (F) UNIT No. 2 (GI 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 Gross Tritium UCi/ml ~1 -2 -2 ~ -2 -
-2 1.45 8.16 y,13 4.68 4.21 4.44 Iodine-131, UCi/mi 8.12 (A) 2.40
~
-5 2.69 -5 1.60~1 9.30 5.47-5 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 0xygen-16, ppm 3.2 (C) .000 '.4 3.1 (C) .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 Sulfate - Chromate 0.48
. 502 NaOH -
Chlorine 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.
l L_______--__ . . _ . _ _ . . _ _ _ . . _ _ _
I l 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 REPORTING . 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 SPECI 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
. .. 33 4
e Maintenance of Safety Related Systems During Outage or Raduced Power Periods ( IktIT#1 Mechanical Maintenance J
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~' tillkli1 ' M ~~REMT H kr%6VE AND 1h3 fall NRfDETtlJb lihiill k:Rf6R kik5 ~ ~ ~
12/12/81 . M SRUMBER 2-RSS-N-38 SRf!B N R 1RSTAllED BACRVARDS 2 iliT555&i '~ ibbi ~ ~ ~ ~ ~ 12/12/81 NC FLAME TE-2%92 FLAME STit) REAVILT CORRODED TintRED SRIABMER ARRXIRD 2 111111111 s03 f.) ' kk/lilii' ~ M SRUBBER 2-RSS-E*18% REMVE SRURSER REPLKED CASKET ARD ALL STtR15 REPA! RED 9 UMBER 2 111182121 518 .. 12/12/81 RSS SRUBBER 2-SRP-RSS-35A 2 1120612%$ 152 SRUBMER LFAK! M 0-rat!UD SRURNR 12/12/81 RSS SRURSER 2-S!!P-RSS-3 5R SRUBBER timinc 2 112081119 105 . 12/13/81 43 0-RAtit. ARD TESTED 1RSTALL 2 112081120 105 VALVE 2-#S-378 P KKinC EAAK ~~ '- - " ~ 12/13/81 BD VALVE tv-BD-200E VALVE RAS A 9 TALL PKKERC LEAR AfPACRFD VALV8 2 tl265I5si l%i
~~
" Rt' PACKED VALVE 2 112100800 12/1%f81 MS VALVE RW!R AS REETED 31 ,: *
$2/t%)Si ~it5 MilV5' MAntifACTintt PKKinC CLARD RinC 2 1120913%$ $23 3 2Y:M5'201C kkPk55 LEAK 59 5EE.55 ~ ~ ADNO PKKIRC 12/1%/81 MS VALVE 2*lS-311 2 182100002 11 BTPASS VALVE LEAKS REPKKED t2/t%/81 RC- P!PinC 1-nc-P-LC REPAIR SEAL WATER 1R TE.ANCE 2 112100803 1% ,
1 REPL KED CASRET 3' ii/ii/Ei' ~M Ellil 2466I i M U5f'd# h5P5Cf ~ ~ ~ ~ -~ AN UM PACKlid
2 ii1801602 91 ~ ~ ~ '
12/1%/81 NC VALVE 2ns08 ANUST OR REPKK 2 il2i6isil ~5 9 ' ANUST PACK!RC 2 St2 tots %9 ss 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*$5kl ~ ~ J ' 12/15191 C RV 2 112t22301~ ~ 55 ~ ~ ~ ~ ~ 1RSTAll/Rr'MYE REKTOR CAVITT SEAL C0wPLETE 2 110090158 t2/15/81 C STUDS RMOVE/RE!RSTALL REKTOR VESS StilDF C0wPLETE 8%8 ; t
' lillilif' 3 58 ~ 5NilBIGR 2 t10090n0t 8%9 ,
~ H Rtbh4 5kUhh5N fl5Kfl6Nkl$ T25ftD'SRUNDER9 ifME6h6b5?iEl19 P 2 tib690312 8%%
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] 12/15/81 RSS SRUBBER 1RSTALL FilRCE + Filt. 12/15/81 NSS SRUBBERS RTR VALVE BLEK NR VfLE R*R V4 VIE MLOCK 1RSTALL PtntCE + TELL RTR VALVE RLOCK MR WTLE 2 110290930 2 11029493L 8%1
& '1 15/t5/61 Rss ~ Shuhst M ~1kSthll nikC2 + till ~ ~ " ' RTW VJLV2'hlMi Nk irits 8%S .
2 816i56455 ~ ~iii ~ ~
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) 12/15/91 N VALVAR 2-N-89 ' REPLACK VALVE REPLACED CRsCE VALVE 2-N-89
~
12/15/81 VC VALVE TV-DC-208A VALVE EAMS 2 s10290941 5s5 [ ) OVEMAtiLED VMVC 2 115132311 303 *
~ ' lillSlii ~Re VALVE 2-hit-%1 VJLVi~h6hirTithUnC .,
) i2/15i81 NC RAMER R*1 REPLACE CORRODED U-BOLTS 153fkllEb'Riii ChSRET t tU141460 308
~~
12/15/81 VS REPL C D U-BOLTS 2 1112309%1 50%
,1 VALVE #0V-VS-2000 M V-VS-200M LEAKS~~~ REPA! RED VALVE SEAL 2 112081801
15/1S/6t ' 31 ' VALVE 2-31-15% bHR VALVE '
111 .. J 12/15/81 WS VLAVE 2-45-ins ORilbiblVE ta N69fbt r~ldiiFin 2 11209t059 1%9 - BODT 10 80ERET LEM REPERED VALVE
~-
12/15/81 VS DtA~Tinc NOV-VS*200C RDt0VE DtK11RC 2 11209134s 1%2
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' IillSli1 ~ ~ Vs ~TnW ~ MV-V3;2000 RMOVE DtA~TinC INSTALL BLARK FLARCE t 112121231
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VALVT ERAT L%hi3 B Y55 1R3FeiflD hi5'ELEhith'51x ARD SEAT 2 112130138 t2/ts/81 BS MAINAT 59 - REPA!R NR RA1CR REPAIRED TLATE OR MAA8/AT 2 112131330 Ellis!% R* PuvP.. __2-mf ta %8 l,
- 12il5/81 VS MOV _ set tzM _ _ _ _ _ _ __ _ ._ _ _.. rinED_SEntt._ 2 1t2131500 %8 -
NOV-VS-201 VALVES LEntS 81 AT 25 SCFR Ril'LKED SEAT 12/11/81 SV 2 1521%0309 %2 PtMP 2-M-P-104 PLMP LOCKED UP REPLACED RN EMPELLER WITR Cln ORE 12/18/81 AC VALVE SV-2551-B PERF09t DtP-CM-Ot t COvPLETE 2 1121st310 to
- 2 11009t%O0 855 -
liliflii Tt3 12/23/8t CC VJLV2 tV'3ti'io1C ikif F6f2 f# FlV fli3 CatPLEr8 2 11%151008 %D '., 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
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12/23/ik SV 'lfklik 56 -N-ib55~ ~l'till V' hlVi f5ST bid kkii$Thil' NUBBl[f55T55~ ~ ~ ~ 2 t102910$s 2 ti559555i tots ~ _.
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12/23/81 N VALVE MOV-N -203C 1555 PULL VALVE TEST MD REIRSTALL BURMLE TESTED 2 110291100 12i23/81 SV VALVE NOV-SV-2030 Evit. VALVE TEST ARD REIRSTMt. BUBBt2 TESTED 1035 n
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11/53/45 N ~ VALV2 ~ ~ ft0V6kb5A 2 11029110% 1035 u
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12i23/81 N Mill V4Lil f5St kh5' HEN 5fkil~ RMOVED BVMHN TEST GNASED REIRSTAL 2 11029t120 986 " VALVE NOV-N-205R ti/LL VALVE TEST ARD RKIRSTME, 12/23/81 M valve MV-N-205C RDt0VED BtfRBLE TESTED CREASED REIRST 2 11029tt3s 981 ., PULL VALVE TEST ARD REIRSTML REw VE ntlBMls TEST CREASED REIRSTAE.L 2 1t0291t%8 181 12123181 SV ' 'FALV2 ' NOV M 2D50 Pull VALV2 TEST AMI REIRSTAlt~ 6 12/23/81 51 MOV NOV-2ns1C M0VZn ntlRRLR TTETEM'CHAsih H1 RET 2 11hiiliis i12 " NOV-28s1C ARD at0V-28s1D E2M RM CASKET + PKK!8C 2 tit 0023%5 in3s ' j! : 2
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E2/02/91 SV NOV M V-N -2034 Dix ARD RK0W POR NEOF RE0ERETED NOV 2 1110%K502 5%9 12/01/81 SV NOV NOV-W-203R DIK eRKOM NRNEM RK0ENCTED NOV 2 1110%1103 569
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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 2 112080901 91 -
~ tilib/8i ~ 55 Q i &i ~ ~ jV-S5-20mA Vidt V5Lf, M0i d5CLR Vi&5 bPDktii ~
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2 1125908i5~~5~ 2
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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 -
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~~ ~~li/fi/it ST NOV NOV-28ssC EE.kW.~hidei,as Aw&SnD unsTS On NOV-18&C 3AT
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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 #@i,3di ibid #714fdi Rar 1sSTAtt/D =t=0 STEEt, art 2 108191=32 8 "
12/st/81 m wr wV-2591 # Ff,ACK N010# Pfff04 KPr REPL E8D N0f0R PINION RKT SAT 2 108191433 0
.l 12/sm/81 e NOV #0v-2590 REPtxt wNR Pin 10E Rav EsPixED Pinson Rsr SAT 2 10819tm3% so -
r l if/islii E Nor af 2590 Tiri-~ - ---' FiFdivs0 M5 biiv0r-r-2590 SAr 2 16isiO9c9 25 ; 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 _. , mPtsT MS 2 _ 1910ltfl2 19_ "
. 12/14/81 E NOV E 2592 MS 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, : ~> b
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12/21/e1 ns Rs soon PwS Nar0mED Pvs on mov-m-212oA SAT 3 .' 82/28tst Rs NOV m 21204 Ms 2 109010919 12/21/et As McV NMOMED NS OW MV-M-titon SAT 2 tiltinog _.121_._._.._ _ __. ' M 21200 PMS VALVE OPERATES SAT e 12/31181 M NOV inTEMEDIATE inDICAT100 2 112230ess ',: ' pi23/s2 N NOV NOV-N-1stC VALVE cuscuEn SAT 2 $o0210132 59 2-Cs-201 A uno cRounO x 12hilst CS mTOR 27-ss-20tB VALVE WILL MT CTCE2 POR PT 18.88 VALVE RBt0VED REAT CRCEES TAPG AEDSATPVT ANUsT80 BKK 02 UNITS _ _1.._$$\112$39._____39 3 12/2%f81 sS VALVE RE40VE HEAT TR King 90R VALVE 2 112221o45 ' _2-S!-9 RO fir 06 tar Pat /#D 2 1122s1650 t L2/2?l*l.. SE._ RT LM C#-21150 CN-2115D WILL NOT STAT OPEN ADJUSTED UN!Ts 06 SV-NS-to1C SAT tone r 12/26/81 CT ANUST UNITS OR 2Y-Ms-201C 2 100310131 ~ ~ ~ ~ 12fts/81 MS VALVE tv-Ms-totC PEM0 min 1905 OR BREAKERS
~
2 165ii6332 1069 ,, N010R 2-Rs-P-2.8 P45 tM NAF0mED PVS MP-f/itf ~ 60 ,. 12/21/81 RS 1995 '1 5 2 1122e19eo - NoiUR 2-RS-P-25 REPAIRED NO20R SAT 2 1122113o1 3 ~ ~ ~ ~ '
'- ' lihilil~ ' #s RD00VE N010E t-N-206D REPL K ED DVERLOAD ass 0tBLT e 12/21/91 N MOV 11/21/81 SE NOV NOV-2065C REPLKE OVERLOAD ASSFtRLT RrPtxEn REur 2 1122entos t 1122611%9 to : '
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12/29/81 Ms 50V $0v-MS-2028 no Pn0else rovr0 2 tito2o12s t , L 2-Rs-P-sn RESET VinRATron Picr OP CLEARS 0 Aum 1 w
.otiottez _ Rs instr VALVE PIT is DRT*Aum is zu 2 111111506 ts-DA-12tn CE2Akan Aum .......
ollb5les DA instr S11CN LS-DA-St98 VALVE PIT l'tPTT ALAm STILL 1R 29e66 ttio3/92 DA * . bh'_T NTAL .. er , 41
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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
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3.* , 48 HEALTH PHYSICS DECEMBER, 1981 l 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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