ML20041G165
| ML20041G165 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/14/1981 |
| From: | Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20041G159 | List: |
| References | |
| NUDOCS 8203190344 | |
| Download: ML20041G165 (46) | |
Text
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1 VIRGINIA ELETRIC AND POWER COMPANY SURRY POWER STATICN MOWHLY OPERL"'ING REPORT REPORP NO. 81-09 SEPTEMBER, 1981 f
3 APPKNED BY: IS (4^
STATICN ENAGER
./
e G
8203190344 811014 PDR ADOCK 05000280 R PDR
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CONTENTS -
Section Page Operating Data Report - Unit #1 1 Operating Data Report - Unit #2 2 Unit Shutdowns and Power Reductions - Unit #1 -
3 Unit Shutdowns and Power Reductions - Unit #2 4 Load Reductions Due to Environmental Restrictions - Unit #1 5 Load Reductions Due to Environmental Restrictions - Unit #2 6 Average Daily Unit Power Level - Unit #1 7 Average Daily Unit Power Level - Unit #2 8 Sununary 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 20 Tests and Experiments That Did Not Require NRC Approval 20 Other Changes, Tests and Experiments 21 Chemistry Report 22 Description of All Instances Where Thermal Discharge Limits Were Exceeded 23 Fuel Handling 24 Procedure Revisions That Changed the Operating Mode Described in the FSAR 27 Description of Periodic Tests Which Were Not Completed Within the Time Limits Specified in Technical Specifications 28 Inservice Inspection 29 Reportable Occurances Pertaining to Any Outage or Power Reductions 30 Maintenance of Saf ety Related Systems During Outage or Reduced Power Periods - Unit #1 - Mechanical Maintenance 31 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Mechanical Maintenance 34
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Section Pare Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Electrical Maintenance 36 Maintenance of Saf ety Related Systems During Outage or Reduced Power Periods - Unit #2 - Electrical Maintenance 38 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #1 - Instrument Maintenance 40 Maintenance of Safety Related Systems During Outage or Reduced Power Periods - Unit #2 - Instrument Maintenance 42 Health Physics Summary 44 Procedure Deviations reviewed by Station Nuclear Safety and Operating Com=ittee after Time Limits Specified in T. S. 45 o
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e UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-280 UNIT NAM E Surry Unit il DATE 10-05-81 REPORT MONTil Septatter, 1981 COMPLETEDsy Sue D. Dunn TELEPHONE (804) 357-3184 Ext. 477
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' 5 E 75b Ei'#" # 'k "I C'" 5' A C""' I
N"- D' ' ' i 2= 4 ii ; x Event uv q' Action to 55 5 ,# G u j i5 y Report # Present Recurrence 5
81-13 09-10-81 F 35.7 A 2 81-046/032-0 A failed regulator card in the 1AC power cabinet caused the Group 1 SB"A", CB"A" and CB"C" rods to be inoperable. 'Ihe reactor ms shutdown in accordance with T.S. 3.12.C.3.
'Ihe failed regulator card ms re- ,
placed and the control rods exercised y 4
before startup.
81-14 09-20-81 S 245.1 H 4 At 1855 the unit tripped on an " anti-motoring" signa 1 during power reduc-tion for a repair outage. 'lhe " anti-motoring" differential pressure sensors and transmitters were in-spected and no problem could be found.
i 1 2 3 4 l': Forced Reason: Method: Exhibit G . instructions 5: Scheduled A Equipment Failure (Explain) l Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entr> Sheets for 1.icensee C Refucting 3 Automatic Scram. Event Report (LI:R) File INURin -
D Regulatory Restriction 4 Other (Explain) 0161) li-Operator Trainmg & License Examination .
F Administrative 5 .
G Operational Error (Explain) Exhibit I- Same Source 19/77) Il-Other (E xplain) .
UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-281 UNIT NAME Surry Unit 12 -
DATE 10-05-81 REPORT MONTil Septether, 1981 COMPLETED BY nm D_ Nrm TELEPHONE (8041357-3184 Ext. 477
- E E No.
3E 3 j{E3 Licensee j s, h Cause & Correceive DJiC f $ [ vent ] Attism to F'
$E cii 5 if, = Report 8r MV o Preseni Recurrence
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81-12 09-03-81 S 169.9 H 3 'Ihe unit tripped on a Io-level on "A" S/G coincident with a Feed Flow / Steam Flow misnatch during shutdown for repair outage. 81-13 09-27-81 S 0 11 4 Ioad followed on orders of the system operator. 1. i I 2 3 4 F. Forced Reason: Method: Exhibit G Instructions 5: Scheduled A. Equipment Failure (Explain) l Manual for Preparation of Data B. Maintenance or Test 2 Manual Scram. Enity Sheets for Lkensee C-Refueling 3 Automatic Scram. Event Repori (LERI File (NllRI.G-D Regulatory Restriction 4 Other (Explain) 0161) E Operator Trainmg a License Examination F.Admimstrative 5 G Operational Error (Explain) Eshibit 1 Same Souru l'r/77 ) Il Other (Emplain)
LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO.1 MONTH: Serreber,1981 DATE TI!E HOURS LOAD, MW REDUCTIONS, If4 INH REASON Ncne during this reporting perio1. e e MONTHLY TOTAL 0
LOAD REDUCTIONS DUE TO ENVIRONMENTAL RESTRICTIONS UNIT NO. 2 MONTH: September, 1981 DATE TUE HOURS LOAD, W REDUCTIONS. W WH REASON i i None durin; this report 2ng ptriod. ! l I i I I
\
MONTHLY TOTAL 0
DOCFET 0 50-280 -
. Ui;IT SUREY I DATE 10-1-B1 COVPLETED EY Sue D. Dunn AVEi: AGE DAILY UliIT PCdER LEVEL VTiTt': SUTi"5El: 61 AVhn'A.7E DAILY ?O.:EE LEVEL AVERAGE W.ILY ?O,FK LEVEL L4Y ( s'C-llhY) DAY (VJE-NET) 1 738.7 16 736.9 2 736.7 17 731.5 3 730.6 18 735.6 4 732.5 19 737.6 5 735.3 20 303.5 6 737.2 21 0.0 7 736.4 22 0.0 -
a 735.5 23 0.0 9 734.6 24 0.0 10 329.8 25 0.0 11 0.0 26 0.0 12 370.3 27 0.0 13 565.8 28 0.0 14 G53.2 29 0,0 15 727.1 30 0.0 LAILi b!.IT P&JER LEVEL E0fN Ii;SliiUCT10d3 0:e TdIS FCils, LIST THE AYTRAGE DAILY Ui/IT EYMEli LEVEL Ill WE-i!ET FOR EACH DAY Il.' 22E JEEQi?!InG 4'0:iT4. THESE FIGURES WILL ST USED TO PLOT A GhAPH E05 EAC4 REP 0iG-1:iG VD;.73. i.GTE T4AT BY USING .VAXIVUW DEFEdDAHLE CAPACIZY F0E THE dET ELCCTEICAL h ATIicG OF THE Jiolk, Si!ERE YAY BE OCCASIC1/S WHEN THE DAILY AVERAGE PCKEn EXCEEDS 299 100 */e LI.iE (O!i THE RESTRICTCD FoiEn LEYEL LIlC). I!: SUCH CASES, THE AVCRACE DAILY 07.1T FNER DJTPUT SiE% S400LD BE FOOT;iOTED T2 EXFLAI2 T4C Af?AAEiiT AdOVALY.
i DOCKl7 i'0 50-281 UliIT SJHCY II DATE 10-1-81 r COVPLLTEC EY Sue D. Dunn
.11':aAGL PAIU U,;IT PGlRE LEVEL
.3C:: ST.iTLMEli 31 Al':KAGE DAIU PW'Ei; LEVER. AVEi: AGE DAIU PO,'EH LEVEL l>AY (ME-!!ET) DAY (WE-JET) 1 734.8 16 728.8 2 706.2 17 730.8 3 3.0 18 738.1 4 0.0 19 741.9 5 0.0 20 738.5 6 0.0 21 734.2 7 0.0 22 732.3 3 0.0 23 730.2 9 0.0 24 739.8 10 419.0 25 745.0 11 577.5 26 745.9 12 729.0 27 701.3 13 728.0 29 739.2 14 723.0 29 738.0 15 730.5 30 739.9 .
LA!!.T U:lli ICiEn LEY:L F0kV I!!STEUCTI3dS G ' .'l!)b FCHY, LIST Tdi. AVER /GE DAIU U!,'IT PO'FR LEVEL I!! *:*.'E-!lET FOE EACM TAY I:l INC 1.'LP0hTIaG *'Oi/TH. T4ESE FI:dNf3 lILL EL' USED T3 PLOT A GRAPH E0h EAC4 REPORT-l'11 :*0:.2'?. i.0TE T.9AT Bl U'I'IG AAXICUd DEPEilDASLC CAPACI17 FON :n tiET RLECT!i1 CAL in 411,;& OF TAL Ul;IT, 74E.%F: UAf sE CCCASIOdS WHE!l THE PAILY AVrnAGE PO,ER EACFEDS 1 H 1CC e/o Li E (01: T!K RTSTRI:TED Pik Ch Li' VEL LI:lL). I? SUCH CASES, THE AVEKA7r L AIT.Y bllIT PG.'Eh OUTPd: SdEET SdOULis bE P00T.10TED T2 EX?LAI3 TiiF APPAinUT At:0VfLt.
9 -
. SID91ARY OF OPERATING EXPERIENCI SEPITMER,1981 Listed belov in chronological sequence by unit is a summary of operating experiences for this month which required load reductions or resulted in sign-ificant non-load related incidents.
INIT 1 Septerber 1 - This reporting period begins with the unit at 100% power. Septerrber 10 - During PI-6 (Control Rod Freedm of Itwement Test) it was discovered that the Group 1 rods in Shutdown Bank "A" (SD"A") , Cmtrol Bank "A" (CB"A"), and Cmtrol Bank "C" (CB"C") would not acne as required. This occurred at 0700 and efforts began to detamine and correct problem. The problem ms not determined and corrected by 0859 and a shutdown was ccrrmenced in accordance with the requirements of T.S. 3.12.C.3. At 1030, Cmtrol Rod M-4 in CB "C" dropped fr a approximately 200 steps to approximately 75 steps. Power a s stabilized at 360 W e and <50% power following the turbine runback and the shutdown continued. The generator was off-the-line at 1157 the reactor was manually tripped at 1200 due to the inoperable control rods. Dose Equivalent Iodine spiked during the shutdown and a pyyam of frequent sartpling was started to track the buildup and reduction. At 1515 the regulator card was replaced in the 1AC power cabinet, which supplies power to the Group 1 rods in SD "A", CB "A" and CB "C", and all shutdown and control rods were exercised by bank to prove freedczn of movement. September 11 - Dose Equivalent Iodine was reduced tu <1.0 uci/mL and the reactor was taken critical at 2131. The generator was synenronized to the line at 2340. Power was increased to allow feedwater and rod control to be placed in autcznatic, then s+2hi149ed at 25% and 140 s e at 2400. September 12 - At 0001, a 3% per hour power increase was started. This rate of increase was utilized to reduce the buildup of Dose Equivalent Iodine. At 1625, with the unit at 70%
- ' power the rate of power increase was reduced to 1/2% per hour.
Septarnber 15 - Unit power reached 100% at 0900. c eber 20 - At 0059 camenced reducing power at 5% per hour for a unit outage to repair atwilin g feedwater system leaks inside the reactor containment. The reactor was tripped by an
" anti-motoring" turbine trip signal from approximately 15%
power at 1855. The Reactor Coolant System (E) t-wature and pressure ucro <350'F and 450 PSIG at 2331. September 21 - The RCS was at cold shutdcun condition at 0410. i
SUM 1ARY OF OPERATING EXPERIENCE (CCNIINUED) Septaber, 1981 i ( tNIT 1 September 30 - This twy.ai.ing period ends with the unit at cold shstdown for maintenance on various syst es. INIT 2 Septa ber 1 - This report 2ng period begins with the unit at 100% power. Septaber 2 - At 2102 a unit shutdown was ca menced for a repa2.r outage. The r W mn was stopped at 2343 at 49% power and 400mie due to a problem with No. 3 Turbine Governor Valve. The Electro Hydraulic Control fluid to No. 3 Governor Valve a s isolated allowing the valve to close and the shutdown i was continued. Septaber 3 - At 0045, the unit tripped frm 10(Mie en a Io-Invel in "A" S/G coincident with a Feed Flow / Steam Flow mismatch signal. The Reactor Coolant System was <3500F and 450 PSIG at 0620
- and reached cold shutdown conditicn at 1230.
September 8 - Started heatup for unit recovery at 0120. Reactor Coolant System tenperature >200 F at 0150. Reactor Coolant Syst s tenparature and pressure >350 F and 450 PSIG at 0645. 'Ihe RCS was at hot shutdown conditicn at 1642. September 10 - The reactor was critical at 0050 and the generator synchro-nized to the line at 0240. At 0728 unit power increase was stopped at 79% power and 565 Nie due to maintenance an "B" MFP. At 2053 the unit power was reduced to 74% and 515 Nie to place "B" MFP in service. "B" MPP was placed in service, but the seal ms still leaking'and was removed frm service for further maintenance. At 2140 unit power was returned to 78% and 565 Mie. September 11 - Startad power reducticn at 0035 to allow placing "B" MFP in service. Stopped power reducticn at 68% and (95 Mie at 0105. Placed "B" MFP in service at 0204 and a power increase was canenced 0237. Stopped power increase at 0400 at 88% and 670 Mie on orders of the System Operator. Started power increase at 0505 en instructicms of System Operator. The unit reached 100% power at 0645. Septa ber 16 - At 1905 power was reduced to 99% and 740 Mie to allow removing "A" ocndenser waterbox for cleaning. The "A" condenser waterbox was returned to service and power 2ncreased to 100% at 2350. I _ _ -
* -n_
SLM1ARY OF OPERAT7NG EXPERIENCE - . 'N) ' l S.Mamber, 1981, i d i i l 11HT 2 Ser a ber 27 - Cmmerced a power decrease at 0156 m orders of .the System Operator to load foHow. Stopped power reduction at 0335 , at 77% and 600 M k. Started power increase at 97JO en instructions of System Operator. The unit reached 100% power at 1000. , September 30 -
'1his reporting period ends with the unit at 100% power.
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- ' -' AMENIEEI;TS TO FACILITY LICEUSE OR TECHNICAL SPECIFICATIONS
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-- None during this reporting pericxi. -
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, TACILITY CHANCES REQUIRING ,
. NRC APPROVAL 1
_SEPTDER, 1981 1
!KIE DUREG THIS REPORTE PERIOD.
1 , l - 1! l; TACILITY CHANGES THAT
- DID NOT REQUIRE NRC APPROVAL
- 1 I
D/C 77-30 Well hter Flow-Hyh.FJnatic ard Hypochlorite Tanks 1&2 0 ; Tnis design change pemits analysis of the wall supply oystan as required by Virginia State Law to keep Surry Power j Station water permit active. SUPNARY T SAFETY ANAIXSIS
'Ihis modification has'no effect cm station operations since the system is a ncm-safety related item and runs autanatically.
D/C 78-28 Service Water Valve Replacement 1 i
'Ihis design change invo3ves replacing the existing 11/2" a x! 2" gate valves in the sezvice water system with bronze
- i ball valves.
\ StPNARY & SAFE'IY RRIXSIS This modification does not increase the probability of a occurance previously evaluated in the FSAR, crente a possibility for an ac:ident or malfunction different frczn those evaluated, or reduce the margin of safety previously i defined. D/C 79-26 Instrument Air Isolation-Main and Bypass Feedwater Regulator 1 valves This design change provides for segregatien of the main i and the bypass feedwater rsgulator valve controllers. If necessary, individual isolation would allow for partial system recovery while repairs are being made to the area of failure. StPNARY T SAFETI MAINSIS
' Itis nodification increases the versatility of the system by allowing the air controllers en either the main i or the bypass feedwater regulator valves to be repaired indivirh2a11y rather than having both sets of valves f
, inoperable. Therefore, there is a greater margin of safety.
l - . _ . . . , - . . _ _ _ . _ _ _ _ _ , - _ . _ . _ _ . - _ _ __ . _ . _ . . _.
FACILTW CI%!KES 'DET DID !Ur RDDUIPE NFC APPRA%L (continued) D/C 79-41 New Fuel Elevator Modification 1 This design change installed a key lock switch on the up button for the new fuel elevator to prevent raising the elevator withc:ut the key which is under the control of the Shift supervisor. SIM RRY T SAFrrY M & LYSIS This nodification provides an increased margin of safety during fuel handling operations. D/C 79-69 Auvi14mW Shutdown Panel / Main Centrol %ni Isolation Modification 1 This design change provides ccmplete el'ectrical isolation between circuits in the Main Ccatrol Board and the Auxiliary Shutdown Panel as reqaired by the NBC issued, Fire Protection Safety Evaluation Report, dated Septarnber 19, 1979. SLM RRY OF SAFrrY M & LYSIS
' Itis nodification does not create a safety problem, since this upgrades safety related circuits naarlarl for safe sautdown.
' Itis modification does not degrade the functicning of any other safety related systems.
D/C 80-52 Insert Check Valve Replacement Bearinos 1
' Itis design change provided a method for replacing teflon insert check valve bearings with stainless steel bearings.
The teflonbearingswere not q2alified for the estimated total , integrated radiation dose due to the valve locations. The
- overexposure of these valve bearings could have resulted in failure of the valve to operate r.wly.
SLM RRY OF SAFrfY R & LYSIS The Service Water System and Ccupcnent Cooling Water System capability and operaticn readiness is not affected. There are no safety inplicaticns created by this design change. 'Ihis nodification increases the reliability of the check valve to operate after an accident. D/C 80-55 Replace Mechanieal Seal-Charging Pump Cooling Water Pump 1&2
'1his design change replaced the mechanical seals en the Charging Punp Cooling Water Ptups secondary seals. The teflon secondary seals were not g ulified to the 40 year normal plus post-accident integrated rad.Miicn doses. The replacement material (ethylene propylens n bber) meets or exceeds the environnental requirements for the original tefico seals.
5 I . FACILITY CIRNGES TIRT DID NCTr REQUIRE NBC APPRCT/AL l (continued) D/C 80-55 SLTtRRY T SAPTTY ANALYSIS 1&2
'Ihis modification cbes not affect staticm operation or operaticm of the charging pump ocoling water pmp. It will
- increase the re14=h414ty of the safety-related peps under
- accident conditicms.
D/C 80-66 Replace "O" Rings-Charging Pep Seal Water Cooler 1&2 1
'Ihis design change replaces the NITRII2: "O" ring seals I in the charging pmp seal water coolers with VIITN seals.
i The VIITN maalm are qualified to the 40 year plus post accident radiatica dose levels. St2fRRY T SAITTY ANALYSIS
' Itis modification does not affect station operation or
- operation of the charging safety-injection peps. It will increase the reliability of the safety related peps under accident conditions.
D/C 80-72 2-Ten Manorail for }btor Generator Sets Switch Gear Roczn 1 iiervice Building El. 58'-6" Unit 1 l 'Ihe servicing of the M3 Sets ins handled by a portable hoist and support frame which becarrut unstable with the loads being lifted and therefore presented a safety hazard. 'Ihis design change erected a permanent nonorail above each unit 1 M.G. Set capable of safely supporting 2-Ton capacity hoist. SLPfRRY T SAFTTY ANALYSIS ! With the additicn of the monorails routine maintenance of 1 the M.G. Sets can be acccmplished in a safer method. This w:Lil minimize danger to staticn Wm usl and damage to aquignant. i D/C 80-84 Boron Recovery Spray Nozzles 1
'!his design change allows for the removal and maintenance of the Baron Recovery Spray Nozzle (lBR-IN-1B) .
St.Pf1ARY T SAITTY ANALYSIS
'Ihis modificaticn does not affect the operaticm of any safety-related =q"4= tant.
D/C 80-88 Isolaticm of Steam Driven A"vi14=7 Feedwater Turbine 1
'Ihis design change gives positive isolaticn required to prevent repair work at steaming conditicms. --, -r- - - - , ,,,--,----~~.,n, - - - . - - , - - . ~ -,- --...-,.,. -- - ---.--,- --
FACILITY CH74!CES 'nIAT DD ICT REUJIEE 10C APPR7E (continued) D/C 80-88 SLMGRY T SAFETY ANALYSIS This modification provides maintenance isolation capability for work on the steam supply system to the turbine driven AW pump. D/C 80-91 Voltage Indication for Serri-vital Buses 2 This design change installed a voltage indicator at the main control board fran semi-vital hises to provide the control roan operator with a continuous indication of sesni-vital bus voltage. The purpose was to meet the requirerrents of VEPCD Response to NRC Serial No. 485 Item 21. SGt&RY & SAFETY ANALYSIS This modificatico does not affect the operation of any safety-related equipnent. Therefore, there are no safety problems caused by this modification. D/C 80-92 Alternate Power to Gaitronics Systern 1&2 This design change provides an alternate power supply to GAITRONICS Public Address Systs to be available by manually transferring the power supplies. SGTRRY T SAFETY ANALYSIS This nodificaticn to the GAITR2nCS Syste as implemented by the use of locally mounted terminal boxes (with barrier strips) having a vital bus supply fran Unit 1 and Unit 2. This nodificaticn does not affect the operation of any safety-related equipnent. Iherefore, there are no safety problems caused by this nM4fication. D/C 80-94 Chance Power Supply Source to F-ll22 and F-2122 1&2 This design change separates the power sources of the charging flow loop and the loop fill header flow. With a loss of vital bus, the operators can verify the flow of water entering the cooling system. SONARY & SAFETY ANALYSIS
'ntis modificatico to the charging flow loop power source provides additional capability of flow indicaticn in the event of loss to Vital Bus 1-II or 1-III.
D/C 80-100 Renoving Centrol Function Interlock from " Hand" Position 2
'niis design change nodifies the starting circuitry so that the operator can start the contairrnent vacuum pump in
" Hand" Positicn in case of instrument failure. This will
+
FACILITY CHA?GES TEAT DID Nr REEUIRE 10C APP CVAL (contimed) D/C 80-100 Bertnino Centrol Functim Interlock frcun " Hand" Positim (continued) not override the SI actuaticn and will not defeat the purpose of control circuitry which prevents the ptmps frm running when the selector switch is cm " Auto" Position. SLM9JU T SAFETY ANMYSIS This ardif4r =ticm will not affect the staticm operatica and the operation of safety-related equiprent because the safety operation of the ptrps will not be changed or defeated. D/C B1-02 Part langth Control Rod Alam Dmwal 1&2 This design change disconnected "Part I.angth Rod Alert" alarm on the annunciator of each unit. The Part langth Control Rods were renoved under D/C 78-25. StM9@l T SAFETY ANALYSIS This modificaticm removes the Part Iangth Control Rod Alert, alarm and does not create any safety problems. D/C 81-04 Pressurizar Heater Control Switch Irv'4r =*4m for the Pull 2 to I.cck Positicm This design change provides control switch light indicatien when the Pressurizar Heater Switch is in the pull to lock positicm.
, StM9JE & SAFETY A?& LYSIS This nodificaticm does not affect staticm operatica or the operation (control circuitry) of the Pressurizer Heaters.
D/C 81-16 Station Telephcme Power Supply 1&2 The station telephone systan, was powered by a lighting panel that has tripped at times due'to the addition of spurious electrical loads. This design change establishes a M im tad power supply that will eliminate the possibility of bringing down the station telephcne systen due to the additicm of spurious electrical loads. SLM1ARY T SAFCY ANALYSIS This modification will enhance the staticm telepheme systen and does not effect any safety-related equipnent.
FACILTIT C2iANGES 'IMAT j,. .- DID FREQUIRE NBC APPRNAL (continued) D/C 81-20 Change Hydraulic Tubing of 6" and 12" Pathon Snubbers 1 j to Stainless Steel
'Ihis design change installed Stainless Steel hydraulic -
tubing, valves and reservoirs an 6" and 12" Pathan snubbers l in place of existing Carbon Steel tubing to increase corrosion resistance. StM9JE & SAFEIT ANALYSIS
'Ihis nodificatim provides additional seimic protection i for the Reactor Coolant System. It does not affect the station operations or the operation of safety-related equipnent.
D/C 81-23 Control Rxan Smoke Denpers 1&2 l 'Ihis design change replaced the covers for the louvers in tM security doors between the main control rom and control room annex with covers operable frczn inside the control room. SGt907 T SAFEM ANALYSIS
'Ihis nodification as added in response to NRC Fire Protecticm Safety Evaluation Report (09-19-79). 'the new covers will more effectively meet requirements.
1 i D/C 81-27 Voltage Indication for Vital ==== 1&2 This design change ensures that the voltage indicator on the main control board will provide a ocntinuous indication of vital bus voltage. This nonitoring as accuplished by tapping the vital bus through a 6-anp, in-line fuse, in lieu of the circuit breaker that u s being used. StM9JU T SAFMY ANAIXSIS .
'Ihis modification does not affect the operation of any safety-related equipnent. 'Iberefore, there are no safety problems caused by this #4 f 4mticm.
D/C 81-101 Replace Impellers in Radiation Mcnitoring Sample Pumps 1
'Ihis design change replaces the existing inpellers with larger inpellers to provide the required TIfi. The 'IDH ms increased due to D/C 80-56.
SLM9JE & SAFEW ANALYSIS
'Ihis modificatim does not affect station operations or operations of the radiation monitoring sanple pianps. It does provide the increased '1TEI requirements.
F%CILITY OWEES 'IHAT . DID NCrr REQUIRE hT APPKNAL l l (continued) D/C 81-106 Outside Recircualtion Spray Ptrp Support MM4 *ica*4m 1 The contairunent outside wall was found cracked in the area adjacent to one baseplate of the support for the Containment Outside Recirculaticn Spray Purrp 1-RS-P-2A. It was determined that the crack extended in the direction of the w M .a t of the baseplate anchor bolt. The area of damage was repaired and a new baseplate was tied into the existing plate. SumARY T SAFTrl ANALYIS This modification does not affect the operation of any safety-related equipnent or structures. u ,
TESTS AND EXPERIMEMS RECUIRING
... NBC APPROVAL SEPTINEER,1981 None during this re;n Q period.
TESTS AND EXPERIMEMS DRT DID NCTT REQUIRE NRC APPROVAL SEPIDEER,1981 Special Test No. Unit Title Capleted ST-130 1 Racirculatico Spray Heat 09-23-81 Exchanger service mtar Foreign Material Evaluation ST-52 1,2 BCS Flow Maarmenent Data 08-21-81 ST-119 1 Condensate Polisher Perfor- 08-21-81 mance Test t i l l l
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!KtE DURING THIS REPORITU PERICE.
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CHEMISTRY REPon! sent eher , Ic g T. S. 6. 6. 3.J PRI.%RY COOLANT UNIT NO. 1 (A) UNIT NO. 2 (B) ANALYSIS MAXIMUM MINIMUM AVERAGE MAXIMUM MINIMUM AVERAGE Gross Radioact., UCi/mi -
~1 2.2 +0 2.54 1.05 E+0 3.11 269
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Suspended Solids, ppm 0.1 0.1 0.1 ri .1 0.1 0.1 E-1 3,34 E-1 E-1 E-2 6.74 E-2 Gross Tritium, uCi/ml 2.83 ~1 1.56 1.03 1.55 lodine-131, uC1/ml 5.34 E-1
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2.77 2.84 4.72 1.32 2.17 I-131/I-133 a>
.6468 .3690 .5156 2.0960 .3907 .9163 M/ drogen, ec/kg 47,4 3,g (D) 28.8 48.7 27.3 39.3 Lithium, ppm 1.92 1.50 1.69 1.10 .31 (F) .76 Boron-10, ppm + 392.6 170.1 248.2 434.5 22.2 113.1 0xygen-16, ppm urated .000 .dOO 2.3 (B) .000 .000 Chloride, ppm < .05 <.05 <.05 <.05 <.05 <.05
, pH 0 25*C 6.81 5.96 6.40 7.63 5.68 6.66 4 l Boron-10 = Total Boron x 0.196 NON-RADIOACTIVE CHEMICAL (G) RELEASES, POUNDS T. S . 4.13. A. 6, Phosphate 0 Boron 567 i Sulfate - Chromate .63 50:: NaOH - Chlorine O Remarks: (A) Unit runback 9-10 1032 hrs. Unit off line 1200 hrs. Rx Critical 9-11 20lM k n - Unit off line 9-20-81 for maintenance. (B) Unit off line for maintenance 9-2 Rx critical 9-10-81 (C) High valves due to suspected fuel f ailure. Valwes high during start-up and shut-down. (D) Reflects degassing for outage. (E) High valves due to suspected pin-hole fuel d2fects. (F) Due to dilution for Unit start-up. Added 1040g of Li oH. 7 (G) These levels of l chemicals should present no major adverse environmental impact.
DESCRIPTION OF ALL INSTANCES k'HERE - , THEICIAL DISCllARGE Ll!!1TS WERE EACEEDED , September, 1981 Due to the impairment of the ciIt:ulatirx3 Water system on the following days, tha thermal discharge limits were exceeded as noted. Septaber 1, 1981 - Exceeded 15.0 AT across station
- September 2, 1981 -
Exceeded 15.0 AT across station
- September 13, 1981 -
Exceeded 15.0 AT across station
- September 14, 1981 -
Exceeded 15.0 AT across station
- Septaber 15, 1981 -
N aadad 15.0 AT across station
- Septemoer 16, 1981 -
Exceeded 17.5 AT across station Septaber 17, 1981 - Exca= dad 17.5 AT across station
- Septeber 18, 1981 -
Exceeded 15.0 AT across station
- Septanber 19, 1981 -
Excaadad 15.0 AT across station Septenber 20, 1981 - Excaaaad 15.0 AT across station *
- Indicates dates where statico AT was less than 15.0 F across station for same time during the day.
The AT excursions were allowable under 'I%chnical Specification 4.14.B.2. There were no reported instances of adverse envis.sual impact. The tenperature change at the station discharge exceeded 3 F per hour on Septanber 3,1981, when Unit 2 tripped during a normal shutdown for a npair outage. The temperature change at the staticn discharge exceeded 3 F per hour cm September 10, 1981, during a shutdown of Unit 1 to mmt regairements of T.S. 3.12.C.3. These events were allowable in accordance with Technical Specification 4.14. 'Ihere were no reported instances of adverse environmental inpact.
FUEL HM;DLIl:G ; September, 1981 Ncrie during this reporting period.
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September, 1981 DATE NO. OF ANSI NO. NEW OR SPENT FUEL ASSEMBLIES PER SHIPMENT INITIAL ENRICle!ENT $91PPING CASl; ACTIVITY LEVE1 SHIPPED / RECEIVED None durinc this remr+ 4 m r=-4 M i . O m l l l t . _ _ _ __ _ _ _ _ . _ _ _ _ _ .-- _ . . - - _. _ ._ -_.__. . . . . . _ - . . - - -- _
. 26-12 TIT 2
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S*F h , 1981 DATE NO. OF ANSI NO. NEk' OR SPE!."I FUEL SHIPPED / RECEIVED ASSEMELIES PER SHIPMENT INITIAL ENRICID'.ENT SHIPPING CASK ACTIVITY LEVE1' I l None durdng this repor* h period. i l l l ( l i I i
PROCEDURE REVISIONS THAT CHANGED THE - OPERATING !! ODE DESCRIBED IN THE FSAR - SEPTENBER, 1981
!KIE DURI!G THIS REPORrrG PERIOD.
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- DESCRIPTION OF PERIODIC TESTS WICH 17 EPI NOT COMPLETED WITHIN THE TDiE LIMITS SPECIFIED I!; TECIC!ICAL SPECITICATIONS SEPTINEER, 1981 L"iIT PT-38.ll Chemistry Sarpling - Primary Coolant Cnx! Analysis - was 1 scheduled for 09-10-81 and was done on 09-21-81, which put the PT out of the grace Period by 4 days. Chenistry started taking sanples an 09-11-81 and could not perform analysis of the sample due to the high level of radioactivity.
Subsequent sanples were taken and the sane problan was encountered. Third set of samples were taken on 09-18-81, and the sanple was able to be analyzed. 'Ihe results were obtained and P::' was then filled out on 09-21-81. Station Deviaticn rep. # Sl-81-305 was subnittad. l l
INSERVICE INSPECTION SEPIE CIR, 1981 No Inservice W.icn as perforned for Unit 1 or thit 2.
~30- ,
. REPOR7ABLE OCCURRENCES PEFTAINING TO
. Ahi OUTAGE OR PO'w'ER REDUCTIONS N , 1991 ME NG THIS REPORTING PERIOD.
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RTD CABLE .990GTS AT kTD 09/1s/et CC non! TOR Rt.CC-in s EG18lOnss as i Al.ADt SFTivlRT KKADING E99 Pl!T 1R RN SRTivlRTS e'* 09/1s/8i N Pt0tr S SM19.on1% 190 8' RESTAl.1/D R. Tat cal.lBRATED CMCK t 109131351 26 ostsolet arS ERSTit FUi%s 1-N-r-SM ~tkM:blitRR ~ ' KErl. WAlvh ACE 1199f' DESCRANCE "'* '~ ~ ~~" RWLAC!b ll6AhnfHMb CAllMRAttb N
, os/solnt Rs M0nlTOR CC-tos AIAnt SATiv!RT CREArrn PUT RW SATivlRTS IN WalTORS 1 t ostt>osan in) i Orty TOTAL. - ~~ '
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9 1 I SEFIDGER, 1981 Maintenance of Safety Related Systems Durina Outage or Reduced Power Periods UNIT #2 Instrument Maintenance
, MAIITIENANCE OF SAFrrY REIATED SYSTDE DURING CUTAGE OR REDUCED POWER PERIODS -
LEIT #2 l INSTRUMENT MAINTDUWCE i SEPrDGER,1981 NCNE DURING THIS REPORTING PERICD. 1 i I l l I
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, HEALTH PHYSICS
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. Septenber, 1981 There was no single release of radioactivity or radiation exposure r;<cifically associated with an outage that accounted for more than 10% of the allowable annual values in 107 R20.
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4 4. . 6 PROCEDURE DEVIATIONS REVIEUED BY STATIOU !:UCLEAR '
- SAFETY AND OPERATING CO:D!ITTEE AFTER TI!!E LI:!ITS
- SPECIFIED IU TEC1:NICAL SPECIFICATI0 :S September, 1981 Date SNSOC Procedure No. Unit Title Date Deviated Revieweci OP-2.2 2 Unit Power Operation-Turbine 09-03-81 09-24-81 i
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