ML20213F735
| ML20213F735 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 11/10/1986 |
| From: | Muffett J WISCONSIN PUBLIC SERVICE CORP. |
| To: | |
| Shared Package | |
| ML20213F733 | List: |
| References | |
| FOIA-86-724 NUDOCS 8611170079 | |
| Download: ML20213F735 (51) | |
Text
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.F-18. i.694E-01 i.230E+00 2.004E-01 NA-24. 0.000E+00 4.670E+00 0.000E+00 l AR-41. i.425E+00 i.750E+00 2.494E+00 CR-Si. 0.000E+00 3.260E-02 0.000E+00 r* N- 5 4. 0.000E+00 8.360E-Oi 0.000E+00
) r4N-56. 0.000E+00 2.520E+00 0.000E+00 FE-59. O.000E+00 i.305E+00 0.000E+00 C D -5'7 . 0.000E&OO i.320E-Oi 0.000E+00
) CO-58. 4.769E-03 8.530E-Oi 4.068E-03 CD-60. 0.000E+00 2.601E+00 0.000E400 f.N-65. 0.000E400 5.900E-Oi 0.000E+00
) BR-84. 0.000E+00 3.032E+00 0.000E+00 K R- 05. 0.000E+00 2.530E-Oi O.000E400 V R - 8 5 fi . 0.000E+00 4.120E-Oi 0.000E+00 l
) kR-M7. 0.000E+00 2.116E400 0.000E+00 KR-33. 0.000E&OO 2 . 2'79 E + 00 0.000E+00 l i&OU . 0.000E+00 2.697E+00 0.000E4 00
; l' '3 ? . 0.000E+00 2.,582E+00 0.000E+00 CR-09. 0.000E400 5.830E-01 0.000E+00 S R '7 0 . 0.000E+00 i.960E-01 0.000E+09 SR-94 0.000E400 i.331E+00 0.000E+00 S R '7 2 . 0.000E+00 i.539E+00 0.000E+00 Y -Y 0 ri . 0.000E+00 6.8iOE-01 0.000E+00 Y -- 9 0 . 0.000E+00 9 . 350 E --01 0.000E+00 Y - 91 ti . 0.000E+00 5.570E-Oi 0.000E+00 Y-91. 0.000E+00 6.060E-01 0.000E+00 Y-Y2. 0.000E+00 i . 6(/7E+00 0.000E+00 2R-95. 0.000E+00 8.51OE-01 0.000E+00 flD-vb. 0.000E+00 7.640E-01 0.000E4OG MU-97. 0.000E+00 i.i30E+00 0.000E+00 hu-99. 0.000E400 5 . 44 0E--01 0.000E+00 W liOM. ;0.000E+00 2.001E+00 0.000 8-00 SN-113. d0.000E+00 3.804E-01 0.000E+00 S 't- 12 4. 0.000E+00 2.232E+00 0.000E+00 SP-125. y 0.000E+00 2.601E400 0.000E+00 0.000E+00 1E-132.
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,CS-138. 3.31OE-03 3.554E+00 1.176E-02
> D A -- 13 Y . 0.000E&OO Y . 350E- 01 0.000L&OO VA-140. O.000E+00 4.3GOE-01 0.00nE&O9 LA-i40. 0.000E400 ?.U42E+00 0.000E+00 CE-144. 0.000E&OO 1.1iOE-Oi 0.000E+00 l W~iO7. 0.000E400 ~7.650E-Oi 0.000E+m' w w w w * * *
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- x ) x v TOTAL ACT]VITY(UC1) 1.602E+00 JSOTOPIC EPAi: T 2.71UE+00 AM
'f 9/Blo8b nuvynsv+uvuv+uyvunvuvxunvuvuuuuuxuxvvuxyuvvun+xvynxxxxnxunuvvvvvunuxu . : 5S.7 EBAR= 1.696E+00 E g x x y n x+ v u n x v v y y v u u u v u v u u n y v w x u v u n x x v e u v y x v vy u v u u v v u + n y v ynx x u v v y u v y y y u: s C
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- c. MAXIMUM COOLANT ACTIVITY Specification The total specific activity of the reactor coolant due to nuclides with halflives of more than 30 minutes, excluding tritium, shall not exceed A = 91 pCi whenever the reactor is critical or the average temperature is CC E
greater than 500 F (E is the average sum of the beta and gamma energies in Mev per disintegration). Basis This specification is based on the evaluation of the consequences of a postulated rupture of a steam generator tube when the maximum activity in the reactor coolant is at the allowable limit. The potential release of activity to the atmosphere has been evaluated to insure that the public is protected. Rupture of a steam generator tube would allow reactor coolant activity to enter the secondary system. The major portion of this activity is noble gases (1) which would be released to the atmosphere from the air ejector or a relief valve. Activity could continue to be released until the operator could reduce the Reactor Coolant System pressure below the set point of the secondary relief valves and could isolate the faulty steam generator. The worst credible set of circumstances is considered to be a double-ended break of a single tube, followed by isolation of the faulty steam generator by the operator within one-half hour after the event. During this period, 120,000 lbs of reactor coolant are discharged into the steam generator.(1) The limiting off-site dose is the whole-body dose resulting from immersion in the cloud containing the released activity. Radiation would include both gamma and beta radiation. The gamma dose is dependent on the finite size and configuration of the cloud. However, for purposes of analysis, the simple model of a semi-infinite cloud, which gives an upper limit to the potential gamma dose, has been used. The semi-infinite cloud model is TS 3.1-9
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. the occurrence. The highest concentration of argon-41 measured was about 48 MPC for a restricted area in the waste gas compressor room. A total of seven individuals were assigned MPC- ur exposures ranging from about 0.6 to 33.2 MPC-hours. Although ar If as an energetic gamma (about 1.29 Mev) no exposures were detectabl ort cket dosimeters worn by the individuals.
No violations or deviations were identified during inspector review of the incident. Since the occurrence, the licensee has identified and repaired several valve / valve packing leaks in the waste gas systpm and the waste gas ph y&h 4. c& y. analyzer.3 Follow ng repair. fg ea,ks, the licensee is continuing to evaluate the feasibility of purging the VCT cover gas to a WGDT for decay of argon I followed by release of remaining argon 0. This is being j considered to preclude incidents such as the ESF actuation (reported to the NRC) which occurred on October 6, from a momentary off gas spike while performing routine type maintenance. The off gas spike occurred during fill and vent operations to get air out of the system after changing seal water filter on reactor coolant pump seals. A- E/% 2ku Y J'% $ 7gu yQoL~ bVOT[ & q 4!I $ JWf & &y"rv/ )g-WGbT f $49 y .& w/ y#"f.dr - ndM93~4 W ~%I
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(WL so sorfm,g.o t) The inspector met with licensee representatives (denoted in Section 1) at the conclusion of the inspection on October 3, 1986. The inspector summarized the scope and findings of the inspection. The inspector also g, Open Items ! Open items are matters which have been discussed with the licensee, which and which iqvolve some action will be reviewed further t "e '=pr'r, k4 pen item disclosed.durina on the part of the NRC or licensee or both. the inspection 4 discussed in Section 2. A l l .. -
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ATTAC MENT TO LETTER FROM D. C. HINTZ DATED SEPTEMBER 27, 1986 I. DESCRIPTION OF EVENT During normal plant operations at 100% power, at 1538 ho.urs on September 26, 1986, the radiation monitor for the condenser air ejector alarmed in the control room. Personnel were immediately dispatched to investigate. The radiation monitor for the reactor coolant purification system alarmed at 1634 hours. The ongoing investigation revealed that the radiation was the result of the decay of Argon-41 Entry of the argon into the reactor coolant system caused it to circulate through the nuclear reactor and become radioactive. The source of the argon was identified as two of six gas
- bottles lined up to provide cover gas to the reactor coolant system.
These two bottles were determined to contain 95% argon instead of pure hydrogen. These bottles were connected to the system earlier in the l morning as part of a routine procedure. The two bottles in question were j among a shipment of 12 specified to contain pure hydrogen. The fittings and color of the two gas bottles containing argon were identical to the remaining 10 hydrogen bottles. The normal procedure to reduce radioactivity in the reactor coolant system l is to transfer the radioactive cover gas to the gas decay holding tanks located in the auxiliary building. During this transfer, which occurred at approximately 1740 hours, some of the gas escaped into the auxiliary building which is vented to the atmosphere through filters and a monitored stack. B/T
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SEP-29 '06 00:00 T- WPSC414/433-1297 88162-03 4 3 i 5 The radiation monitor in the auxiliary butiding vent stack detected the I increased radioactivity, and although the gas transfer had been terminated, the monitor reading reached the threshold at which the plant emergency procedures required declaration of an Unusual Event at 1810 hours. Offsite notifications of state and local authorities were completed within 15 minutes as required by procedure. The combination of terminating the gas transfer, thus isolating the source, and the natural decay of Argon-41, resulted in the monitor reading returning to below the Unusual Event level. The Unusual Event was closed out at 0333 hours on September 27, 1986. II. CAUSE OF EVENT The root causes of the improper addition of argon to the reactor coolant system include: a) The bottle gas vendor supplied an argon-hydrogen mixture instead of pure hydrogen as specified on the shipping list. b) Plant personnel did not detect the discrepancy in the gas bottle 1 I labeling during the receipt inspection nor at the time of installation. c) The bottles containing the argon-hydrogen mixture are of the same color , as the bottles containing pure hydrogen. In addition, the labeling on l these bottles is relatively small. l The root cause of the unexpected increase in radiation levels in the auxiliary building was leakage of radioactive argon from the waste gas system. The leakage pathway from the waste gas system has not been identified at this time and is still being reviewed. s
L T .. WPSC414/433P1297 SEP-29 '86 00:10 T- WPSC414/433-1297 N162-05
- i 4
b IV. CORRECTIVE ACTIONS Innediate corrective actions taken included:
- a. Identifying, removing, and segregating the argon source from the hydrogen supply to the reactor coolant system.
- b. An inspection of gas bottles in the storage area was completed to ensure no similar problems existed.
- c. Contacts with the hydrogen gas supplier were made to determine the cause of the shipment discrepancy. This activity is still in progress.
- d. Transfer of radioactive argon to the waste gas system from the ,
, reactor coolant system was terminated. This stopped the release of radioactive gas from the reactor coolant system.
- e. The auxiliary building was ventilated to remove the airborne radioactive argon. This allowed personnel access in accordance with normal control practices, at approximately noon on September 27, 1986.
Long term corrective actions are being formulated and evaluated. l t i
.- ._. WPSC414/433P1297 ..
SEP-29 '86 SEie09 T- LPSC414/433-1297 #162-04 4 III. ANALYSIS OF EVENT The total amount of radioactive argon released from the plant through the auxiliary building ventilation system was determined to be a small fraction of the Kewaunee Plant operating license limit. Site teams were dispatched to obtain samples within the site boundary for analysis and confirmed that there was no threat to the health and safety of the public. Any exposure to an individual at the site boundary would have been significantly be ~. 4 the federal limit. The remaining radioactive Argon-41 in the reactor coolant system is naturally decaying to the stable (non-radioactive) isotope Potassium-41. The potassium is being removed from the reactor coolant by the reactor coolant purification system, i Full power operation continues as reactor safety was not affected by this event. i _ -.y ~ .-
l. t 09/20/06 DSILY REPORT-RIII ( tct i FACILITT/ LICENSEE
- PERRfUNITI/CLEVELANDELECTRICILLUMINATINGCOMhANY LOTIFICAT!0hs SBh!OR RESIDENT Dh5PECTOR SUBJECT REACTOR WATER CLEANUP SYSTEM !$0LATION l EV8his Oh.SEPTEW9ER 29, 1996, AT APPRONIMATELY 2'847 A.M. A REACTOR WATER CLEANUP (RWCU) SYSTEM ISOLATION OCCURRED ON MISP DIFFERENTIAL FLOW. JUST PRICR TO THE OCCURRENCE, OPERATING PERSONNEL HAD ESTABLISHED RwCU BL0wD0wN FLOW TO THE MADN.COhDENSER IN ORDER TO CONTRCL REACTOR WATER LEVEL DURING PLANT HEATUP. ACCORDING TO OPERATING PERSONNEL. THE MISM i OIFFEEBhTIAL FLou ALARM WHICH Sf6hlFIES INITIATION OF THE 45-SECOND TIME DELAY IN THE ISOLATION LOGIC WAS NOT RECE!vEO
) P250D DC THE !$0LATION. FOLLOW 3h6 THE OCCURRENCE. THE ISOLATION WAS RESET ANO THE RwCU SYSTEM WAS RETURNED TO SERVICE
' LICENSEE DNVESTI64 TION IS ONGOING.
CESIOhAL ACTIONI FOLLOWUP 8Y THE HESIDENT INSPECTION STAFF IN ACCORDANCE WITH MC 2515. s FACILITY /LICENSEEI E AR PLANT 4n1SCONSIALELS.LIC SERVICE
. NOTIFIC8TI0h LICENSEE 50.72 NOTIFICATION l
l SU2 JECT: DNADVERTENT RELEASE OF AR6ON 6AS I EV8NT: Oh 5EPTEMBER 26. 1986. AT 6:10 P.M. CDT AN UNUSUALTHE EVENT WAS DECLARED WHEN APPROXIMATELY 2 CURIts DF ARGON AI ARGON 845 WAS INTRODUCED INTO THE PRIMARY COOLANT SYSTEM l CERE RELEASED THRCUGH THE AUXILEARY BUILDING VENT STACK.
' FCOM TWC GAS BOTTLES USED IN THE WOLUME CONTROL SYSTEM TO PROVIDE COVER GAS IN THE VOLUME CONTROL TANK (VCTI. TMESE TWO l 8OTTLES WERE DETERMINED TO CONTAlk 955 ARGON INSTEAD OF PURE HYDROGEN. WHILE PUR6ING THE VCT TO THE SAS DECAY HOLDING TANRSeiSOME OF THE ARSON GAS LEAMED INTO THE AUXILIARY BUILDING AND WAS VENTED TO THE ATMOSPHERE THROUGH FILTERS AMO A ] NONITORED STACK. ALL SYSTEMS FOR DETECTION OF RADI0 ACTIVITY OPERATED AS DESIGNED. NO PERSONNEL CONTAMINATION OR ! INJU2I55 0CCURRED. THE TOTAL AM0LNT OF RADIOACTIVE ARGON RELEASED FROM THE PLANT27, ON SEPTEMBER WAS DETERMINED 1986 TO BE LESS THAN 19 0F AND THE PLANT
, THE TE0eh! CAL SPECIFICATIONS. DhE UNUSUAL EVENT WAS TERMINATED AT 3833 4.M.
- CONT) hut $ TO OPERATE AT FULL POWER.
, EEGIchAL ACTION: A RESIDENT INSPECTOR WAS DISPATCHED TO THE SITE IMMEDIATELY FOLLOWING THE DECLARATION OF THE UNUSUAL j EVBNT RkD MONITORED LICENSEE ACTIb! TIES UNTIL THE PLANT RETURNED TO NORMAL. 1 FACILIT1/ LICENSEE NOTIFICATION: I
SUBJECT:
MEETINS $ EVBhTI PR. C. J. PAPERIELLO WILL BE ATTENDING THE B&W OWNERS GROUP (BWO61 IN HEADOUARTERS SEPTEM8ER 29 ANO 30. 1 CEGIch4L ACTION: INFORMATION ONLY i i e
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o SEC0NDARY K EY SELEC1 I ON RETRIEVE TRAt4SACTION: ADD /llPDATE DOSE OPTION: TRX 62D KEY: 860900958604980000000000 SELECTION: ADFEi31 ENTER OPTION:R TO RETURN TO FIRST SCREEN TIME TIME GAMMA NEUTROil UPDATE DATE Y-M-D IN OUT DOSE DOSE INDICATOR 31 860924 1610 1745 0 0 D 32 860924 2035 2115 0 0 D 33 860925 1645 1740 0 0 D 34 860925 2000 2110 0 0 D,
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- ZM , Ads' S E C 0 IJ DARY KEY S E t. E CT I ON RElRIEVE TRANSACTION: ADD / UPDATE DOSF OPTION: T R'X 62D l EY 860900758605000000000000 SELECTION: *** ENTER A SELECTION NUtil:ER FROli THIS SCREEN *** TIME GAMMA NEUTRON UPDATE TIME DOSE DOSE INDICATOR DATE Y-H-D IN OUT 1429 1512 O O D __ 860912 i seF' w3.Js64977 th !R4BDTJ 2320 ~; NUEM ; 32 MT- __rD_ __ s
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. REsc_RER liiPUT DA'IA ISOTOPE C0tiCEiil P ATIOtl AR-41 2.OOOOE-06 UCI/CC TIME 336.00 MINUTES 0.0 tiREil DOSE TO THYPOID IS 0.0 tiREti DOSE TO BONE IS MREti 0.0 DOSE TO LIVER IS 0.0 MREri DOSE TO KIDNEY IS MREM 0.0 DOSE TO GI-LLI IS 0.0 MREM (EXCLUDING NOBLE r.ASES) ,
DOSE TO LUNG IS MREM (FRoli N0 file G ASES ONL Y )
+ 0.i1 46.63 MREti DOSE TO SKIN IS 1i.29 MREti DOSE TD (JHOLE DODY 1F STAY TliiE Ii> tilliUi ES 400 jihE n 50 Hi:Eh 100 tiREH 200 MREli ORGAN MREM PER 1000 MREti 2000 tihi i.
tillJUT E 500 tiREti THYROIb O.0 DVEP i YEAR doi 1E 6.0 OVER i YEAR LIVER O,O OVER i YEAR KIDNEY 0,6 OVEf? i YEAR GI-LLI O.0 OVER 1 YEAR LUlJG O.0 OVER i YEAR (WITHOUT N0i:LE GASES) 620340.0 12406c o.C O.0003 155087.0 310174.0 LUfJG OVER i YEAR (TNLLUDIHG NOBl.E GASES) 404i.8 80f 3 . c-O.0495 1010.5 2020.9 SFIN 1Oi04.5 20267.O 404i8.i 59 4 9 . ei iii'9c 6 i487.4 2974.9 Ull0LE DODY 0.0336 14874.4 29740.9 59497.8 DODY BURDEtiS (IN NCI ABOVE, IN PCT tiPliB liLLOU 6 HR 12 HR i DAi
- 90 MIN 3 HR ISOTOPE AT EYTT 45 tiIN 8 DAY 16 DAY 32 DM I
2 DAY 4 DAY
. %3AusorJ INPUT DATA 1SOTOPE CONCEtJTR Al 10i1 AR- 41 2.0000E-06 UCI/CC TItiE i291.00 mil 4UT ES 0.0 fire M DOSE TO THYROID IS 0.0 tik Eti DOSE TO D0tJE IS MRFM 0.0 DOSE TO LIVER IS 0.0 MREtt DOSE TO KIDNEY IS MREM DOSE TO CI-LLI 35 0.0 0.0 MREti (EXCLUDING tiDi4LE G ASE S ) DOSE TO LUi4G IS MREti (FR0ti NOBLE GASES OllLY) 4 0.42 63.88 MREM DOSE TO SKIN 15 MFEM DDSE TO a E It0DY IS 43.40 STAY LIME IfJ MIi1UTES 200 Mi;Eii 404 tiRF t. MREM PER 50 MREli 100 MhEh ORGAN 1000 MWEM 2000 tiREM til NUT E 500 liREti THYRDID 00 OVER 1 YEAR IsoliE 6.0 OVER i YEAR LIVER 0.0 OVER i YEAR MIDtJEY 0.0 OVER i YEAR GI-LLI O.0 GVER 1 YEAR LUilG ;0. OVEF 1 YEAR (WITHOUT NOBLE GASES) 620348.0 i?4069 6 . 0. ,0 :' 15PO8/.0 310174.6 l Uin, OVER i YEAR (liJEi.UDijJG 110BLE G ASES) 4041.G ROU 1010.5 ?O20.9 SK]lJ 0.0495 2020V.0 404id.1 10104.5 5949.8 i i 3 C. 1487.4 2974.9 WHOL.E 1.ODY 0.0336 14074.4 2774J.9 59497.8 BODY BURDENS (IN NC1 ABOVE. ]N PCT MPbB FELGW 12 HR i 90 ti1N 3 HR 6 HR ISOTOPE AT EYIT 45 MIN 16 bM 32 DAi 2 DAY 4 DAY b DAY
r-p b8C.h INPUT DATA ISOTOPE CONCEtJ1 R AT10iJ
. AR-41 2.OOOOE-06 llc 1/CC TIliE 1249.00 ti1NUTES DOSE TO THYROID IS 0.0 liREM DOSE TO PONE IS 0.0 MREti DOSE TO LIVER IS 0.0 HREM DOSE TO EIDi4EY IS 0.O MREti DOSE TO GI-LLI IS 0.0 MREM DOSE T O Lui4G IS 0.0 MREM (EXCLUDING I40DLE GASES)
+ 0.46 HREM (FROM (J0e.E GASES OiJLY)
DOSE TO SKIlJ IS 61.80 MREM
OSE TO UHOLE kODY IS 41.98 MREM STAY TIME IN MINUTES DRGAN MREM PER 50 MREN 100 MREM 200 MREli 400 MREM MINUTE 500 MREtt i000 MREM 2000 MRE.li THYROID O.0 OVER i YEAR B G'4E O.0 OVER i YEAR LIVER O.0 UVEi' i YEnR EIDNEY 0.O OVER i YLAR
.GT-LLI O.0 OVER 1 YEAR LUNG O.0 OVER i YEAR (WIlHOUT NDBLE GASES)
LUNG O.0003 155087.0 310i74.0 620348.0 1240696.0 OVER i YEAR ( I NCL UDIl4G i> DOLE CASES) i SK I(J 0.0495 i010.5 2020.9 4041.8 GOG3.6 10104.5 20209.i 40418.1 UIHiLE Lobi O.0336 i487.4 2974.9 5949.8 1i899.6 i4874.5 29748.9 59497.8 30DY FelRDENS (IN NCI ABOVE, IN PCT MPBD BELOU ISOTOPE Al EXIT 45 tillJ 90 11IN 3 HR 6 HR 12 HR 1 DAY 2 DAY 4 DAY O DAY 16 DAY 32 DAY t
r Nb , D
.t r6'UT DAT A i ISOTOPE CONCENTRAT10N
. AR-41 2.OOOOE-06 UCI/CC TIliE 1773.00 MINU1ES DOSE TO THYROID IS 0.0 likEtt DOSE TO BONE IS 0.0 tiREli DOSE TO LIVER IS 0.0 tiREM DOSE TO VIDl1EY IS 0.0 MRLli DOSE TO GI-LL1 IS 0.0 HREM DOSE TO LUi1G II O.O MREM (EXCLUDING I401<LE GASLS)
+ 0.57 F1 REM (FROM NOBLE GASES ONLY)
DOSE 10 SKIN IS 87.73 tiREM T)DSE TO WHOLE It0DY IS 59.60 MREM STAY TIME IN HINUTES ORGAN MREM PER 50 MREri 100 MREli 200 MREli 400 tiREtt i MINUTE 5 0 0 ti R Eti i000 MREM 2000 MREti l THYROID O.0 OVER i YEAP DONr v.O OVER i YEAR L1VFR O.0 OVER i YEAR IIDi4EY 0.0 OVER 1 YLAR C 1 --L L ] 0,0 OVER i YEAR >
!.UN ; O.0 OVLR i YEAR (UITHOUT NOBLE GASES) i Ui4 0.0003 1 5 5 0 8 .' . o ai0174.O 620348.0 1240690.0 OVER i YEAR !
(IllCLUDING NOBLE GASES) SEIN O.0495 iOiO.5 2020.9 404i.8 5063.6 10104.5 20209.0 40418.1 Uilai.E LO Di v.vaa6 148~' 4 '974.? 5V49.8 11:Yf9.o i4874.4 29748.9 59497,8 BODY BURDENS (IN NCI ABOVE, IN PCT ttPitti DELOU ISOTOPE AT EXIT 45 MIN 90 tiIN 3 HR 6 HR 12 HR 1 DAY 2 DAY 4 DAY 8 DAY 16 DA( 3? IAY l u ..}}