BECO-82-194, Responds to Confirmatory Action Ltr 82-19 Re Identification of Spent Resin on Roof Tops & Pavement within Protected Area on 820611.Condensate Demineralizer Sys Identified as Resin Source & Secured.Related Documentation Encl
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- CoStrN EDIS O pe COMPANY COO cayLorcw Giacr7 eQETON. MAme ACMue[TTs 0 219 9 .
4.c -*** " **^"* July 15, 1982 RFrn. Ltr. #82-194 Mr. Richard W. Starostecki, Dir mtor Division of Project and Resident Programs Nuclear Regulatory Ccrmission 631 Park Avenue King of Prussia, PA. 19406
- License No. DPR-35 Docket No. 50-293 Response to CAL #82-19 Reference (A) NRC lettnr (R. Starostecki) to BDCo (W. Harrington), CAL #82-19, dated June 16, 1982
Dear Sir:
his letter provides our response to Reference (A), Its 6, rogarding the identification of spent resin on roof tops and powcment within the protected area of Pilgrim Nuclear Pcuer Station on June 11, 1982. Response , M h
- 1. 'HistoryIa causes
'~
Se Condensate Dcmineralizer System has been identified as the source of the resin contamination found in the ductwrk. More specifically, the processes associated with condensate dcmineralizer resin backwasVtransfer have been deternuned as the causal factors as discussed belcw During resin transfer operations into a condensate deineralizer, the vent valve is open to allow proper resin sluicing and subsequent filling with water. Condensate deineralizer venting occurs sequentially via 1) ccmnon j vent header, 2) gas scrubber, 3) reactor building ccntaminated exhaust systm ; and 4) standby gas treatment systm. (Attachments A & E) l For the fill step, gas scrubber readings are utilized by the operator for indication of a " Pull" dcmineralizer. Howwer, because of excess water carry-over into the scrubber and beyond, water could flood through the scrubber ard into the ventilaticn ductwork on El. 23' of the reactor building, depositing any entrained resin in the ductwrk and ultinntely, after drying, in the Standby Gas Treatment Syst s. 8606300171 860613 PDR FOIA ( *jL BURNSTEIS6-58 PDR C___.______.__ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ . - _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _
r b aros gg 33 , co p y
- g g W. Starostecki, Director
_- My 15,1962 Pege 2 4 During resin backwash operations, the " Cation" or " Storage" tank, by systen design (Attachment B) , warrant the respective vent valve to be'in the open position for venting through the upstream gas scrubber. Small amounts of resin are sometimes entrained in the air and water sluice, which could gain access to the contaminated exhaust vent plenum as discussed above.
- 2. Extent of Doct Cbntamination Attachment D shows the extent of duct contamination frcm the sources (Conden-sate Dmtineralizers) to the Reactor Building Vent Stack. It also shows the amount of resin collected frczn June 12, 1982 to July 13, 1982.
Since the contaminatcd exhaust filters were found to be degraded and replaced on ?' arch 15, 1982, and since the analysis of the resin indicated that it was at least a year old, it was concluded that the nost likely patlway of the resin was frcm the condensate danineralizer vent to the contaminated exhaust plenum, through the contaminated exhaust filters and out the Reactor Building Vent Stack.
- 3. Ciretrnstances Surrounding Release of Resins
'Ihe circumstances surrounding the release of resin can be attributed to several factors. As mentioned earlier, condensate danineralizer backwash operations and problans with the condensate domineralizer systen vents were primary factors.
In order to maintain condensate danineralizers operating within icw differ-ential values, so as to attain maxirnen filter capabilities while minimizing crud loading of the reactor vessel and attendant radiation exposures, num.rous backwashes of the condensate danineralizer beds were re3uired during the ascension to guer frcm extended refuel outages. The resin beds that had
- accunulated in the vent ducting over the ymrs were hastened in their mioration by the repeated venting operations and by virtue of SGIS testing usiry a ccrron ventilation plenum allcwing the entrained resin beads to pass into the Reactor Building Ventilation.
The initial identification of the release was observed by a health physics technician on June 11, 1982 while collecting randcm samples on top of the Condenser Retube Building, as part of a general site survey.
- 4. Arount and Extent of 01 site and offsite Reimses An extensive survey was conducted both cnsite and offsite. Small gtnntities of resins wre detected on sections within the protected area to the south ard west of the plant. Attac) ment C sbus cnsite areas where resin was discovered.
'Ihe total anount of resin found outside the process buildirgs was less than one cubic foot. licalth physics technicians surveyed and checked pnrsonnel and c n: ___ ,
e EDOT'c4 {c: cow CSM8'ANY m Richard W. Starostecki, Director July 15, 1982
~
Page 3 vehicles in the parking lot with no measurable results. The storm drain outlet to the Discharge Canal was checked with no measurable results. A fine mesh screen was affixed to all storm drains to cxantain resin within the protected area. In situ soil analyses conducted in selected areas outside the Protected Area resulted in no detectable activity above historic levels. We shorefront area and the main stack area were also checked which resulted in no activity above tackground. A cmplete list of samples taken including isotopic analyses is available for review. . ) i In total, less than one (1) cubic foot of resin was found inside the protected area fencing and less than (70) cubic fmt was found and renoved from inside the ventilation system. (Attachment D)
- 5. Corrective Actions Taken our inmcdiate corrective actions were to conduct an extensive survey of l
affected areas, comence cleanup operations, and identify and secure the resin source. The Condensate Danincralizer System was identified as the resin source and was secured to preclude further backwashing or venting l activities until procedures and/or tmporary modifications could be imple-3 mented to ensure that no more resin would be admitted to the ventilation i ducting. Tne vent to the ducting was blanked off under Tm;nrary Modification T4 82-39 and a Turporary Procedure 'IP 82-44 was written to address the operational as-pects necessary to prevent carryover of resins. The Tagorary Procedure was finalized utilizing a clean (new) charge of resin before condensate daninier-alizer operation was allowed again. The integrity of the contaninated exhaust ventilation filters was verified by DOP testing (Procedure #7.) .30), on June 14, 1982 and found to be 99.95tt l mrticulate efficient for both banks. Potentially affected safety-related ventilation systs emnonents were inspected or tested to verify their ; operability and the absence of resin. Clean air intake filters and ducts were l inspected to verify absence of resin. Se Reactor Building Vent monitor was inspected to verify operability. We inspection found the systen to be operable.
%e long term corrective actions to prevent recurrence currently in place or under consideration are ]) changes to the operating procedure, i.e.
restricting times and flows during backwashes and transfers to minimize resin volume with the cation tank; 2) a plant design change to the existing gas scrubber so as to provide a larger volune, two levels of phase separation and a final stage screen to trap the resin; and 3) the condensate danincralizer
- vent systen will be ventcd to the TIP Hoom rather than directly to the ventila-tJon ducting.
In addition, a vmtilation systan inspection program has been estnblinhcd to identify and rutove any ramining resin frun the ventilation systan. We integrity of the contaninated exhaust filters will be verified by visual in-spection on a six nonth basis. __ _-- -_. -- - - _ _ _ _. :- T --- ,-_--_.____-_I_
Co:1rou g:enu c:NPANY l- rd W. Starostecki, Director
, July 15,1982 page 4 . . .i+ ~
P We believe these acticms to be prudent and effective measures to assure that the condensate demineralizer resins will not be entrained'in the plant ventilation systms in the future.
- 6. Additional Panagonmt CNersight Initiated Boston Edison Ccrpany, in response to an Order tradifying our License, has cmmitted to improve the Corrective Action Program through a Performance Improvenent Program (PIP) . In Sections III.l.C.3 and III.l.C.4 of the PIP, we have made ccrmitments to identify weaknesses and determine alternatives for improvcments. This determination will include 1) Fhnagonmt Systes involved in Corrective Action Program, 2) Forms and Reports including Status Reports, 3) latest Trend Analysis, 4) Informational sources and 5) Evaluation of cmmunication methods and uses.
In addition, revision to the Corrective Action Systen design will be de-veloped around a " universal carrier form" on which to identify report problans/ events. 'Ibe use of this report / followup mechanisn will be pro-cedurally addressed. 'Ihe origin of same of the elments which will revise the Corrective Action Systcn are based on our recent knowledge of a Corrective Action Systm used by another Utility, currently under review by Boston Edison Company. , We believe this infonnation adequately addresses the Reference A concerns; hcuever, should you have additional questions on this subject, please do not hesitate to contact us. Very truly yours, I
! , j /
Attachnents: (A) P&ID #M-213 (B) P&ID #M-214 (C) Iccation of onsite Rosin Discoveries (D) Sketch of Resin Discoveries in Ventilation Systen (E) P&ID #M-294 l l l
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': A. R. Trudeau .
NonSafety Related DfDt Doc. TCH B5-139 (W142) ste: May 6. 1985 Investigation of ROR 85-4-3-205 Sublecti Hot Shop floor Drain Backing Up 1
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Mstribution: J.MastranQelo P P. D, Smith J. P, Aboltin A. L. Oxson M, N. Brosee N. Pickett (4) C. J. Mathis that ths floor Af ter reviewing floor drain drawings M-404 and M-421 intoit the appears drain in the Hot Shop ties into the norm) waste line which goesThi sanitary waste systero, recommends that the follwing actions should be taken 1. Trece flow path of floor drain in Hot shop with colored dye in or establish exit point. ry 2. If exit point it in the oil separator prior to going into the sanita Radiological uste ejector, this line must be blocked off and a reviw of til other Floor draint in the Mochine Shop should also becontamination. ible evalueted. samples should be taken of the sanitary systembefor poss accomplished 3 R3 route of appropMate floor drains to them Radvaste taust if this 16 tna case. tion and any 4. Drewings should be updated to 11flectible. the current configura reedifications should be reflected as soon as poss 5. The source of this water is thought to be f' rom using the ultraso cleaner. ttou NOTE > Floor drains must be kept isolated at all times until investiga modification is complete, VS:Ep
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( 1-l;EV = 1. 5 r ISIG=2.0, ISM 00THS=1) SAMPLE DESCRIPTION.. SAMITARYPilMPItJGSTATION[(ONS/n[g[c) l CCERP OPERATOR......: SHATAS DATE & HOUR SAMPLED.: 5/6/05 e 15\5\730 l TIAIE s HOUR AtJALYZED: 5/6/85 0 1740 COUiri ( YES/t!O ) - Y SE1 I/0 liEVICE T O REriUTE , PRESET tit 1E TO O O COL.Lt C T T I(1E (SECi 7 3000 (10 0 CullNTIslG COlltJT doi 1E T O Ti i! Colli 1TL IN SPECTRUli - 18726. GAMMA SPECTR0 GRAPHIC ANALYSIS ClI.T N N E L Ar.CA(COUNTS) ENERGY (NEV) ISOTOPES GROSS NET 1430.23 139. 101. 662.22 CS-137 2550.01 219. 202. 1173.83 CO-60,CO-56 2890.4?O 178. 159. 1333.11 CO-60
........................................................ ~.........
RADIONUCLIDE ANALYSIS COLLECT 11HE (SEC)..: 3000 ISOTOPE ACTIVITY +- 2 SIG l- CS-137 2.24285E-07 UC/ML +- 7.47432E-08 ( 33.33%)d#Ie' CO -60 5.86930E-07 UC/ML +- 1.15323E-07 ( 19.65 %) e' f ISOTOPE THEORETICAL MEASURED DIFFERENCE , CS-137 661.64 662.22 0.58 , CO-60 1332.49 1333.11 0.62 STANDARD DEVIATION = 0.60 r C4
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\ il .t \ 0 DATE & TIME NOW...: 16:30'18 6-MAY-85 .
DECAY TIhE (MIri) : 1 CAL]D CURVE t...: 1 DILU TION FACTOR. ! 1 DEnD TIME (%)...: 0 (+-hEV=1.5r 1SIG=2.0, ISM 00THS=1) ,
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SAMPLE DESCRIPTION..: SEPTIC TANK [84d vg.f[s) ~ r: e 1 ' [ CCSRP OPERATOR......: SHATAS , I DATE & HOUR SAMPLED. 5/6/85 0 1630 '> DATE & HOUR ANALYZED: 5/6/785 0 1635 COUNT (YES/NO) ?Y SET I/O DEVICE TO REMOTE, PRESET TIME TO O O COLLECT TIME (SEC) ? 3000 tlOW COUNTING j COUNT DONE TOTAL COUNTS IN SPECTRUM = 19361. GAMMA SPECTR0 GRAPHIC ANALYSIS CHANNEL AREA (COUNTS) ENERGY (KEV) ISOTOPES j GROSS NET 1429.82 132. 94. 662.03 CS-137 2549.68 245. 228. 1173.68 CO-60,CO-56 2898.71 200. 181. 1332.98 CO-60
...................................................................... k RADIONUCLIDE ANALYSIS COLLECT TIME (SEC)..: 3000 ISOTOPE ACTIVITY +- 2 SIG CS-137 2.08682E-07 UC/ML +- 7.40703E-08 ( 35.49 %)dl./3
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RUN GAN\N\tiMAN PILGRIM NUCLEAR POWER STATION DATE & TIME N0lJ...* 13:12:54 10 -fi AY-05 DECAY TIfiE ( tiI N ) : 15 CALID CURVE I...: 1 DILUTION FACTOR. 1 DEAD TIME (%)...: 0 (+-KEV =1.5, ISIG=2.0, -fSM00THS=1) . SAMPLE DESCRIPTION..: LIO. SAMPLE FROM SANITATION TRUCK CC&RP OPERATOR......: A. STEARNS DATE & HOUR SAMPLED.: 5-10-85,1300 DATE & HOUR ANALYZED: 5-10-85,1315 COUNT (YES/NO) ? Y SET I/O DEVICE TO REMOTE, PRESET TIME TO O O COLLECT TIME (SEC) ? 3000 NOt1 COUNTING COUNT DONE ( TOTAL LOUNTS IN SPECTRUM = 22673. GAMMA SPECTROGRAPHIC ANALYSIS CHANNEL AREA (COUNTS) ENERGY (KEV) ISOTOPES GROSS NET 2550.28 233. 199. 1173.95 CD-60,CO-56 , 2898.45 207. 108. 1332.87 CO-60 4 J ' RADIONUCLIDE ANALYSIS 4
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r COLLECT TIME (SEC)..: 3000 g ISOTOPE ACTIVITY +- 2 SIG [ O, $ CO-60 6.93866E-07 UC/ML +- 1.19878E-07 ( 17.28[%),- ,
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- DATE & TIflE NOW...* 16:23:.10 24-tiAY-85 gd fiECAY TIME (tilN): 1 cs M CALIB CURVE I... 1 DILUTION FACTOR.; 1 DEAD Til1E (%)...: O
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P1LGRIM NUCLEAR POWER STAT 10N
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1 1 j II A I E & TIME NOW...: 17:37:39 6-MAY-05 DECAY TIME (HIN): 1
; CALID CURVE I...: 1 i IIILUTION FACTOR. 1
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! COLIFCI T i tie s c,EC i .50 0 G
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! T O ral L'Ollil l S IN SPECTRHis - 107?d.
l ..... ............................................................... i 1 1 GAsiMA SPECTRUGRAFHJ C ANALYSIS 1 2 j Cll. rML nREA(CDUtl15) ENE RGY (l(EV ) ISOTOPES I GROSS NET a J i 1430.23 139, 101. 662.22 CS-137 I CO-60,CO-56
'?550.01 219. 202. 1173.03 l 2E,90.90 178. 159. 1333.11 CD-60 J
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- 1 j IS010PE THEORETICAL HEASURED DIFFERENCE i i
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' I DEC AY TIME ( Mili) : 1 @ 6,g @ f UAl.lB CURVE 1...: 1 ff. l_j t.i i i .U l"t OH F AC T OR . ' 1 N(m4Lig .4#bOM
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ISO f 0PE THEORETICAL MEASURED DIFFERENCE , CS-137 c.o l . 64 ,661.89 0.25 CO-60 .1 3 3 2 . 4 9 1332.66 0.17 STANDARD DE:VinTIOic o. :1
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ISOTOPE MDA (UC/ML) MN-54 3.66Al'iE-08
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I I. 6 0 ! Di'E IHEUREIICAL. MEASURED DIFFERENCE CD-13/ 661.64 662.59 0.95 eN CU-60 1332.49 1332.58 0.09 l ., STANDARD DEVIATION = 0.6'7 y .. . IbOTUPE MDA ( UC/ Mt. ) HN S4 3.756V7L-00 - FE- 59 5.64599E-00 .L
'N-6', 6.75962F-00 - - - --
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JATE & HOUR SAMPLED.: 6-29-85,1035 JATE & HCUR ANALYZED: 6-29-85,1125
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- OUNI DUNE ul AL COUNfS IN SPECTRUM = 19417.
GAnM6 SPECTROGRAPtlIC ANAL s'S t S LHo ifIEL AREA (COUtnS) E N ERtiY ( F E V .i i%!A ' CROSS NET 1 4.5 0 , / d lb/, 118. 4( 7 . L' Y , 1. i . 2 40.69 2ti. 188. .! t ' .> . , 5 n. -6),: 20 Yts . Y 5 190, 1bh. .l33? bH - - - ' i (g /37 8 .2.G E -7 ,d RADI%UCL IDE ANAL M iR u d Co 60 1 1.d5 d- > , d OLLEf~ , 'IHF '"!C)..'
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GAMMA SPECTROGRAPHIC ANALYSIS CHANNEL. AhE A ( CollrJ T S ) ENERGY (tWV) ] SUIUPt S GROSS NET 1430.02 162. 149. 66?. O CU '.L'
? b b O . t ,', 266. 232. L 173. i 1 C O -!.0 2099.32 199. 19V. 1332.75 00- 60 RADIONUCLIDE ANALYSJE 42 G /37 A.G 4-7 wEa unE . s e: c > . . : 30 %
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