IR 05000155/1987009

Insp Rept 50-155/87-09 on 870303-04 & 20.No Violation or Deviation Noted.Major Areas Inspected:Gaseous & Liquid Radioactive Programs,Including Effluents Releases & Records & Repts of Effluents

ML20206G406
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	04/07/1987
From:	Hueter L, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20206G331	List: IR 05000155/1987009 ML20206G326
References
50-155-87-09, 50-155-87-9, NUDOCS 8704140543
Download: ML20206G406 (6)

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U. S. NUCLEAR REGULATORY COMMISSION l-REGION III Report No. 50-155/87009(DRSS)

Docket No. 50-155 License No. DPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201

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Facility Name: Big Rock Point Nuclear Plant Inspection At: Big Rock Point Site, Charlevoix, Michigan

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Inspection Conducted: March 3-4, and 20, 1987

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}//, fbwssidb g Inspector: L. J. Hueter A l Date 72/ / /av w u dlu  !

Approved By: M. C. Schumacher, Chief Radiological Effluents and Date Chemistry Section l Inspection Summary:

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Inspection on March 3-4, 1987 (Report No. 50-155/87009(DRSS))

Areas Inspected: Routine unannounced inspection of gaseous and liquid radioactive programs including: effluent releases, records and reports of effluent Procedures for controlling releases; gaseous effluent filtration; audits and appraisals; organization and management controls; training and qualification effectiveness; and status of an open ite Results: No violations or deviations were identified.

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8704140543 870407 PDR ADOCK 05000155 G PDR

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DETAILS l

1. Persons Contacted 1 R. Abel, Production and Performance Superintendent 1,2,3,4J. Beer, Chemistry / Health Physics Superintendent 1,2R. Burdette, Senior Health Physicist 1T. Fisher, Senior QA Consultant 1R. Garrett, Chemistry / Health Physics Supervisor D. Hoffman, Plant Superintendent i S. Guthrie, NRC Senior Resident Inspector '

1D enotes those present at the exit intervie Telephone conversation on March 11, 198 aTelephone conversation on March 12, 198 Telephone conversation on March 20, 198 . Licensee Actions on Previous Inspection Findings

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(0 pen) Open Item (50-155/86006-01): Followup of licensee efforts to quantity small (below monitor sensitivity) releases via the emergency condenser event resulting from a small leak of reactor water into the secondary (shell) side of the emergency condense This work is not completed because the licensee has not completed his efforts to positively identify and quantify a primary to secondary leak as a basis for determining release. As noted in Inspection Report No. 86006, xenon-133 activity (IE-4 uCi/ml maximum)

observed in May 1985 disappeared with isolation of loop 2 of the emergency condenser and did not recur during the balance of the 1985 operating cycle. Extensive testing of that loop during the fall 1985 outage, described in an October 31, 1985 letter to NRR, failed to identify eration with a

theleak or tube November deterioration 1985 and both restart. Transient loopsofwere low-levels returned to op(8E-7 uCi/m xenon-133 were detected for a short aeriod after restart and again for several weeks after startups following s1 ort shutdowns in February 1986 (IGE-6 uCi/ml peak)

and July 1986 (7.2E-7uC1/ml). Because of the ephemeral presence of the xenon, the licensee shifted to weekly analyses of shell side tritium in 1986 in its effort to positively identify leakage. The data reviewed by the inspector indicated that the shell side tritium increased from about IE-5 uCi/ml to about 6 E-5 uCi/ni over 11 months in 1986 while reactor water tritium remained fairly constant at about 1E-3 uCi/ml. However, the picture is complicated by the recurrent presence of tritium in the demineralized water used for shell side makeup (unmeasured) at with concentrations normally in the SE-6 uCi/ml range but showing several spikes near 1E-4 uCi/ml. Licensee representatives are not fully convinced that a leak exists, but nevertheless, made an estimate based on the tritium data and the simplifyir,1g assumption that no makeup water was used and that sampling and evaporation losses were balanced by primary to secondary leakage. This estimate was about 0.75 ml/ minute. (two gallons per week). The licensee plans to complete its estimate of releases that may have occurred via the emergency condenser

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vent within two months and to continue efforts to identify and eliminate the source of contamination to the demineralized water supply. The NRC resident inspectors will review operational implications of the possible primary to secondary condenser lea . Gaseous Effluents The inspector reviewed selected records of sampling and analysis of

. gaseous effluents as well as semiannual effluents reports for 198 The pathways samoled and analysis performed appear to comply with Technical Specification requirements. Licensee ODCM calculations indicated that all releases were within limits. The limit most closely approached (eight percent) was the annual gamma air dose limit of ten millirem at the site boundar The noble gas release (68,000 Curies) was about the same as in 1985 but a factor or two lower than 1984(141,000 Curies). The 1986 release was about six times normal owing to continuing fuel cladding problems experienced over the last four cycles. The problem fuel is gradually being replaced with fuel of a new design. Over half (that )ortion having the greatest potential for leakage, based on exposure) of tie problem fuel to be retained in the core for the upcoming cycle was tested for leakage using ultra sonic testing techniques with no leakers being identifie No violations or deviations were identifie . Liquid Effluents The inspector reviewed selected records of radioactive liquid effluent sampling and analysis for 1986 and the semiannual effluent reports for 108 The pathways sampled and analysis performed appear to comply with Technical Specification requirement Total liquid radioactive effluents (excluding tritium) during 1986 was about 71 mci compared with 154 mci released in 1985 and the 148 mci released in 1984. Total tritium release in liquid effluents in 1986 was 0.35 Ci, well below the 1.3 Ci in 1985 and the 1.1 Ci in 1984. The low total liquid release in 1986 is in large part attributable to the absence of a refueling outage in 198 The licensee has been in a refueling outage (now nearing completion)

since the beginning of 1987 which has resulted in total licuid releases (excluding tritium) of about 141 mci as of the inspection cat Contributing to the liquid effluent activity during this outage have been decontamination solutions used for cleaning five casks that were removed from the spent fuel pool and from efforts to control contamination on the reactor dec No violations or deviations were identifie _ .

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i 5. Leak from Outdoor Tank On February 13, 1987, operatorstransferringwater(whichhadbeen l processed through a demineralizer) to the treated waste hold tank i

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filled the tank to overflowing. The tank is located outdoors on a concrete pad. The overflow pipe which routes water to the radwaste system extends initially above the tank a few inches higher than the manhole cove The manhole cover was sealed with a bolted plate and gasket. Water was observed leaking from the manhole gasket are Operators )romptly stopped the transfer to the tank and lowered the level in tie tank sufficiently to terminate the lea Both maintenance I activities associated with the leaking gasket and aspects of personnel l l errors associated with overflowing the tank are being pursued by the i onsite NRC Senior Resident Inspector.

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The licensee estimates that 10 to 25 gallons (probably nearer the l low end) of liquid leaked from the Based on the concentration of 1.8 Egasket area 4 pCi/ml in of thethe manhole waste holdcove tank comprised of about 30 percent Co-60 and several other nuclides), the total activity in the spill was about 7 to 17 pCi. Most of the contaminated water froze on either the side of the tank or on the concrete pad with some running into a small area of soil off of the concrete pa A commercial absorbant was used to soak up the unfrozen liquid while a heater with a blower was used to thaw frozen water so it could be absorbed. The licensee excavated several cubic feet of 1 contaminated soil at the edge of the concrete pad until only background levels of activity remained according to licensee personnel. The soil and absorbant material were collected in four 55 gallon H type drums currently in storage onsite. The licensee plans to include this waste with a future offsite shipment to a licensed burial facility. A deviation report is in preparation describing the event and the corrective measures ta ken. In addition, the licensee has agreed to prepare an evaluation, including survey data, supporting the conclusion that the decontamination effort was fully successful, to be available for any future revie i No violations or deviations were identifie . Air Cleaning Systems ThelicenseehasnoaircleaningsystemssubjecttoTechnical Specification surveillance requiremen A moisture separator and HEPA filter are located in the off gas line at the base of the vent stack. Although no in place testing is performed for this HEPA filter, a new HEPA filter, certified as meeting standard acce)tance criteria, is installed each refueling outage. The chemistry la) oratory has a separate unmonitored vent with HEPA filtration. An in place leakage test is performed annually using 00P and an administrative 1y established i acceptance criterion of 98 percent. The acceptance criterion continues to '

be met. In addition, smears are taken and analyzed monthly from the l ducting down stream of the chemistry laboratory HEPA filter. These l smears continue to show no detectable activity above backgroun No violations or deviations were identifie I

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7. Audits The inspector reviewed Audit Report No. QT-86-25 for an audit conducted October 13-17, 1986, regarding implementation of the REMP/RETS programs initiated in late 1985. The audit also included a followup review of all findings and observations from the previous annual audit in the radiation protection area to verify that identified problems had been properly resolved. The one finding and four observations during the ,

current audit were relatively minor in nature. These matters are being appropriately addressed on a timely basi No violations or deviations were identifie . Organization and Training The chemistry and health abysics organization has been quite stable for the past two years at bot 1 the technician and professional level. The twelve technicians who serve capacities in both radiation protection and chemistry, and may analyze samples associated with effluent releases, are designated in four levels from trainee to senior technician, depending on training and demonstrated qualifications. Trainees will perform analysis only under direct supervisio A Senior Health Physicist (one of five professionals who report directly to the Chemistry Health Physics Superintendent) is directly responsible for radioactive material control, including liquid and gaseous effluents, and for compliance with RETS. Initial training of technicians regarding RETS and related procedures was provided by Health Physics managemen Periodic refresher training is being provided by the Training, Departmen Chemistry and radiation protection personnel have also been given specialized training on systems, process monitors and the Technical Specification requirements for monitors. Valve operations for liquid batch releases are performed by auxiliary operators. Personnel interviewed were knowledgeable of liquid and gaseous radwaste system,s procedures, and their assigned responsibilitie No violations or deviations were identifie . Exit Interview The inspector summarized the scope and findings of the inspection with licensee representatives (Section 1) at the conclusion of the inspection on March 4, 1987 and in followup telephone discussions on March 11, 12, and 20, 1987. The inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection. The licensee did not identify such documents or processes as proprietary. The inspector summarized the scope and findings of the ins)ection. In response to certain items discussed by the inspector, t1e licensee: Stated plans to complete within two months their estimate of releases that ma have occurred via the emergency condenser vent. (Section 2 .

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l b. Stated that continued effort would be given to identifying and eliminating the source of contamination to the demineralized water supply. (Section 2).

c. Stated they had removed contaminated material resulting from a spill on February 13, 1987, and would send the material to a waste burial site. They also stated they would attach to the deviation report and evaluation, including survey data, supporting their conclusion '

that the contaminated material had been removed. (Section5).

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