IR 05000263/1976002
| ML20024G260 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/29/1976 |
| From: | Fisher W, Greger L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20024G256 | List: |
| References | |
| 50-263-76-02, 50-263-76-2, NUDOCS 9102080437 | |
| Download: ML20024G260 (11) | |
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U. S. NUCLEAR RFI;UI.ATORY COMillSSION
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OFFICE Or INSPECTION AND ENTORCrJtENT REGION 111 Report of Operational Radwaste Inspection IE Inspection No. 050-263/76-02 Licensect Northern States Power Company License No. DPR-22 414 Nicollet Hall Category 1 C Minneapolis,}!innesota 55401 Monticello Nuc1 car Generating Plant Monticello, Minnesota Type of Licensect BWR 1670 int Tyre of Inspection:
Routine, Unannounced
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- 1 Dates of Inspection:
January 5-9 1976 g!
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Principle Inspector :
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Accompanying Inspectors: None Other Accompanying Personnel: None
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Reviewed By:
W. L. Fishcr,'Secti Leader
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Fuel Facility Projects and (Date)
Radiation Support
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SUtDIARY OF FINDINGS Inspection Summary Inspection on January 5-9, (76-02) : Review of radwaste records and procedures, process monitor calibrations, and reactor coolant chemistry.
Enforcement items
!b items of noncompliance with NRC requirements were identified during this inspection.
Licensec Action on Previously Identified Enforcement Items Not Applicable.
Other Significant Items A.
Systems and Components j
The augmented of f-gas system was considered operational f or the purpose of impicmentation of the revised technical specifications coumencing with the fourth quarter of 1975.
(Paragraph 3.a. Report Details)
B.
Facility Items (Plans and Procedures)
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Unresolved item - The licencoe's process monitor calibration procedures utilize solid sources in the performance of quarterly calibrations.
Review of cross calibrations between the solid sources and fluid standards is required to determine the adequacy of the quarterly calibrations.
(Paragraph 7. Report Details)
C.
Managerial Items None identified during this inpec tion.
D.
Noncompliance Identified and Corrected by Licensec None identified during this inspectP.n.
E.
Deviations t
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Nonc identified during this inspection.
F.
Status of Previously Reported Unresolved Items Not applicabic.
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Management Int erview
L interview was conducted with Mr. Entson and other members A management of the licensec's stuf f at the concluulon of the inspection on January 9, 1976. The f ollowing items were discussed with the licensee representatives:
A.
The inspector noted that the licenr.cc had impicmented the technical specification revision (Amendment No. II) pertaining to operation of the augmented off-gns system as of October 1, 1975. The inspcetor asked f or clarification of the licensee's intent with respect to continued implementation of the revised technieni specifications.
The licensee stated that although some operational problems had not been fully resolved, the augmented off-gas system would continua to be operated in accordance with the revised technieni specifications.
(Paragraph 3.a, Report Details)
B.
The inspector noted that.the gaseous ef fluent limits changed ~ f rom an.nual to quarterly with impicmentation of Amendment No. Il to the technical specifications. The inspector requested the licensee to clarify the derivations of the " Percent of Technical Specifications Limit" entries in the semiannuni report covering the last half of 1975. The licensee stated that explanatoty information would be
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included in the semiannual report.
(Paragraph 3.b, Report Details)
C.
The licensee stated that the procedures utilized to control discharge of radwaste f rom the licensee's solidification system to the contrac-tor's mobile solidification trailer would be revised to specifically
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address controls to prevent inadvertent dischar ge of radwaste.
(Paragraph 5. Report Details)
D.
The licennec stated that the off-gas stack monitor conversion factor calculation would be reviewed to ensure that gas decay tank release calculations utilize the correct isotopic analyses.
(Paragraph 7.a.
Report Details)
E.
The inspector stated that due to time restrictions and the limited availability of a member of the lic ensee's staf f, cross calibrations between the discrete solid sources used in several process monitor calibration procedures and fluid standards had not been examined.
The inspector further stated that until the cross calibrations were reviewed the adequacy of the calibrations would be carried as an i
unresolved item.
The licensee stated that the cross calibrations would be availabic for the inspector's review during a subsegunnt inspection.
The licenvec further stated that certain cross calibra-tion procedures were to be revised to include a requirement for j
multipoint en11brations and more explicit description of calibration sources.
(Paragraph 7, Report Details)
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Personn contact ed C. larson, Plant Ibnager H. Clarity, Plant Engineering and Radiation Protection Superintendent L. Eliason, Radiation Protection Engineer l
F. Fey, Assistant Radiation Protection 1:ngineer R. Jacobson, Chemist L. Nolan, Engineer J. Peterson, Radiation Specialist 2.
Cencral
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This inspection was conducted to examine the licensee's radwaste (gaseous, liquid, and solid) operations for compliance with NRC regulations. The licensec's derivations and records of radioactive i
ef fluents were reviewed and compared with the radioactive releases reported in the licensee's semiannual reports.
Liquid and gaseous ef fluent process monitor calibrations and reac tor coolant chemistry measurements were also reviewed.
No deviations from regulatory requirements nor prudent health physics practices were identified during the inspection.
3.
Gascous Radwaste a.
Augmented Off-Gas System The licensec's augmented of f-gas system, consisting of two recombiners and five pressurized hold up tanks added to the existing 30-minute holdup system, has operated most of 1975.
Feveral prob 1 cms, including of f-gas detonations, leakage associated with the hydrogen analyzers, and pressure oscilla-tions causing flow control dif ficultics, prevented continuous operation during the year. The probicm of of f-gas de tonatfor.s has apparently been resolved through modification of the catalyst support bed and thorough cicaning of the of f-gas piping.
Although minor operational problems remain, the licensec considered the augmented off-gas system operational for technical specification purposes as of Oct.ober 1,1975. The more restrictive gaseous ef fluent technical specification limits therefore become applicable commencing with the fourth quarter of 1975.
Based upon statements by licensee personnel and review of liccusec records, the recombiner downstream hydrogen monitors have been operabic (at 1 cast one per train) during power operation, hydrogen concentrations, downstream of the recombinors
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have not reachcd the 4% trip point, and the gas decay storage
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t tanks have not experienced prob 1 cms associated with valve Icakage.
Storage times in the gan decay tanks have averaged between lo and 20 days, dependent upon condenser air inicakage rates and operating history.
No instances of less than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> holdup were noted. Condenser air inleakage, determined weekly as required by the technical specifications, has normally been in the range of 5 to 10 cim.
Cas decay tenh gross radio-
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activity is determined in conjuntion with the weekly air inicokage surveillance.
Review of the licensce's curveillance records revealed the maximum gross radioactivity contained in any one gas decay tank during 1975 to have been less than 25% of the technical specification limit.
Subsequent to the last refueling outage, gas decay tank gross radioactivity has routinely been i
less than 1% of the technical specification limit. According to the licensee's surveillance records, functional test and calibration frequencies for the modified off-gas hydrogen analyzers complied with the technical specification requirements
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I during 1975.
b.
Cross Caseous Radioactivity Releases'
Continuous monitors on the off-gas stack and reactor building vents perform alarm, isolation, and quantificat. ion f unctions to prevent exceeding the technical specification release rate limit.
The gross radioactivity release limit was redaced by a f actor of approximately 10 by the modified of f-gas technical specification revision which became effective October 1, 1975.
According to the licensee's monitoring records, the maximum release rate experienced during the first three quarters of 1975 was Icss than 25% of the technical specification limit (annual average), and the average release rate was approximately 5% of the technical specification limit during that period. The maximum release rate noted under the revised technical specifications (fourth quarter) was Icss than 3% of the technical specification limit (quarterly average) and the average release rate was Icss than 1.5% of the tecnnical specification limit.
No release rates
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in execss of the instantaneous technical specification limits were identified during the records review.
According to the licensec's surveillance records, air ejector
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of f-gas isotopic analyses were perf ormed weekly during the entire year.
The long-lived to short-lived activity ratio was determined ucekly during the first three quarters of the year, as required by the former technical specifications.
Average beta and gamma energics per disintegration were determined veckly in conjunction with.the isotopic analyses.
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Rnd f otodine Ecleasds c.
Charcoal sampicra on the off-gab stack and reactor building
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vents provide continuous sampling and periodic qaantif ication of airborno radiciodine ef fluents. The rad j oiodine release limit was changed during the year (conuencicg in October) due to the modified of f-gan technical crecification revist'n and a change in the location of the nearest dairy cow. According j
to the licensec's monitoring records, the average radiciodinc release rate was less than the annual technical specification
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limit f or 1975. Subsequent to the last refueling (October 1975),
radioiodine releases have routinely been Icss than 1% of the technical specification limit. The modified of f-gas system utilizes an in-line charcoal bec' f or iodine removal, whereas
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the former off-gas system did not utilir.c ' rc oa l. Daily sampling has not been required during 197S.
1-133 and 1-135 analyses have been performed at Icast monthly, d.
Radioactive Particuin te P,eleases Particulate samplers on the of f-gas stat t and reactor building vents provide continuous sampling and periodic quantification
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of airborne particulate effluents. The radioactive particulate release limit was changed during the year (commencing in October), due to the modified of f-gas technical specification revision.
According to the licensco's monitoring records, the average particulate release rate vas Icss than.the annual technical specification limit during 1975.
S'ibs equ en t to the last refueling (October 1975), particulate releases have
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routinely been less than 1% of the technical specification limit.
Daily sampling has not heer required during 1975.
Gamma isotopic analyses were performed weekly; FIFC values are determined f or each isotopic analysis.
Sr-89, Sr-90, and gross alpha analyses were conducted at 1 cast quarterly.
e.
Tritium Releases During 1975, the licensee has used coth cold trapping and silica gel to collect vaporous tritium samples. According to the licensec's surveillance records, the of f-gas stack and the reac tor building vents were sampled monthly during 1975. Gaseous tritium releases were calculated from conden-sate concentiations snonthly. The licensce's sampling records were in agreement with the tritium releases reported for the-first half of 1975.
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4.
Liquid Radwante a.
Effluents
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No liquid radwaste releases were mado during calendar year 1975.
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Wasto liquida continue to be recycled for reuse in the reactor
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coolant system or used in processing of solid wastec.
In order to achieve this maximum recycle philosophy, the licensee minimizes the generation of high conductivity wastes, such as laundry, chemical c1 caning, and dcmineralizer regeneration water.
The licensec has not experienced significant ground water or condensor inleakage. Makeup water is required to compensate for losses via evaporation and solid radvaste usage.
The makeup requirements have been significantly reduced by operation of the recombincts in the modified off-gas system.
Approximately 4500 gallons of high conductivity (low radio-activity - approximately 56 mci total) chemical waste water was shipped of f site f or disposal during 1975.
The licensec's monthly discharge canal surveillance records were reviewed.
No discrepancies from the technical specification requiremeats were noted, b.
Liquid Storane The licensee's " Liquid Radwaste Storage Activity" surveillance records f or 3975,were selectively reviewed.
No discrepancies from the required surycillance frequencies were noted. The maximum total activity recorded f or thc Maste Sampic, Floor Drain Sample, Waste Surgo, and Condensato Storage Tanks was Icss than 20% of the technica'l specification limit of 30 curies.
5.
Solid Radwaste The licensec's radwaste solidification system remains out of operation, due to cement hardening prob 1cma in the " mixer-feeder." Excessive
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personal exposures associated with maintenance resulted in the decision to modify the "mixcr-feeder" by improving the flushing arrangemer,t.
Further modifications to the solidification syster, including TV level monitoring instrumentation and a drum fill splatter shicid, arr also underway. Until the radwaste solidification modifications are completed, mobile solidification services have been contracted from Chem Nuclear Systems, Inc. Mobile solidification operations were
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conducted on four occacions during 1975, totaling approximately threc
months onsite time.
According to the licensee's records, approximately 5000 curies of waste was transferred to chem Nuclear for solidification-7-
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l and disposal during 1975. The licensee completed construction of a permanent enclosure which surrounda the mobile solidification trailer. The enclosure provides weather protection and enhances (-
contamination control, should accidental Icakanc occur.
Licensee procedures control the solidification operations, including ship-J ment of the solidified radwaste.
It was noted that thest procc-dures did not specify precautions to prevent inadvertent discharge of radwaste material via the temporary hose connection to the mobile solidification trailer.
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Revicw of the licensec's waste disposal records did not reveal any discrepancies from the waste disposal data reported in the licensec's Ninth-Semiannual Operating Report..
No discrepancies from packaging vr labeling requirements were note'.
6.
Radioactive Effluent Reports The licansec's semiannual operating reports covering the periods July 1,1974 through December 31, 1974 and January 1, 1975 through June 30,15 75 were reviewed. The reporting format complies with the technical specification requirements.
No anomalous results were noted.
It was noted that nobic gas releases had decreased more than a factor of 10 orer the reporting periods, apparently due to replace-ment of Icaking fuel in January 1975 and increased usage of the modified of f-gas syrtem during the first six months of 1975. The licensce's release rec;rds subsequent to the October 1975 refueling indicate that the noble gas telcases have been reduced by more than a f actor of 100 over those experienced during the last half of 1974.
i 7.
Process Monitors a.
Off-Gns Stack Monitor Continuous of f-gas stack monitoring is provided by two scintill.-
tion detector monitors located on an isokinetic sampic line. The monitors' outputs are averaged and printed out hourly by the process computer. According to the ifcensce's records, the conversion r.Ator f or the monitor is determined at least seckly from an in '.3pic analysis performed on a sample of the air ejector of-. gas.
Review of the licensee's conversion calculations revealed that a relatively minor error apparently exists in the method used to calculate the conversion factor. The nonsystenatic error evolves from an inaccurate celection of gas decay storage tank isotopic analyses. The stack monitor alarm and isolation trip points are determined querterly in conjunction with the monitor calibration.
The setroints were found to be consistent with the technical specification release rate limits.
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According to the licensec's surveillance records, functional
test and calibration f requencies during 1975 complied with the technical specification requirements. The adequt.cy of the calibration technique was not ascertained and is considered unrecolved pending examination of cross calibrations between the.discretc solid sources utilized in the calibration procc-dures and gaseous standards. Performance of the functional test was adequatc.
b.
Air Ejector 11onitor Continuous air ejector off-gas monitoring is provided by two of f-line ionization chamber monitors.
According to licensee personnel, both air ejector monitors were operable throughout 1975. A selective reyiew of the licensec's records did not reveal any instances of monitor inoperability.
It was further noted that operation with the off-gas holdup system recombiners bypassed was not necessary during 1975. The air ejector monitor
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isolation trip points are determined in conjunction with the monitor calibration. The trip setpoints were found to be consistent with the technical speelifcation limit for the maximum stack gross rodioactivity relcace rate (assuming 120 minutes decay). The ifcensec's records indicated that the air ejector monitor conversion factor (mR/hr to uCi/sec) is determined at Icast weekly, based upon an isotop'ic analysis performed on a sampic of the air ejector off-gas.
No discrc-pancies were noted in the conve-ton calculations.
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According to the licensco's surveillance records, functional test and calibration frequencies during 1975 complied with the technical specification requirements.
Cross calibrations between the discrete solid sources utilized in the calibration procedure and gaseous standards were not examined.
This item vill be examined further during a subsequent inspection.
Performance of the functional test was adequate.
c.
Reactor Building Vent }1onitors Continuous release monitoring of the rcactor building ventila-tion exhaust is provided by an off line continuous air monitor.
The nonitor output is averaged and printed out on an hourly basis by the process computer. According to the licensec's surveillance records, functional test and calibration frequencies
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during 1975 complied with the technical specification requirements.
Cross calibrations between the discrete solid sources utilized in the calibration procedure and gaseous standards were not examined.
This item will be examined further during a subsequent inspection.
Performance of tbc functional test was adequate.
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Two GM monitors in the reactor building ventilation plenum and two CM monitors on the refueling floor serve alarm and ventila-tion isolation funtions. According to licensee personnel, the monitors were opetabic throughout 1975. A selective review of the licensce's records did not reveal any instances of monitor inoperability. According to the licensce's surveillance records, functional test and calibration frequencies during 1975 complied with the technical specification requirementa. The monitor trip points are determined quarterly in conjuction with the monitor calibrations. The setpoints were found to be consistent with the technical specification requirements, d.
Liquid Effluent Monitor and Discharge Canal Monitor
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Liquid radwaste effluent and discharge canal monitoring is provid(d by separate, in line, scintillation detector monitors.
~ According to licensec personnel, both liquid monitore were operable throughout 1975.
A selective review of the licensce's I
records did not rescal any instances of monitor inoperability.
According to the licensce's surveillance records, functional test and calibration frequencies during 1975 complied with the technical specification requirements. Cross calibrations between the discrete solid sources utilized in the calibration procedures and liquid stardards were not examined.
These cross calibrations will be examined during a subsequent inspection.
Performance of the functional tests were adequate.
8.
Procedures The f ollowing Operations Manual changes were reviewed:
B.5.11 Process Rad'intion Monitoring (9/6/75)
B 7.1 Liquid Radwaste (2/11/7 5)
B.7.2 Caseous kadwante (11/25/75)
B.7.3 Solid Radwaste (6/25/75)
The above listad procedural changes were noted to have been reviewed by the Operations Commit.tec. The changes do not appear to degrade the licensec's radiological effluent control capabilitics.
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9.
Reactor Coolant Chemistry The licensec's reactor coolant radiochemintry results for calendar year 1975 were examined.
No discrepancies from the technien)
specif f ention surveillance requirements for radiciodine sampling or monthly gamma isotopic analyses were noted. According to the licensee's records, radiciodine sampling was conducted: (1) at 1 cast every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> during power operation, (2) within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> subsequent to reactor startup uhen the 1-131 dose equivalent concentration prior to shutdown had been between 1% and 10% of the 5,4Ci/gm technical specification Ifmit, and (3) prior to
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reactor startup when the 1-131 dose equivalent concentration prior
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to chutdown had been greater than 10% of the 5 pCi/gm limit. The reactor coolant radiofodine concentration (I-131 dose equivalent)
averaged less than 10% of the technical specification limit; the maximum radiciodine concentration was 3 css than 20% of the technical specification limit.
Radiodine surveillance during 1975 was not dependent upon air ejector monitor increases.
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