IR 05000317/1990031

Insp Repts 50-317/90-31 & 50-318/90-31 on 901029-1102.No Violations Noted.Major Areas Inspected:Radiological Environmental Monitoring,Transportation & Solid Radioactive Waste Programs,Including Mgt Controls,Audits

ML20216K163
Person / Time
Site:	Calvert Cliffs
Issue date:	11/08/1990
From:	Bores R, Joseph Furia, Jang J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20216K157	List: IR 05000317/1990031 ML20216K154
References
50-317-90-31, 50-318-90-31, NUDOCS 9011200082
Download: ML20216K163 (14)

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U.S. NUCLEAR REGULATORY COMMISSION REGION 1 50-317/90 31 Report No /90-31

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50 317 Docket N i DPR 53 License N DPR-69 Licensee: Baltimore Gas and Electric Comnany Post Office Box 1475 Baltimore. Maryland 21203 Facility Name: Calveri Cliffs Nuclear Power Plant. Units 1 and 2 Inspection At: Calvert Cliffs Site and BG&E Electric Test Department Laboratory inspection Conducted: October 29 - November 2. 1990 g

Inspectors: "'M UY .

~L v/iho J. Furia, Senior Radiation Specialist, Facilities

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date Radiological Protection Section (FRPS), Facilities Radiological Safety and Safeguards Branch (FRSSB),

Division of Radiation Safety and Safeguards (DRSS) .

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' Jang, Senior Radiation Sppalist, Effluents ' date RadiationProtectionSection(ERPS),FRSSB,DRSS

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Approved by: s // '99-P@

R.BoreyChief,ERPS,FRSSB,DRSS date insoection Summary: Inspection on Oct2ber 29 - November 2. If90 (Combined Inspection Report Nos. 50-317/90 31: 50-318/90-31)

Areas Inspected: Routine, unannounced inspection of the Radiological '

Environmental Monitoring, transportation and solid radioactive waste programs including: management controls, audits, quality assurance, and implementation of the above programs, Results: Within the areas inspected, no v_iolations or deviations were noted.

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l DETAILS 1. Personnel Contacted 1.1 Licensee Personnel i

L. Bartel, Sr. Radiochemist, Chemical Engineering & Test Laboratory l J. Brown, Training Instructor j

• S. Cowne, Senior Engineer, Quality Assurance Auditing

• P. Crinigan, General Supervisor, Chemistry  !

• M. Gavrilas, Environmental Scientist -

S. Hutson. Health Physicist

• P. Katz, Superintendent, Technical Support

• J. Lenhart, Superviser, Materials Processing

• M. Milbrandt, Compliance Engineer

• G. Phair, Assistant General Supervisor, Radiation Control & Support E. Reichert, Principal Engineer, Chemical Engineering & Test Laboratory R. Sheran, Auxiliary Operator

• J. Szymkowiak, Chemical Analyst, Chemistry Service

• J. Thorp, General Supervisor, Nuclear Operations Support ,

• B. Watson, Plant Health Physicist  :

1.2 NRC Personnel T. Kim, Resident inspector

• A. Howe, Resident Inspector

• Denotes those present at the exit interview-on November 2, 199 . Puroose The purpose of this routine inspection was to review the licensee's programs for the followin Preparation,~ packaging and transportation of radioaciti materials

- Conducting the Radiological Environmental Monitoring Program (RE.4P)

- Conducting the Meteorological Monitoring Program 3. Previously Identified Items

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(Closed) 50-317/88-29-01;50-318/88-29-01 and 50-317/89-24-02;50-318/89-25-02 (Repeat Violation) Failure to correlate scaling factors with current plant samples. The licensee revised Procedure CP-228, and has taken, analyzed and provided to the Materials Processing staff scaling factors for Dry Active Waste (DAW) on a semiannual basis, and for spen; '

resin on an annual basis. This item is close .

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(Closed) 50 317/88 29 03:50-318/88-29-03 and 50-317/89 24 01;50-318/89-2501(RepeatViolation) Failure to properly quantify isotopes on waste matifest. The licensee has revised Procedure RSP 2-204 for waste shipments and written a new Procedure RSP 2-207 for waste classificatio In addition, the licensee now utilizes the RADMAN c smputer code, which greatly reduces the chances for calculational trrors on manifests. This item is close . Transportation and Radwaste Processing, packaging and transportation of radwaste and other radioactive materials were the responsibility of the Radiation Safety Section, whose General Supervisor reports to the Superintendent for Technical Support. Within the Radiation Safety Section, the Supervisor, Materials Processing was responsible for the operation of the Materials ProcessingFacility(MPF),andthustaskedwithpreparingradioactive materials for shipmen .1 Radwaste j The plant processed primary plant water through ion exchangers and i filters, waste water from floor and equi > ment drains through !

demineralizers, and collected DAW throug1out the plant. Spent resins were dewatered in polyethylene High Integrity Containers (poly-HICs), as were spent filter cartridges. DAW was compacted at the Materials l

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Processing facility (MPF) and then shipped to SEG (a Westinghouse !

subsidiary) for sorting and ultimate disposal via incineration or supercompaction. Additionally, during tie past year, the licensee made several shipments of irradiated hardware for disposal, and one shipment of spent fuel and hardware to Canad '

As part of this inspection, the inspector reviewed the following procedures utilized in the processing, packaging and shipment of radwaste and radioactive materia .VP 2-202, Rev 3, " Low Level Solid Radioactive Waste Control"

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RSP 2-204, Rev 5, " Packaging, Labeling and Shipment of Radioactive !

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l' Materials" RSP 2-206, Rev 6, " Chem-Nuclear CNSI l-13G Cask Handling" ,

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RSP 2-207, Rev 0, " Radioactive Waste Classification"  !

RSP 2-209.. Rev 0, " Radioactive Material Characterization" '

l RSP 2-217, Rev 0, "CNSI High Integrity Container Handling and Loading Procedure" L

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RSP 2-220, Rev 2, * Solid Waste Processing Resin Transfer" These procedures were determined to be complete and to accurately ,

reflect plant operations in this are l

Scaling factors for hard to detect isotopes were typically determined on l an annual basis for resins and filters, and on a semiannual basis for DAW, by the submission of representative composite samples to Teledyne 1 Isotopes, Inc. These results were then analyzed by the licensee and a l contractor, Bland Associates, to determine the waste stream specific l scaling factors to be used.

3 The licensee had recently begun taking action to correct deficiencies in the plant radwaste system which led to resin infiltration into the plant waste vent monitoring system and the Waste Monitoring Tank. Resins and water had been detected in the Plant Waste Vent Monitor 0-RE-2191 for -

several years. Recently, 37 55-gallon barrels of sludge were removed from Waste Monitoring Tank 12, and this sludge consisted primarily of resins. The source of this resin appeared to be one or more of the various ion exchangers, demineralizers or the Spent Resin Metering Tan Based upon the above events, the licensee was investigating methods for cleaning out the plant waste vent system and preventing further intrusion of resins from the various sources in the plant. Preliminary actions taken by the licensee appear adequate to prevent further intrusions of resin into this vent system. The results of long-term actions taken to decontaminate the vent system will be reviewed during a future inspectio .2 Transportation l

Packaging and shipping of all radioactive materials, including radwaste l were the responsibility of the Materials Processing staff within the Radiation Safety Section. As part of this inspection, the following 20 shipping records for materials shipped in 1990 were reviewe Shioment Activity (Ci) Volume (cu ft) lyst i

90-060 3.52E-02 99 Laundrf 90-061 3.23E-02 90 Laundr/

90-062 3.71E-01 90 DAW 90 064 9.26E+04 3 Spent fuel 90-065 3.28E+01 12 Resi's90-066 5.41E-03 18 Equipment 90-067 7.60E-08 < Samples 90 068 3.75E-02 90 Laundry 90-069 2.87E+00 4 Equipment 90-070' 3.41E-02 90 Laundry 90 071 1.52E+03 1 Irradiated Metal 90-072 2.57E-02 63 Laundry ,

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4 1 Shioment Activity (C1) Volume (cu ft) Lp1 90-073 9.48E-07 < Samples90-074 1.28E+03 1 Irradiated Metal 90-075 3.98E 02 99 Laundry 90-076 3.30E 02 81 Laundry 90-077 1.09E+00 99 DAW 90-078 4.70E-03 9 Equipment 90-079 1.60E-04 < Samples90-080 1.65E 02 45 Laundry & DAW ;

All records were determined to meet the regulatory requirements as set forth in Titles 10 and 49, Code of Federal Regulation .3 Interim Radwaste Storaae In preparation for possible exclusion from the existing burial sites in 1993, as allowed under the Low level Waste Policy Act of 1980 and the Low-Level Waste Policy Amendments Act of 1985, the licensee had built a storage area as ) art of the MPF, with a storage capacity for packaged DAW of 75,000 cu)ic feet. The possible storage of spent resins and filters in HICs, which are then ) laced in On Site Storage Containers (OSSCs), was being examined at tie time of this inspection. The

. licensee had budgeted, beginning in 1992, for the purchase of OSSCs and the construction of a storage area within the owner controlled area of the plan ,

4.4 Ouality Assurance The licensee's program for the assurance of quality in the radwaste and transportation areas involved the evaluating principal vendors supporting this area, plant audits of this area, and quality control review of all shipments of radwaste and principle radwaste evolution Vendor evalhetions were conducted by the licensee's Vendor Quality Assurance group. The evaluation of CNSI, which supplies liners and shipping casks to the licensee, was conducted by representatives of the

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Wolf Creek Nuclear Generating Station, on behalf on the Nuclear

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Procurement Issues Council (NVPIC), of which the licensee was a membe All pertinent records related to this audit were maintained by the

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license Audits of'the plant radwaste and transportation program were conducted 3 on an biennial basis. Audit 89-20, dated November 7, 1989, was the most recent audit in this area. All findings as a result of this audit' we ,

addressed and resolved. The inspector had no further questions in this i are .

Quality Control (QC) observed most radwaste shipments and major ;

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evolutions, and documented these observations in the shipment records maintained by the Materials Processing group. The inspector had no further questions in this are .

4.5 Trainino Training of Materials Processing personnel to meet the requirements of NRC IE Bulletin 79-19 was conducted on a continuing basis as part of continuing training for Health Physics Technicians. In addition, the licensee had a vendor, WMG, Inc., come on site and present three i

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training programs on radwaste and transportation. Supervisory personnel were also in attendance at this course. The inspector had no further questions in this are . Radioloaical Environmental Monitorina Proaram (REMP)

, Proaram Chances The inspector. reviewed the licensee's organization for the management of- l the REMP. There were no significant changes in the licensee's REMP !

since the previous inspection conducted in September 1989, i

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5.2 Direct Observations The inspector examined various environmental sampling stations. These stations included air particulate ar.d iodine samplers, thermoluminescent dosimeter (TLD) stations, a milk sampling station, and the broad leaf vegetation gardens. All air sampling equipment was operational and TLDs were placed at the specified locations.- The licensee was not able to *-

obtain milk samples from the farm because the farmer would not cooperate with the licensee. The licensee, therefore, collected and analyzed grass samples around the farm :The broad leaf vegetation samples were available at the garden as specified by the Offsite Dose Calculation Manual (ODCM). The inspector noted that the licensee had its own i vegetable gardens to ensure sufficient sample collection at the required frequencie .3 Review of Annual Report

.The inspector reviewed the Annual Radiological Environmental Report for 1989. This report provided a comprehensive summary of the results of '

the REMP around the Calvert Cliffs site and met the Technical Specification requirements. No violations were identifie .4 Review of Other Reports The inspector reviewed the following reports relate to the REM ___ _ __

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- Calvert Cliffs Nuclear Power Plant Routine Operation REMP Perspective, May 1989 -

- REMP around Calvert Cliffs Nuclear Power Plant, August 1990

- Compilation and Graphical Display of Age-Adjusted Cancer Mortality Rates for Maryland Counties, August 1990 The above reports were prepared by the Environmental Scientist who has ,

responsibility for the REMP, and were published by the Environmental ,

Programs, Baltimore Gas and Electric Company. These re: orts were an .

excellent raflection of the licensee's utilization of tie REMP on a !

broad scope and in use of their technical expertise to go well beyond the regulatory requirements in their assessment .5 Imolementation of the REMP The inspector reviewed the licensee's REMP to determine whether the ;

program described in the Technical Specifications was effectively implemented. The areas reviewed included maintenance and calibration .

records of air samplers, sampling frequency, sampling techniques for environmental media, and the REMP-plan. All-reviewed areas exceeded the licensee's Tcchnical Specification requirements. It was noteworthy that the licensee installed a new air sampling station during 1990.- The inspector examined this equipment and noted that the new equipment had a capability to draw a larger air volume resulting in more representative '

samples. -The inspector also noted that the new air sampling equipment ran very quietly. The new equipment was mounted on thick rubber pads to absorb the motor vibration to minimize any malfuaction due to the vibration, a fairly _ common problem. The inspector stated that the new equipment appeared to be well suited for the REMP. Based on the above

, review, the inspector concluded that the licensee implemented an excellent REM No violations were identified, r Ouality Control Proaram for the REMP Analytical Measurements

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The quality control of analytical measurements was conducted by a contractor laboratory, BG&E Electric Test Department Laboratory. This a laboratory participated in the EPA cross-check program and also conducted internal quality control programs such as split and blind sample analyses. The inspector reviewed quality control data for source ,

checks and backgrounds for gamma spectrometry systems, liquid scintillation counter, and low bac(ground gas flow proportional counter, including QA control charts. Based on the above review, the inspector determined that the licensee conducted an excellent QC program for analytical measurements. No violations were identifie ,

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6. Meteoroloaical Monitorina Proaram ,

The inspector reviewed the licensee's meteorological monitoring program ,

to determine whether the instrumentation and equipment were operable, calibrated and maintained. The inspector also reviewed the most recent calibration results for wind speed, wind direction, and the delta temperature at the 60 meter and 10-meter elevation levels. All results h reviewed were within the licenses's acceptance criteria. Comparisons of parameters between the monitoring station (trailer) at the tower and the-control room were conducted and the results were in agreemen The inspector noted that the licensee planned to install a permanent station at the tower in the near future. ~The inspector stated that the replccement of the trailer would be beneficial to the program because the equipment room temperature could be more easily controlle The inspector stated that the new facility or progiess status for the facility will be reviewed during a subsequent inspection. No violations were identifie . Exit Interview The inspectors met with the licensee representatives denoted in Section 1 at the conclusion of the inspection on November 2, 1990. The inspectors summarized the purpose, scope and findings of the inspection, r i

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REPORT HOURS 1. Operations' 7. Outages 2. Rad-Con n 8. Training ,

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Reoort hours: Enter report hours for each 5 ALP area addressed in the inspection repor . .

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t Docket e Insert 5 digit hyphenated, e.g. 50 219. or the 6 digit non. hyphenated, e.g., m20ll, docket number in the spaces provide Item Number The first E spaces include a hyphen and are the same as the report number, e.g., 76 d. This portion of the item number is the same for all items ioentified in a given

report and is only filled in once per page although WPC will inter this portion in all items on the page. The last two digits are assigned when documenting the item within a given report and start with 01 and continue sequentially until all items reaviring followup have been identifie Ae T - Enter the 3 letter coce SLI through SLV to indicate noncompliance severity leve If, Deviation. UNR - UhFesolved. C0F - Construction Deficiency Reports. Lil - Other Licensee Identified items (hete: matters identified by the licensee should be entered g_ nix if there is safety or safety guards significance requiring followup action), inspector followup items are coced IFl anc are used when an item to be followed up does not fall in one of the coding categories above. NV4 and hv5 - ho violation issued and Severity Level 4 or $ ALP Area: Enter the SALP area of the outstanding ite Area Code - Enter the 3 letter code that best characterizes the Functional Area into which the item wou'Id fal CEP - Construction Environment Protection PAC - Material Accountability / Control COA - Constructica Quality Assurance OEP - Operations Environmental Protection CAS - Concrete and Structures 00A - Operations Ovality Assurance FDP - Fire Detection /Prever. tion LRT - Leak Fate lestirg FhD - FouN0ations FN1 Maintenance

!!! - In$ervice Inspection POT Pre 0peration Testing ,

PSC - Procedures. SLrveillance. Calibratier !

!$7 - In$crvice lestire. Pr s A Vches N M - honDestructive lesting REF - Refueling activities RVI - Reactor Vessel and Internals hf5 - Reactor fuel Shipping

$NB - Snubbers TRN - Training i SME - Special Mechanical / Electrical Problem EFP - Emergency Plans and Procedures WLD - Welding IMV - Independent Measurements Van FFH - Fuel Fabrication and Handling RDP - Radiation Protection FN$ - Fbel facility huclear Safety INV - INiestigations Ph5 - Preparation of Materials for Shipment SPP - Security and Physical Protection (used for fuel / reprocessing only) OTh - OTher speciality, not coded elsewhere Resp - Enter the specific cooe which identifies the section with responsibiliy to perform inspection follow u A. Materials Assurance Section 6. Division of Reactor Projects I 8. Quality Assurance Section H. Effluents Rad. Protection Section C. Test Programs Section 1. Facilities Red. Protection Section  !

D. Operational Programs Section J. Emergency Preparedness Section E. Materials and Processes Section K. Plant Protection Section

.F. Plant Systems Section l Action Due Date - Enter the date by which hRC followup should be completed. (Typically 3 months; Update /Closecut Report # - The first 5 positions correspond to the report number, e.g., 86 0 The position following the second hyphen is filled with a *C" if the item was reinspected and Closed or was opened and closed within the same inspection. An '0" is inserted if the item tas reinspected and remains Outstandin Date item was opened, modified or close !

Originator - Last name of individual establishing a new ite Modifier - Last name of individual making a modification to an existing ite Descriptive Title: A description of 123 or less characters, the module number may be included, if desire Region 1 Fom 6 (Side 2)

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I I I I l l 'l i i l i l i i l i I I i i l i I I I I I I I I I I I I I I I I I I I l i I I I I I I I I I I I I I I I I I I I I l ,

i I L i l! I I I I I l l l l l l 1 I i i i I i i i l i I I I I I I I I I I Item Number Type SALP Area Area Action Due Date Updt/Cisout Rpt/ Date 0/M/Cisd i I l-i i 1-1 l l l l1 IIIIIIIIIII IIII I I l-l I l-1 I I I I l-l I l-l l I I I l-l I l-1 1 MM DD YY MM DD YY Originator / Modifier -Resp Sec l l 1 I I l l l l l l 1 i Descriptive Title i i l l l -l l' I L l l l 1 1 I I I I I I I I I I I I I I I l- 1 I I I l 1 1 I F I '

I I I I I I I I I I I I l l I I 1 1 I I I I I

[ l i I i l ! I L I I I I I I I I I I I I l i I l i I I I I I I I I I Item Number Type SALP A &.2 Area Action Due Date Updt/C1sout Rpt/ Date 0/M/Cisd i I ;-l i 1-1 1-1 I II Iilill IIIII IIII I I l-l I l-l i I I I l-l I l-l i I I I l-1 I l-l 1 MM DD YY MM DD Y1 Originator / Modifier Resp Sec I a I i l- 1 I I I I I i i Descriptive Title i I '

i l I I I I I i l I I I I I i 1 1 I I I I I L I I i i I ll I!

l l l- 1 I i i l i l i i I i l l I I I I l ! I I H I I I I I I l- l 1 I I I I l- 1 I I I I I I I I I I I I I I I I I I l ll 1 1 I I I I I Region I Form 6 i (January 1987)

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Report hours: Enter report hours for each SALP area addressed in the inspection repor . .

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Docket # - Insert 5 digit hyphenated, e.g. 50 219 or the 6 digit non. hyphenate .

e.g., m2011. docket number in the spaces provide Item Number The first ! spaces include a hyphen and are the same as the report number, e.g., 76 19. This portion of the itte number is the same for all items identified in a given report and is only filled in once per page although WPC will enter this portion in all items on the page. The last two digits are assigned when documenting the item within a given report and start with 01 and continue sequentially until all items recuiring followup have been identifie ate - Enter the 3 letter coce SLI through SLV to indicate noncompliance severity leve DIVistion. UNR UhFesolved. CDF - Construction Deficiency Reports. Lil - Other License?

Identified items (hote: matters identified by the licensee should be entered Joni if there is -

safety or safety guards significance requiring followup action). Inspector foTTowup items are coced IF1 and tre used when en item to be followed up does not fall in one of the coding categories above. NV4 and hVS - ho violation issued and Severity Level 4 or SALP Area: Enter the SALP area of the outstanding ite Area Code - Enter the 3 letter code that best characterizes the Functional Area into which the item would fal CEP - Construction Environment Protection PAC - Material Accountability / Control COA Construction Quality Assurance OEP Operations Environmental Protection CAS - Concrete and Structures OCA Operations Quality Assurance FDP - Fire betection/Prevertion LRT - Leal Fate Testing FND - Foundations PNT - MaiKienance

!!! - Inservice Inspection POT - PreDperation Testing IST - In$ervice Testirc. Pu :s 1. Ychts PSC - Procedures. SLrveillance. Calibratier hti - honDestructive Testing REF EEFueling activities RV! - Reactor Vessel and Internals kFS - Reactor Fuel Shipping SNB - Snubbers TRN - TRaihing )

SME - Special Mechanical / Electrical Problem EPP - Emergency Plans and Procedures WLD - WeL0ing IMY - Independent Measurements Van FFH - Fuel Fabrication and Handling RDP Radiation Protection FNS - Fuel Facility huclear Safety INV - thiestigations PMS - Preparation of Materials for Shipment SPP - Security and Fhysical Protection (used for fuel / reprocessing only) 01h - 0THer speciality, not coded elsewhere i i

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Resp Enter the specific coce which identifies the section with responsibiliy to perfonn inspection follow u A. Materials Assurance Section 6. Division of Reactor Projects B. Quality Assurance Section H. Effluents Rad. Protection Sectio C. Test Programs Section 1. Facilities Rad. Protection Se: tion D. Operational Programs Section J. Emergency Preparedness Section E. Materials and Processes Section K. Plant Protection Section F. Plant Systems Section Action Due Date - Enter the date by which hRC followup should be completed. (Typically 3 months)

Update /Closecut Report # - 1he first 5 positions correspond to the report number, e.g., 86-0 The position following the second hyphen is filled with a *C" if the item was reinspected and

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l Closed or was opened and closed within the same inspection. An "0" is inserted if the item

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was reinspected and remains Outstandin Date item was opened, modified or close Originator - Last name of individual establishing a new ite Modifier - Last name of individual making a modification to an existing ite Descriptive Title: A description of 123 or less characters, the module number may be included, fi desired.

l Region 1 Fonn 6 (Side 2)

(January 1957)

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