IR 05000295/1979003
| ML19289F110 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 04/03/1979 |
| From: | Essig T, Oestmann M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19289F108 | List: |
| References | |
| 50-295-79-03, 50-295-79-3, 50-304-79-03, 50-304-79-3, NUDOCS 7906020065 | |
| Download: ML19289F110 (10) | |
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i U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-295/79-03; 50-304/79-03 Docket No. 50-295; 50-304 License No. DPR-39; DPR-48 Licensee:
Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility Name:
Zion Nuclear Power Station, Units 1 and 2 Inspection At:
Zion Site, Zion, IL Inspection Conducted: March 12-16, 1979
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Inspector:
M.
. Oestmann
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m bA Approved By:
T. H.
.sig, Chief 3!"7 f
[ Environmental and Special Projects Section Inspection Summary:
Inspection on March 12-16, 1979 (Report No. 50-295/79-03; 50-304/79-03)
Areas Inspected:
Routine, unannounced inspection of (1) emergency planning activities for Units I and 2, including:
review of Generating Stations Emergency Plan (GSEP) and implementing procedures (EPIP's);
coordination with offsite support agencies; emergency facilities, equip-ment and supplies; radioactive effluent monitoring systems and survey instruments; medical arrangements; emergency training; tests and drills; and (2) confirmatory measurements inspection, including evaluation of the licensee's analytical results of effluent samples obtained from a previous inspection and licensee's program for quality control of analytical measurements.
The inspection involved 31 inspector-hours on site by one NRC inspector.
Results: For the ten areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees V. Chaney, GSEP Coordinator, Corporate Headquarters F. Palmer, CSEP Command Center Director, Corporate Headquarters W. Sallers, Quality Assurance Engineer, Corporate Headquarters
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Wandke, Station Superintendent, Zion Station
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Soth, Administrative Assistant, Zion Station S. Miller, Rad / Chem Supervisor, Zion Station
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Rescek, Lead Health Physicist, Zion Station
- S.
Gurunathan, Lead Chemist, Zion Station
- P. Kuhner, Qualtity Assurance Engineer, Zion Station F. Ost, Health Physics Technician, Zion Station C. Schultz, Training Supervisor, Zion Station The inspector also interviewed 13 other licensee employees during the course of the inspection.
They included training personnel, chemistry and health physics technicians, members of the security force, and general office personnel.
- Denotes those present at the exit interview.
Other Personnel N. Lee, Chief of Police, Zion Police Department D. Koetz, Coordinator, Zion Emergency and Disaster Agency Dr. H. J. Solomon, Director, Zion Rescue Squad f. Poulsen, Assistant Chief, Zion Rescue Squad G. Mencer, Fire Chief, Zion Fire Department E. Loscar, Manager, Safeway Ambulance Service M. Marineau, Assistant, Safeway Ambulance Service J. Wasson, Administrator, Victory Memorial Hospital R. Willer, Coordinator, Lake County Emergency Services and Disaster Agency J. Donaldson, Deputy Sheriff, Lake County Sheriff's Department F. Bronson, Vice President, Radiation Management Corporation 2.
Generating Stations Emergency Plan (GSEP) and Implementing Procedures (EPIPs)
The inspector reviewed the licensee's GSEP, dated December 1977, and 19 EPIPs which were updated during 1978.
The licensee conducted an annual review of the CSEP on February 22, 1979, and determined that no major changes were required at this time. During examination of 2236 223-2-
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the revised EPIPs, the inspector noted that the ' licensee did not
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include a list in EPIP 500-3 of the first aid supplies and decon-tamination facilities located at the Victory Memorial Hospital, which the licensee is responsible for.
This item will be examined during a subsequent inspection.
The inspector also verified that distribution of the GSEP and the revised EPIPs had been made to appropriate onsite and offsite personnel.
No items of noncompliance or deviations were identified.
3.
Agreement and Coordination with Of fsite Support Agencies The inspector visited or contacted those representatives of offsite emergency support groups identified in Paragraph 1 above. The inspector discussed the degree of licensee coordination with these representatives, including planned meetings, training sessions, and participation in drills and exercises.
In general, these dis-cussions verified that existing agreements between the licensee and the agencies remain in ef fect and that the licensee's coordination was adequate for these agencies to maintain an effective response capability.
However, the inspector observed that the emergency staff at the Victory Memorial Hospital appeared to lack familiarization with the licensee's GSEP and emergency arrangements. Also, a copy of the GSEP or the licensee's medical procedures could not be located. This apparently inadequate f amiliarization training provided by the licensee for the emergency staff at the hospital is considered an unresolved item.
The inspector also reviewed 13 letters of agreement from prime support agencies and found them to be current.
The licensee also held an annual training session on December 1, 1978, with representatives from these agencies as required by Section 3.5.3 of the GSEP. Training was also provided for representatives from selected offsite support agencies through participation in the medical drill held under the supervision of Radiation Management Corporation (the licensee's contractor) in May 1978.
No items of noncoupliance of deviations were identified.
4.
Emergency Facilities, Equipment and Supplies Emergency facilities, equipment and supplies identified in the licensee's EPIP 500-3, and Appendix B for the Zion Station emergency trailer, both cated May 1978, were examined by the inspector to verify items specified in the procedures were available for use and maintained in an operable state.
Items inspected included first aid kits and decontamination facilities, portable survey meters and 2236 224-3-
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radiation detectors, stretchers, respiratory equipment, and other radiological emergency supplies. The inspector examined these items each at five different locations throughout the reactor building complex and the emergency trailer. Except for minor discrepancies of a few items missing from one first aid kit, all materials and supplies were found located as described in EPIP 500-3 and Appendix B.
Emergency survey meters, which are calibrated on a quarterly schedule, were also found to have current calibration tags.
Housekeeping of the Zion emergency trailer was observed to be poor, with many af the trailer contents loose on the counter.
Securing this equipment would delay using the trailer in the event of an emergency.
A licensea representative agreed that the contents should be secured and the trailer straightened up.
The inspector also determined that the licensee conducted monthly checks of the mobile trailer radio communcations with the control roor. This iter. was identified in a previous inspectiva report 1/ as an area needing attention.
The inspector also examined inventory records and calibration checks for 1979 to date as required in accordance with EPIP 500-3.
(Records of these activities for 1978 were being microfilmed at the time of this inspection and were not available for review). First aid kits, emergency radiation detectors, and operability of respiratory equip-ment were included. The inspector determined that the licensee conducted the inventories on schedule and had corrected any discre-pancies found.
No items of noncompliance or deviations were identified.
5.
Radioactive Ef fluent Monitoring Systems and Survey Meters Selected portable survey meters, stack and ventilation, and liquid ef fluent monitors were checked for operability and calibration.
The instrumentation viewed was found to be operable and located as specified.
During a tour of the control room, the inspector also observed readout equipmen; for wind speed and direction taken from a vane on top of the Unit 1 containment building. Meteorological data from the meteorological tower are also reported at the base of the tower, transmitted to the licensee's corporate headquarters and checked daily by the licensee corporate personnel.
During an emergency the licensee would utilize the real time meteorological data taken from the tower to more accurately determine the offsite consequences of the effluent release.
Decisional aids, including communication lists, maps and other items were found where specified.
No items of noncompliance or deviations were identified.
1/ IE Inspection Rpt. No. 50-295/78-07; 50-304/78-07.
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6.
Medical Arrangements The inspection included examination of the medical treatment f acilities at the plant site and at the offsite hospital and ambulance services.
The onsite first aid and personnel decontamination facility was found to be maintained in accord with EPIP 500-3.
The offsite treatment facility at the Victory Memorial Hospital, however, was fumd to be disorderly and disorganized.
Emergency supplies contained in large plastic bags were not placed in appropriate locations.
Several shipping boxes containing foot lockers were found in the room.
The emergency supplies, located in the decontamination-radiation room were in good order. The condition of the treatment room was brought to the attention of the licensee's management during the exit interview and will be examined during a subsequent inspection.
The inspector also determined during review of selected training records that the licensee had given radiation protection personnel an annual first aid training and retraining program as required by Section 6.4 of GSEP.
The inspector also determined during a review of ambulance services used by the licensee that the local rescue squad is seldom used for actual emergency situations.
Instead, a private ambulance service located in Waukegan, which is about ten miles away, is used. The local ambulance service has paramedic trained personnel, while the ambulance service in Waukegan has only emergency medical trained personnel.
This item was discussed with licensee representatives and will be examined during a subsequent inspection.
No items of noncompliance or deviations were identified in this area.
7.
Training for Emergencies The inspector reviewed internal memorandum and records (for CY 1978)
of training and retraining of selected station and corporate personnel which indicated that such training for specific GSEP positions had been provided to the required personnel in accord with requirements in Section 9.3.1 of GSEP.
Records of orientation training (for CY 1978)
which include GSEP duties and responsibilities to new employees and contracto rs to obtain identification badges each year were also reviewed.
The licensee also conducted a coordination meeting with offsite support agency personnel on December 1, 1978 to discuss the role each agency plays in the event of an emergency. A meeting was also held in July 1978 between the Zion Fire Department and station personnel. A video tape taken of the medical drill held in May 1978 has also been used for training purposes at the local hospital and also for the licensee personnel.
No items of noncompliance or deviations were identified.
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8.
Tests and Drills The inspector examined documentation pertaining to conduct and evaluation of the GSEP tests and drills during 1978. Quarterly drills were completed as required and critiqued by the GSEP coordi-nator for identification of problems.
No items of noncompliance or deviations were identified.
9.
Licensee Internal Audits The inspector reviewed the results of internal audits during 1978 which included the GSEP and EPIPs. An audit conducted on June 20, 1978, indicated no deviations from program requirements; however, it did recommend actions to be taken to improve emergency preparedness, i.e., more conspicuously displaying first aid kits and conduct monthly kit inventories. The inspector determined during a tour of the reactor complex that these actions had been accomplished.
No items of noncompliance or deviations were identified.
10.
Licensee's Program for Quality Assurance and Quality Control of Analytical Measurements a.
Nonradiological Analysis of Reactor Coolant The inspector reviewed selected licensee laboratory procedures for nonradiological effluent and chemical analysis of reactor coolant to determine their adequacy and completeness. Procedures reviewed covered analysis of chlorides, ammonia, morpholine, hydrazine, conductivity, and pH, and sampling procedures.
All procedures had been reviewed by the lead chemist during the first quarter of 1979 to assure that they were current and deemed technically adequate.
The inspector also toured the licensee's nonradiological chemistry laboratory and observed that all laboratory instruments appeared to be functional and operable and chemical solutions dated currently.
Calibrations of laboratory instruments are verified on a monthly schedule.
No technical weaknesses were observed.
The inspector also examined selected logs, check sheets and other records of analytical results (for the period January 1, 1979 to date) which are reviewed daily by the lead chemist (as was the case with the records discussed in Paragraph 4, records of these activities were also being microfilced). Licensee management is also informed of any unusual results.
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b.
Radiological Analysis of Reactor Coolant and Effluent Samples Selected reactor coolant and radiological effluent procedures reviewed by the inspector pertained to radiochemical separations and analysis of radionuclides and counting room procedures.
These procedures had been reviewed in the first quarter of 1979 by the licensee to assure they are kept up to date and are acceptable. The inspector also noted that the licensee calibrates his gemma spectrometer system on an annual basis and maintains daily checks of energy calibrations.
A tour of the licensee's radiological chemistry laboratory revealed no major problem areas.
Selected results of recent quality and functional checks of the licensee's multichannel analyzers were reviewed by the inspector for the period January 1,1979 to date.
(Records for 1978 were being microfilmed). All checks required by the procedures were conducted and recorded. The inspector also examined logs, and check sheets resulting from the licensee's quality assurance activities which reflect ed adherence to procedural controls.
The licensee performed frequent background counts and checks on each of the instruments currently in use for the confirmatory measurements program.
Acceptance criteria have been established and properly documented.
c.
Training of Chemistry Laboratory Personnel Programs for training chemistry laboratory personnel were discussed with the licensee. A formal program includes a one-week orientation; a five-week system description of plant operation; and a fourteen-week radiation laboratory training program, including theory, and hands-on laboratory experience. Laboratory personnel are given examinations during the six-month formal training period. Licensee's training program and chemical and radiochemical laboratory practices appeared to be adequate.
d.
Quality Control of Laboratory Operations The inspector also examined the licensee's quality control procedures for nonradiological and radiological measurements, including performance checks and calibrations of chemical and radiation counting equipment. The licensee explained that the program has been established to check the laboratory technician's results of reactor coolant chemistry by means of spikes and blind samples. The licensee has procedures which contain criteria for accepting measurement results and which require notification when deficiencies are noted. The inspector noted no problems relative to notification of management of program deficiencies and unusual results.
No items of noncompliance or deviations were identified.
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11.
Results of Comparative Analyses Results of comparative analyses performed on effluent samples collected at the site in May 1978 for the Confirmatory Measurements program are shown in Table 1.
The criteria for comparing measurement results are given in Attachment 1.
The results were discussed with the licensee.
For seven comparisons, the liceensee's results yielded four disagree-ments, viz., gross beta activity, cobalt-60 and cesium-134 in liquid waste and xenon-133 in gaseous waste samples were not properly quantified. The licensee stated that attempts were being made to resolve the differences in the xenon gaseous activity in having the National Bureau of Standards measure activity in the same sample measured by the licensee; however, no explanation for the disagreement in results for this particular sample was apparent. Also, no reason for the disagree-ment relative to the gross beta activity was apparent.
If the disagreements for xenon-133 in gas samples and gross beta activity were real and representative of routine analyses, the licensee could have over-estimated releases of xenon-133 and gross beta activity at the time of this comparison.
The licensee also f ailed to determine the presence of cobalt-60 and cesium-134 in the liquid waste. No reason for these discrepancies was apparent af ter review of the licensee's data and discussion with the licensee representatives. Arrangements are being made to provide the licensee with spiked liquid, particulate filter and charcoal adsorber samples as a further test of the licensee's analytical capability.
12.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.
An unresolved item disclosed during the inspection is discussed in Paragraph 3.
13.
Exit Inte rview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of this inspection on March 16, 1979.
The inspector summarized the purpose and scope of this inspection and its findings.
The licensee stated that he would investigate the status of the emergency treatment room at the Victory Memorial Hospital and the lack of familiarization of the emergency staff at the hospital of existence of GSEP and his medical procedures. He also stated that he would continue to investigate the reasons for disagreements in the Confirmatory Measurements Program.
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Attachments:
1.
Confirmatory Measurements Program, Zion Station 2.
Attachment 1, Criteria for Comparing Analytical Measurements-8-2236 229
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ATTActrit:T 1 CRITERI A FOR COMPARING ANALYTICAL MEASURC!ENTS
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This attachment provides criteria for comparing results of capability tests and verification measurements.
The criteria are based on an
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empirical relationship which combines prior experience and the accuracy needs of this program.
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In these criteria, the judgment limits are variable in relation to the comparison of the NRC Refetence Laboratory's value to its associated one sigma uncertainty. As that ratio, referred to in this program as
." Resolution", increases, the acceptability of a licensee's measurement should be more selective.
Conversely, poorer agreement should be con-sidered acceptable as the resolution decreases.
The values in the ratio criteria may be rounded to fewer significant figures to maintain statistical consistency with the number of significant figures reported by the NRC Reference Laboratory, unless such rounding vill result in a
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narrowed category of acceptance.
The acceptance category reported will be the narrowest into which the ratio fits for the resolution being used.
RESOLUTION RATIO = LICENSEE VALUE/NRC REFERENCE VALUE
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Possible Possible
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Agreement Agreement "A" Agreeabic "B"
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No Comparison No Comparison No Comparison
>3 and <4 0.4 -
2.5 0.3 3.0 No Comparison
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T4 and <8 0.5 -
2.0 0.4
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2.5 0.3
- 3.0 78 and <16 0.6 -
1.67 0.5
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2.0 0.4
- 2.5 T16 and <51 0.75 -
1.33 0.6
- 1.67 0.5
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2.0 551 and <200 0.80 -
1.25 0.75 - 1.33 0.6
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}{200 0.85 -
1.18 0.80 - 1.25 0.75 - 1.33
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"A" criteria are applied to the,following analyses:
Camma spectrometry, where principal gamma energy used for identifi-cation is greater than 250 kev.
d Tritium analyses of liquid samples.
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"B" criteria are applied to the following analyses:
Camma spectrometry, where principal gamma energy used for identifi-cation is less than 250 kev.
Sr-89 and Sr-90 determinations.
Gross beta, where sampics are counted on the same date using the same reference nuclide.
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TABLE I m
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U S NUCLE AR REGUL ATORY COMMISSION OFFICE OF INSPECTION AND E NF O R CE ME N T
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. CONFIRMATORY ME ASUREMENTS PROGR AM FACILITY: ZION
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FOR THE 2 OUARTER OF 1978
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--NRC-------
--NRC: LICENSEE----
SAMPLE ISOTOPE RESULT ERROR RESULT ERROR RATIO RES T
OFF G 5S XE 133 6 5E-04 3 0E -05 1 6E -03
2 5E+00 2 2E+01
L WASTE BETA 9 2E-06 3 0E-07 4 3E -0 4
4 7E>01 3 1E+01
- H 3 5 4E-02 1 0 E -0 4 S e 1 E -0 2
9 4E-01 S e4E +02 A
CO 60 4 5 E-0 6 2 4E-07
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1 9E+01 D
SB 124 2 8E-06 3 1E-07 2 4E-06
8 6E-01 9.0E+00 A
0.0
6 0E+00 D
C FILTER I 131 3 7E-02 1 1 E-03 2 3E-02
6 2E-01 3 4E +01 P
T TEST RE S U L T S :
A = A G R E E ME N T p.-D I S A G RE E ME N T p, P O S S I BL E A GREE ME NT p=NO COMPAPISDN 2236 231
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