IR 05000400/1992025
| ML18010A929 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/25/1992 |
| From: | Robert Carrion, Decker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18010A928 | List: |
| References | |
| 50-400-92-25, NUDOCS 9212040328 | |
| Download: ML18010A929 (21) | |
Text
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Report No:
50-400/92-25 UNITED STATES NUCLEAR REGULATORYCOMMtSStON
REGION II
10'I MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 NOII g5 pe Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Shearon Harris Nuclear Power Plant License No.:
NPF-63 D te Signed Inspection Conducted:
October 19 - 23, 1992 A
C Inspector:
li z~ Pz.
R.
P. Carrion, Radiat~iion Specialist Approved by:
'.
R. Decker, Chief D
e S>gned Radiological Effluents and Chemistry Section Radiological Protection and Emergency Preparedness Branch Division of Radiation Safety and Safeguards SUMMARY Scope:
This routine, unannounced inspection was conducted in the areas of organization of the Chemistry Department and the Radwaste Shipping Unit; plant water chemistry; confirmatory measurements of non-radiological chemistry samples; radiological effluents; process and effluent monitors; the post accident sampling systems (PASS); the Spent Fuel Pool (SFP)
clean up status; the Control Room Emergency Ventilation System; and shipping of radwaste and spent fuel.
Results:
The licensee's organization in the areas, of Chemistry and Radioactive Waste was stable and staffed with competent personnel.
(Paragraph 2)
Plant water chemistry was maintained well within Technical Specification (TS)
limits.
(Paragraph 3)
The licensee demonstrated adequate ability to evaluate Non-Radiological chemistry samples for a variety of analytes in the matrix presented by the inspector.
(Paragraph 4)
9212040328 921125 PDR ADOCK 05000400
The licensee had kept releases of radiological effluents well within TS limits and had returned all previously-referenced long term out-of-service TS radiation monitors back to service.
(Paragraph 5)
Process and effluent monitors were well-maintained and liquid and gaseous releases were well within TS limits.
(Paragraph 6)
The licensee had continued to make progress in resolving problems with the PASS.
(Paragraph 7)
The clean up of SFPs C and D continues.
(Paragraph 8)
The licensee had implemented a good program to maintain its Control Room Emergency Ventilation system within TS requirements.
(Paragraph 9)
The Radiation Control (RC) staff involved with the radwaste and spent fuel shipments is competent and carries out its duties in a professional manner.
(Paragraph 10)
REPORT DETAILS Persons Contacted Licensee Employees R. Andrews, Specialist, Environmental and Radiation Control (E&RC)
- J. H. Collins, Operations Manager
- P. L. Doss, Senior Specialist, Chemistry
- C. S. Hinnant, General Manager
- Harris Plant
- S. Johnson, Chemistry Supervisor J.
L. Kiser, Radiation Control Manager
- D. P. Knepper, Nuclear Engineering Department (NED) Site Supervisor
- W. Levis, Principal Engineer
- Nuclear Plant Support Section
'*J.
W. HcKay, Engineering/Technical Support Assessment Manager
- T. C. Morton, Maintenance Manager
- B. A. Meyer, E&RC Manager
- J. F. Nevill, Technical Support Manager L. Oakley, System Engineer C.
S. Olexik, Regulatory Compliance Manager
- A. D. Poland, E&RC Support Manager
- K. Rogers, Radiation Control Technician I
- G. E. Vaughn, Vice President
- Harris Nuclear Project
- H. G. Wallace, Senior Specialist, Regulatory Compliance B. White, Environmental and Chemistry Manager
- E. Wills, Radiation Control Supervisor W.
R. Wilson, Spent Nuclear Fuel Manager
- L. J.
Woods, Systems Engineering Manager Other licensee employees contacted during this inspection included engineers, operators, technicians, and administrative personnel.
Nuclear Regulatory Commission
- H. Shannon, Resident Inspector
- J. Tedrow, Senior Resident Inspector
- Attended exit interview Acronyms and Initialisms used throughout this report are listed in the last paragraph.
Organization (84750 and 86750)
Technical Specification (TS) 6.2 describes the licensee's organization.
The inspector reviewed the licensee's organization, staffing levels, and lines of authority as they related to the Chemistry Department and Radioactive Waste Shipping Group to verify that the licensee had not made organizational changes which would adversely affect the ability to control radiation exposures or radioactive materia The inspector determined that th'ere had been no changes in the Chemistry Department whatsoever since the last inspection (Inspection 92-12 of June 1992).
The only change in the Radioactive Waste Shipping Group was the rotation of one technician out of the group and the rotation of another into the group.
The inspector concluded that the respective organizations had maintained their ability to function effectively.
No violations or deviations were identified.
Plant Water Chemistry (84750)
During this inspection, the Shearon Harris Nuclear Power Plant (SHNPP)
was in the midst of Refueling Outage No. 4, which had begun on September 12, 1992 and was tentatively scheduled to be completed by the first week of December.
The reactor was defueled and the fuel rods were in the
"A" Spent Fuel Pool.
The inspector reviewed the plant chemistry controls and operational controls affecting plant water chemistry since the last inspection (Inspection 92-12, in June 1992) in this area.
TS 3.4.7 specifies that the concentrations of dissolved oxygen (DO),
chloride, and fluoride in the Reactor Coolant System (RCS)
be maintained below 0. 10 parts per million (ppm), 0. 15 ppm, and 0. 15 ppm, respectively.
TS 3.4.8 specifies that the specific activity of the primary coolant be limited to less than or equal to 1.0 microcuries/gram (uCi/g) dose equivalent iodine (DEI).
These parameters are related to corrosion resistance and fuel integrity.
The oxygen parameter is based on maintaining levels sufficiently low to prevent general and localized corrosion.
The chloride and fluoride parameters are based on providing protection from halide stress corrosion.
The specific activity parameter is based on minimizing personnel radiation exposure during operation and maintenance.
Pursuant to these requirements, the inspector reviewed daily summaries which correlated reactor power output to chloride, fluoride, and dissolved oxygen concentrations, and specific activity of the reactor coolant for the period of August 1, 1992 through September 30, 1992 and determined that the parameters were maintained well below TS limits.
Typical values for DO, chloride, and fluoride were less than two parts per billion (ppb), less than two ppb, and less than two ppb, respectively.
Typical DEI values at steady-state conditions ranged from 5.54E-2 uCi/g,to 1.03E-2 uCi/g.
The inspector concluded that the Plant Water Chemistry was maintained well within the TS requirements.
No violations or deviations were identifie I
Confirmatory Measurements (84750)
In an effort to evaluate the licensee's analytical capabilities, Non-Radiological Water Chemistry Standards were prepared by the Oak Ridge National Laboratory (ORNL) and presented to the licensee for analysis.
The matrix of samples to be analyzed was determined by those analyses routinely performed by the licensee at each facility.
The licensee was also provided with an opportunity for the splitting of samples of feedwater between the licensee's laboratory and ORNL.
The split samples were sent off to ORNL for analysis and comparison.
Upon compilation of the sample analyses by ORNL, the complete results of all participants as well as statistical data will be made available to all of the licensees that submitted analytical results.
The results of those samples which the licensee analyzed are included in the table of Attachment l.
No violations or deviations were identified.
Radiological Effluents (84750)
a.
Semiannual Radioactive Effluent Release Report TS 6.9. 1.4 requires the licensee to submit a Semiannual Radiological Effluent Release Report within the time periods specified in TS 6.9. 1.4 covering the operation of the facility during the previous six months of operation.
The inspector reviewed the semiannual radioactive effluent release report for the first half of 1992.
This review included an examination of the liquid and gaseous effluent results for the first half of 1992 as compared to those of full years 1990 and 1991.
The data are summarized below.
Harris Radioactive Effluent Release Summary 1990 1991 first half 1992 Abnormal Releases a.
Liquid b.
Gaseous Activity Released (curies)
a.
Liquid 1.
Fission and Acti-vation Products 2.
Tritium 3.
Gross Alpha 7.26E+2
< LLD 2.92E+2
< LLD 5.59E+2
< LLD 7.31E-1 6.62E-1 6.37E-2
b.
Gaseous 1.
Fission and Acti-vation Products 2.
Iodines 3.
Particulates 4.
Tritium O.OOE-O 7.72E-5 1.56E+0 O.OOE-O 9.98E-6 4.71E-5 2.89E-5 8. 13E-1 5. 66E-4 5.96E+2 8.63E+2 3.37E+2 A comparison of the listed data for 1990, 1991, and the first half of 1992 showed no significant changes.
For the first half of 1992, Harris liquid, gaseous, and particulate effluents wer e maintained well within TS,
CFR 20, and
CFR 50 effluent limitations.
Although no abnormal releases were documented during the first half of 1992, two non-routine gaseous releases had been recorded since July 1 and will be included in the Semiannual Radioactive Effluent Release Report for the second half of 1992.
The details of these releases are detailed in Paragraph 6.c of this report.
The report also included the results of solid radwaste shipments.
The following table summarizes those shipments for the previous two and a half years.
The shipments typically included spent resins, filter sludges, dry compressible waste, and contaminated equipment.
Harris Solid Radwaste Shipments 1990 1991 first hal f 1992 Volume (cubic meters)
Activity (curies)
77.4 62.5 78.0 301.8 26.8 213.2 For solid radwaste, no significant changes were noted for the period reviewed.
There were no changes to the Process Control Program (PCP),
Environmental Monitoring Program, or Offsite Dose Calculation Manual (ODCN) during this reporting period.
However, the Land Use Census, performed in June 1992, determined that changes in the distances to the nearest special locations, i.e., residences, gardens, meat animals, milk animals, etc.
had occurred.
Therefore, Table 3.2-2,
"Distance to the Nearest Special Locations for the Shearon Harris Nuclear Power Plant," of the ODCH would be revised and, upon approval and incorporation into the ODCH, included in the Semiannual Radioactive Effluent Release Report for the second half of 1992.
No unprotected outdoor tanks and no gas storage tanks exceeded TS limits during this reporting period.
Furthermore, no major modifications to the Radwaste System were mad b.
Out of Service Honitors Out of service monitors were addressed in Paragraph 5.b of Inspection Report (IR) 50-400/91-22, Paragraph 9 of IR 50-400/92-01, and Paragraph 5.b of IR 50-400/92-12.
The inspector followed up this item with a status review to determine when the monitors were expected to be placed back in service.
Plant Change Request (PCR) 3170, which addressed the Flow Rate Honitors for the Reactor Auxiliary Building (RAB) Vent Stack 1,
Waste Processing Building Vent Stack 5, and Waste Processing Building Vent Stack 5A, had been completed and closed out on August 17, 1992.
PCR 5107 addressed modifications to the flow measurement system to correct moisture interferences which resulted in discrepancies between actual and expected flow rates of the flow rate monitor for Turbine Building Vent Stack 3A.
The moisture subjected the flow velocity probe to burnout.
No design change was made by this PCR.
Rather, new equipment of the same type was to be installed.
The new equipment was installed but broke down while testing procedures were being developed.
The equipment was returned to the vendor for repair/replacement.
The equipment was installed and had been declared operable on September 23, 1992.
Formal close out was awaiting completion of a documentation package and was expected in the near future.
In addition, the licensee had developed a tracking system which summarized TS Radiation Honitors which were inoperable for more than one day on a monthly basis.
The tracking would enable the licensee to quickly identify a problem monitor and rectify the condition.
The inspector concluded that the licensee had resolved the problems associated with its out-of-service monitors.
N The inspector concluded that the Semiannual Radioactive Effluent Release Report was complete and satisfied TS requirements.
No violations or deviations were identified.
Process and Effluent Honitors (84750)
'a ~
Status of Honitors TSs 3/4.3.3. 1, 3/4.3.3.10, and 3/4.3.3. 11 define the operation and surveillance requirements for monitors of radioactive (or potentially radioactive)
streams.
This instrumentation is provided to monitor and control the releases of radioactive materials during normal and abnormal plant conditions as well as in effluents during effluent releases.
The alarm/trip setpoints
for the effluent monitors are calculated in accordance with the procedures in the ODCH to ensure that the alarm/trip will occur prior to exceeding the limits of 10 CFR 20.
The alarm/trip setpoints for the process monitors are specified by the TSs.
The inspector walked down fifteen TS Radiation Honitors, including six Effluent Monitors, to become familiar with their physical location in the plant and to observe their state of maintenance and operability.
The following monitors were included:
REM-ILT-3502B; RN-1AV-3509-SA and RH-lAV-3509-1SA; REM-1MD-3528; REH 1HD 3530)
RM 1TV 3536 1 )
REH 1WL 3540 )
REH 21WL 3541 REM-21WS-3542; REH-1WC-3546 and RH-1WV-3546-1; REM-1WV-3547 and RM-IWV-3547-1) RN-ICR-3561A-SA, RH-ICR-3561B-SB)
RH-ICR-3561C-SA, and RH-1CR-3561D-SB; RM-1CR-3590-SB; RN-1HS-3591-SB; RH-1MS-3592-SB; and RH-1HS-3592-SB.
Of these monitors, one was found to be out of service due to an in-progress calibration (and its associated microprocessor was correspondingly out of service).
All other monitors were found to be well-maintained and operable.
The inspector concluded that the program for maintaining the plant's process and effluent monitors was being successfully implemented.
Release Permit Review TSs 3.11.1.1, 3.11.1.2, 3.11.2.1, 3.11.2.2, and 3.11.2.3 define the requirements for liquid and gaseous effluent concentrations, doses and dose rates, and waste treatments released to Unrestricted Areas.
These requirements are intended to ensure that the limits of 10 CFR 20 and,10 CFR 50 are satisfied.
TSs 4.11.1.1.1, 4.11.1.1.2, 4.11.2.1.1, 4.11.2.1.2, 4.11.2.2, and 4. 11.2.3 define the surveillance requirements for the sampling and analysis program.
The inspector reviewed two randomly-selected Liquid Release Permits (920497 and 920498)
and a randomly-selected Gaseous Release Permit (920501)
from since July of this year to verify compliance.
The permits included both release information and projected dose calculations and were found to be complete, including the identification of the source of the release, the activity released (identified by isotope),
and the volume of the effluent'ischarged.
Unplanned Releases In addition, the inspector reviewed two non-routine gaseous releases, 920425 and 920494.
In the case of 920425, an unplanned release occurred on September ll, 1992 in the form of a small fission gas "burp" as preparations were being made for plant shutdown.
The total release was calculated to be 2.5 Curies, yielding a total dose of 0.0014 mrad (vs.
an annual Technical Specification limit of 10 mrad at the site boundary).
In the case
of 920494, operations utilized the Main Steam Power Operated Relief Valves (PORVs) to maintain system temperature and pressure after the turbine and reactor tripped on July 12, 1992.
Low levels of activity were identified in samples taken from the steam generators (SGs)
about thirty hours after the trip.
(Samples of the SGs taken shortly before the trip showed activity to be less than the Lower Limit of Detection (LLD).
The PORVs were utilized in this manner for about sixty-three hours until the Hain Steam Isolation Valves (HSIVs) were opened.
The licensee estimated that 4.35E+5 uCi of tritium as well as minute quantities of noble gases and activation products were released.
Doses to the most vulnerable member of the public (the thyroid of a child at the site boundary)
were determined to be 1.73% of the allowable weekly limit.
The inspector concluded that effluent processing and monitoring was generally well controlled and ensured that regulatory requirements were satisfied.
No violations or deviations were identified.
Post Accident Sampling System (PASS)
(84750)
NUREG-0737 requires that the licensee be able to obtain a sample of the reactor coolant and containment atmosphere.
Furthermore, the sample must be promptly obtained and analyzed (within three hours total) under accident conditions without incurring a radiation exposure to any individual in excess of 3 and 18 3/4 rem to the whole body or extremities, respectively.
TS 6.8.4.e requires that a program be established, implemented, and maintained to ensure the capability to obtain and analyze, under accident conditions, reactor coolant, radioactive iodines and particulates in plant gaseous effluents, and containment atmosphere samples.
The PASS should provide these capabilities and should enable the licensee to obtain information critical to the efforts to assess and control the course and effects of an accident.
The inspector spoke to the cognizant licensee Technical Specialist responsible for the system for a status update.
The gas stripper had experienced a problem in maintaining a constant pressure or flow.
PCR 6161 had been initiated to make numerous changes to the PASS.
Two field revisions had been added to PCR 6161; (1) to increase the tubing size to the portable cask and dilution valve 1SP-1004 and (2) to replace the flow control valve 1SP-978, which would allow stable gas operation and sampling.
In addition to actions listed in the expansion of PCR 6161 in Paragraph 8 of Inspection Report 50-400/92-12, two other actions were taken. Specifically, (1)
a bypass line and valve 1SP-1726 were installed around drag valve 1SP-1725 to allow for Residual Heat Removal (RHR)
System sampling, and (2) valve 1SP-1727 was added in the degasification inlet line to permit fine tuning of the degasifier inlet flow.
Furthermore, two work tickets, 92-AHPWl and 92-AHPXl, were added to the
outage work scope so that the PASS can be operated while the plant is on RHR.
92-ANPWl'as written to resolve an intermittent problem with the totalizer readout and 92-ANPX1 was written to resolve a problem of excess voltage of the controller.
Testing done during the third quarter showed mixed results, with the hydrogen grab sample, the in-line hydrogen stripped gas concentrations, undiluted stripped fission gas isotopic activity, and the diluted RCS sample analyzed for chloride failing to meet the acceptance criteria, while the diluted RCS sample analyzed for isotopic activity, 'on-line pH value and oxygen concentration, and containment air sample analysis (charcoal and isotopic) satisfied the acceptance criteria.
Also, PASS sampling procedure, Chemistry and Radiochemistry (CRC)
Procedure CRC-821,
"Post Accident RCS/RHR Sampling,"
had been revised (Rev. 9, July 29, 1992) to incorporate the latest modifications to the PASS.
Before the PASS can be turned over for operation, other procedures must be revised to reflect modified valve and flow configurations and to incorporate lessons learned during the testing and evaluation phases.
The inspector concluded that the licensee was continuing to make progress in its efforts to upgrade the PASS.
No violations or deviations were identified.
Spent Fuel Pool (SFP) Facility (84750)
The inspector met with cognizant licensee representatives to discuss the status of the clean-up effort of the SFPs.
Pool A was used for storage of new fuel as well as some spent fuel and Pool B exclusively for the storage of spent fuel from all three CPL nuclear facilities.
Pools C
and D had been used for temporary storage of contaminated filters, scaffolding, etc.
The status of Pool C had not changed since the last inspection, i.e., it was empty of contaminated equipment and debris and filled with borated water to the same level of the Transfer Canal (to reduce stress on the isolation gates between the pool and the canal).
Pool D was filled with borated water and, although some miscellaneous items remained, the steel platform, hoses, and other equipment supporting the vessel had been removed.
Water clarity, due to undissolved solids, in Pools C and D
continued to be a problem.
After the current outage and some additional minor clean up around Pool D, the licensee planned to utilize a submersible filter system to remove the undissolved solids in Pool D.
The licensee had established a task force to consider engineering and procedural controls to keep the crud source term in the fuel pools for the long term, where it would naturally decay, thereby reducing exposure and dose to plant employee The inspector concluded that the licensee was making steady progress in the cleanup of Pools C and D and that Pools A and B and the Transfer Canal were well-maintained.
No violations or deviations were identified.
Control Room Emergency Ventilation System (84750)
Per
CFR 50, Appendix A, Criterion 19, licensees shall assure that adequate radiation protection be provided to permit access to and occupancy of the control room under accident conditions and for the duration of the accident.
Specifically, operability of the control room emergency ventilation system ensures that 1) the ambient air temperature
'does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room remains habitable for operations personnel during and following all credible accident conditions such that the radiation exposure to personnel occupying the control room is limited to 5 rem or less whole body, or its equivalent.
TS 3.7.6 defines operability requirements for the control room emergency air cleanup systems under the various design scenarios.
TS 4.7.6 sets the surveillance requirements for the system.
The inspector reviewed the latest test results for High Efficiency Particulate Air (HEPA) filter and carbon adsorption testing of both system trains, R-2-1A-SA and R-2-1B-SB, to verify compliance with TS requirements.
The tests were conducted on July 28, 1992 and the filters satisfied their respective acceptance criteria.
The inspector reviewed the following Heating, Ventilation, and Air Conditioning (HVAC) Air Balance Drawings for the Control Room:
PD-8220-C-C-0002, Sheet Nos.
2A, 2B, 2C, and 2D; PD-8220-C-C-0003, Sheet Nos.
3A and 3B; PD-8220-C-C-0004, Sheet Nos.
4A, 4B, and 4C; PD-8220-C-C-0005, Sheet Nos.
5A, 5B, 5C, and 5D; and PD-8220-C-C-0006, Sheet Nos.
6A and 6B.
These drawings showed the general layout of the components of the Control Room Air Conditioning System.
The inspectors walked down the system, from the air intake to the Control Room, to air exhaust, noting the major components, such as isolation dampers, filter banks, and fans as well as detectors for radiation, etc.
All components were well maintained, with no sign of physical degradation.
The inspector reviewed the System Description, SD-173,
"Control Room HVAC Systems,"
Rev. 3, effective October 15, 1991, and discussed system operation under both normal and emergency conditions with the System Engineer.
The inspector concluded that the licensee had implemented a good program to maintain its control room emergency ventilation system within TS requirements.
No violations or deviations were identifie.
Radwaste Processing and Transportation (86750)
CFR 71.5 (a) requires that each licensee who transfers licensed material outside of the confines of its plant or other place of use, or who delivers licensed material to a carrier for transport, shall comply with the applicable requirements of the regulations appropriate to the mode of transport of the Department of Transportation (DOT) in 49 CFR, Parts 170 through 189.
Pursuant to these requirements, the inspector reviewed the licensee's activities affiliated with these requirements, to determine whether the licensee effectively processes, packages, stores, and ships radioactive solid materials.
The licensee's program for the packaging and transportation of radioactive materials, including solid radwaste, was conducted by the Radioactive Waste Group within the Health Physics Department.
Radwaste was processed and packaged by the Radwaste Group, including compacting contaminated material, loading shipments, and preparing shipping documentation.
'a ~
b.
C.
Radwaste Shipping Documentation The inspector reviewed shipping logs for 1992.
The logs showed that fourteen disposal shipments and one hundred special, non-burial shipments were made to date (October 21, 1992).
The non-burial shipments included a wide variety of items, from empty spent fuel shipping casks to samples to be counted at the Energy and Environmental (BE) Center.
The inspector reviewed three disposal shipment packages, including D-10-92, D-11-92, and D-14-92 as well as five non-burial shipments, including S-38-92, S-41-92, S-57-92, S-92-92, and S-95-92 for completeness and compliance with the regulations.
The packages documented the shipments and included items such as unique shipment and shipping container numbers, waste content and volume, total activity, analytical summary and breakdown of isotopes with a half-life greater than five years.
The radiation and contamination survey results were within the limits specified and the shipping documents were being maintained as required.
Spent Fuel Shipment Status The licensee had received two shipments of spent fuel from the H. B. Robinson Plant since the last inspection, for a total of five to date this calendar year, and expected one more by year end.
Shipments of spent fuel from the Brunswick site were expected to resume in Spring, 1993.
Status of Changes Resulting from Shipment S-47-92 Paragraph 12.c of IR 50-400/92-12 references the failure of the
"strong, tight package" requirement for a shipment of LSA
material.
Adverse Condition Report (ACR)92-234 had been written to address the subject so as'to preclude its happening in the future.
Its focus was on three corrective action items:
Corporate Health Physics to develop a company policy for the construction and use of wooden boxes for radioactive material shipments.
Corporate Health Physics to develop guidance on properly verifying interior and exterior bracing on radioactive material packages.
Harris Plant E&RC Department to revise shipping procedures/instructions to ensure proper interior and exterior shoring.
These corrective actions were scheduled to be completed by Harch, 1993.
The inspector concluded that the issue had been appropriately addressed by the ACR and implementation would be reviewed during a
subsequent inspection.
d.
Information Notice (IN) 92-62 The inspector discussed IN 92-62,
"Emergency Response Information Requirements For Radioactive Haterial Shipments," with cognizant licensee personnel to be sure that the licensee had received it and that the staff was aware of it and its implications.
The IN emphasizes that all emergency response information required by Department of Transportation (DOT) regulations must be accurately provided on shipment papers or other documents and that the licensee must be prepared to respond immediately with the information, as needed.
Furthermore, the IN defines
"immediate access" to a person knowledgeable about a specific shipment as being fifteen minutes.
The licensee was modifying its shipping procedures to streamline the emergency response information instructions to meet the guidance as outlined in the IN.
11.
Exit Interview The inspection scope and results were summarized on October 23, 1992, with those persons indicated in Paragraph 1.
The inspector described the areas inspected and discussed the inspection results, including likely informational content of the inspection report with regard to documents and/or processes reviewed during the inspection.
The licensee did not identify any such documents or processes as proprietary.
Dissenting comments were not received from the license Acronyms and Initialisms ACR - Adverse Condition Report CFR - Code of Federal Regulations Ci - curie CRC - Chemistry and Radiochemistry DEI - Dose Equivalent Iodine DO - Dissolved Oxygen DOT - Department of Transportation E&C - Environmental and Chemistry BE - Energy and Environmental E8RC - Environmental and Radiation Control g - gram HEPA - High Efficiency Particulate Air HVAC - Heating Ventilation and Air Conditioning IN - Information Notice IR - Inspection Report LLD - Lower Limit of Detection uCi - micro-Curie (1.0E-6 Ci)
mg - milligram MSIV - Main Steam Isolation Valve NED - Nuclear Engineering Department No. - Number NRC - Nuclear Regulatory Commission ODCM - Off-site Dose Calculation Manual ORNL - Oak Ridge National Laboratory PASS - Post Accident Sampling System PCP - Process Control Program PCR - Plant Change Request PORV - Power-Operated Relief Valve ppm - parts per million RAB - Reactor Auxiliary Building RC - Radiation Control RCS - Reactor Coolant System Rev - Revision RHR - Residual Heat Removal SFP - Spent Fuel Pool SG - Steam Generator SHNPP - Shearon Harris Nuclear Power Plant TS - Technical Specification
ANALYSIS TYPE ATTACHMENT 1 CONCENTRATION RANGE m
l RESULTS Chloride Anions Chloride Anions Chloride Anions Fluoride Anions Fluoride Anions Fluoride Anions Sul fate Anions Sulfate Anions Sulfate Anions Copper Copper Copper Iron Iron Iron Silica Silica Boron Boron Boron Sodium Sodium Sodium Zinc Zinc Zinc Ammonia Ammonia Ammonia Hydrazine Hydrazine Hydrazine Lithium Lithium Lithium 10.0 30.0 60.0 10.0 30.0 60.0 10.0 30.0 60.0 15.0 25.0 60.0 15.0 25.0 60.0
40 500 2500 4500 2.5 7.5 12.0 0.5 4,0 8.0
275 400 5 '
25.0 40.0 2.5 7.5 18.0 30.0 50.0 100.0 30.0 50.0 100.0 30.0 50.0 100.0 25.0 55.0 100.0 25. 0 55.0 100.0
60 1500 3500 5500 7.5 14.5 18.0 1.5 6.0 12.0 125 325 600 15.0 35.0 60.0 7.5 14.5 28.0 Agreement gualified Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Disagreement gualified Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Agreement Note:
gualified Agreement is < three standard deviations.
Agreement is < two standard deviation t