IR 05000528/1990033
| ML17305A991 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/26/1990 |
| From: | Cillis M, Coblentz L, Miles K, Yuhas G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17305A990 | List: |
| References | |
| 50-528-90-33, 50-529-90-33, 50-530-90-33, NUDOCS 9008100298 | |
| Download: ML17305A991 (10) | |
Text
U.
S.
NUCLEAR REGULATORY COMMISSION
REGION V
Report:
Licenses:
Licensee:
Facility:
I Location:
50-528/90-33, 50-529/90-33, and 50-530/90-33-NPF-41, NPF-51, and NPF-74 Arizona Public Service Company'.
0.
Box 52034 Phoenix, Arizona 85072-2034 Palo Verde Nuclear Generating Station Units 1; 2, and
Mintersburg, Arizona Inspection dates:
'July 17-20, 1990 Inspected by:
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e igne Approved by:
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le Rea Radiological Protection Branch ra 5o e
igne
~Summer:
F Areas Ins ected:
Routine, unannounced inspection of followup items, occupationa exposure, radioactive waste systems, water chemistry, and radiological environmental monitoring.
Inspection modules 92701,'83750, and 84750 were used.
Results:
The licensee's programs were maintaining previous levels of
~per ormance, with housekeeping in controlled areas noted as a.strength (Section 3).
No violations of NRC requirements were identifie \\
DETAILS
, 1.
Persons Contacted Licensee M. Barley, Acting Supervisor, RMS/Effluents J. Baxter, Engineer, Compliance P.
Hughes, General Manager, Radiation Protection (RP)
D. Johnson, Supervisor, Compliance S.
Kanter, Site Coordinator, Participant Services M. Linares, Lead Engineer, RP M. Marsh, Plant Director J. Napier, Lead Engineer, Compliance K. Oberdorf, Manager, RP, Unit 1 A. Ogurek, Manager, RP, Unit 2 R.
Rouse, Supervisor, Compliance R. Schaller, Assistant Plant Manager, Unit 1 J. Scott, Manager, Site Chemistry C. Seliga, Lead Auditor, equality Assurance (gA)
J. Sills, Acting Manager, RP Technical Services NRC
J.
Ringwald, Resident Inspector The individuals listed above attended the exit meeting held on July 20, 1990.
The inspectors met and held discussions with additional members of. the licensee's staff during the inspection.
2.
~F11 (92701)
Item 50-528/88-40-03 Closed):
This item concerned the
.
s en s
>ca son o
a new ms sampling location in the 1986 land use census, and the criteria by which sample locations for milk ingestion pathway monitoring are selected.
The location in question had been added to.the Offsite Dose Calculation Manual (ODCM),
Revision 3, dated'February 21,.1990, although low milk production rate at the new location had precluded obtaining sufficient sample for representative monitoring.
In addition, Technical Specification (TS) Table 3. 12-1 had been revised to clarify location selection criteri a.
3.
Occu ational Ex osure 83750)
~Chan ea The inspectors reviewed the status of changes to organization and staffing in the licensee's RP and Chemistry groups.
For comments related to this area, see NRC Inspection Report 50-528/90-2 ~Trainin The inspectors reviewed the licensee's general employee training (GET) in radiological work practices for compliance with 10 CFR 19. 12 requirements.
GET training modules provided thorough coverage of radiation fundamentals, external dose limits and monitoring devices, contamination control, control of radioactive material, protective clothing, radiological postings, and radiation exposure permits.
Audiovisual aids, instructor knowledge and techniques, and classroom conditions provided a positive learning environment.
The inspectors examined the licensee's computer modules for periodic retraining of radiation workers.
Learning objectives were well
organized, and radiological safety concepts were clearly presented.'
Particular attention had been given to site-specific hot particle controls, control of high radiation areas, and voicing employee con'cerns.
Surve s
Monitorin Contamination Control and Control of a >oac
>ve a er>a The inspectors reviewed posted surveys of radiation and contamination levels for completeness, accuracy, and recency.
Extensive tours were conducted of the Unit 2 Auxiliary Building, Fuel Building, Control Building, and Radwaste Building.
Dose rate surveys were performed using NRC ion chamber survey instrument Model R0-2, Serial No.
9163, due ft:g calibration September 30, 1990.
The inspectors observed the following items:
General housekeeping was excellent.
Work areas and step-off pads were well kept, with'adwaste, debris and laundry neatly sequestered into convenient bags and receptacles.
Hoses and cords traversing contaminated areas were properly secured to avoid spread of contamination.
An aggressive program was in evidence to reduce the amount of contaminated areas in auxiliary spaces.
Radiological postings were consistent with survey information, and in keeping with independent surveys performed by the inspectors.
Management review of posted surveys was timely.
Personnel dosimetry devices were properly worn by workers.
Portal monitors and frisking equipment were used properly.
Monitoring instrumentation was in current calibration and had been performance checked.
Auxiliary operators and RP technicians questioned appeared well trained in radiological safety procedures and exposure control techniques, and were knowledgeable of radwaste system functions.
In the areas observed during tours, the licensee's programs were satisfactory.
Improving performance was exhibited in control of
.
contamination, and housekeeping in controlled areas was a strengt.
Radioactive Waste S stems Water Chemistr and Radiolo ical nvironmen a
oni orin This program area was reviewed by observation, review of applicable procedures and records, and interviews with responsible personnel.
Audits and A
raisals The inspectors reviewed licensee Audit Report 90-003, which addressed sampling of gaseous.effluents and the radiological environmental monitoring program (REMP).
Sampling records and performance were evaluated in relation to TSs, licensee procedures, and the ODCM.
Overall program structures were compared to Regulatory Guides 1.21 and 4. 15.
Particular attention was given to proposed reor'ganizations of the chemistry -and effluents groups, and to the Radiation Monitoring System (RMS) long term improvement plan.
The audit resulted in two equality Deficiency Repoi ts, but identified
.
no major program breakdowns.
Im lementation of Radioactive Waste Pro ram The inspectors reviewed the Semiannual Radioactive Effluent Release Report (SARERR) for July 1 through December 31, 1989.
Radiation doses at or beyond the site boundary were within the limits of TS 3. 11. 1.2.
Dose rates due to gaseous effluents were within the limits of TS 3. 11.2. 1.
Sample analysis systems achieved lower limits of detectability (LLDs) at or below~ the levels required by TS 3. 11. 1. 1.
No anomalous measurements, omissions, or trends were observed.
Low levels of tritium were reported to be present in -the Evaporator Ponds.
Monitoring of the ponds had be'en performed in accordance with TS 3. 12. 1, and releases to the pond had been limited to concentrations specified in TS 3. 11. l. 1 by sampling the Chemical Waste Neutralizer Tanks.
The licensee stated that the source of the radioactivity had been identified 'as primary-to-secondary leaks experienced during earlier phases of operation.
The inspectors noted that the Final Safety Analysis Report (FSAR) implied that the Evaporator Ponds would be maintained free of radioactivity.
The licensee stated that this discrepancy had been identified,,and that a change to the FSAR had been submitted.
The inspectors toured the Unit 1 Dry Active Waste Processing and Storage (DAWPS) Building, and examined the licensee's methods of sorting, compacting, and packaging compressible waste.
Processing equipment appeared well maintained, storage areas. were orderly, and radiation monitorinq equipment had received current performance checks.
RP technicians and equipment operators were knowledgeable of their tasks and responsibilities.
Radiological postings were consistent with the requirements of 10 CFR 20.20 Im lementation of Water Chemistr Pro ram The inspectors reviewed records of reactor coolant system chemistry for 1990.
The licensee had performed analyses of dissolved oxygen, fluoride, chloride, and dose equivalent Iodine-131 at the frequencies required by TS 3/4.4. 6, "Chemistry," and TS 3/4.4.'7,
"Specific Activity."
Sample results were within TS required concentrations'm lementation of Radiolo ical Environmental Monitorin Pro ram The inspectors reviewed the 1987 Annual Radiological Environmental Operating Report, Revision 1, dated July 17, 1990.
The revision had been issued as the result of a licensee audit and internal review which identified redundancies in the earlier version of the report.
Two sets of data had in'advertently been used in the original report, due to a change in the contractor responsible for the licensee's REMP program.
The inspectors asked the cognizant health physicist (HP) what degree of administrative and technsca]
oversight had been given to the REMP contractor, The HP stated that survey reports submitted by the contractor had been painstakingly reviewed.
Discrepancies between raw data arid final analysis results had been discovered by the licensee on several occasions, due to calculational and transpositional errors by the contractor.
The HP stated, in addition, that the contractor's performance had shown 'improvement, and that technical reviews by the licensee would continue to ensure accuracy in environmental reports.
The inspectors reviewed the February 1990 performance of licensee procedure 75ST-9ZZ04,
"Land Use Census," for compliance with the requirements of TS 3/4. 12,2.
All sectors had been appropriately canvassed, and several new residences had been added.
Revision 3 to the ODCM was included in the SARERR.
Changes to the ODCM included revised descriptions of sample locations (for improved accuracy),
deletion of meat animals-from the required annual land.
use census, and updates to sample locations based on the most recent land use census.
ODCM changes did not reduce the accuracy or reliability of dose calculations or setpoint determinations.
The inspectors noted that the licensee had submitted a proposal to relocate requirements of TS 3. 11 and 3. 12 into the ODCM per NRC Generic Letter 89-01.
Using data and methods provided in the ODCM, the inspectors calculated child thyroid dose from inhalation and milk 'ingestion at the controlling location.
Results were within the limits prescribed by 10 CFR 50, Appendix I, and the calculation revealed no procedural concern Im lementation of Meteorolo ical Monitorin Pro ram The inspectors reviewed records of survei llances of 'site meteorological instrumentation conducted during the previous
months.
Channel checks had been performed daily pursuant to TS 4.3.3.4.
Station procedures 36ST-9RG02,
"Meteorological System
~
Calibration," and 36ST-9RG03,
"Meteorological System Calibration,"
(redundant system)
had been performed semiannually as required.
Records were complete, and indicated a high degree of reliability (greater than 95 per cent).
Out of tolerances discovered during testing had been reported to the work group supervisor per procedure, and corrective action taken as necessary.
Management review of data was timely.
The licensee was maintaining its previous level of performance in this program area.
Observed aspects of the environmental monitoring, water chemistry, and radioactive waste management programs were adequate in meeting the licensee's safety objectives.
5.
Exit Interview The inspectors met with the individuals denoted in Section 1 at the conclusion of the inspection on July 20, 1990.
The scope and findings of the inspection were summarized.