IR 05000528/1993047
| ML20059A185 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 12/16/1993 |
| From: | Chaney H, Reese J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20059A156 | List: |
| References | |
| 50-528-93-47, 50-529-93-47, 50-530-93-47, NUDOCS 9312300048 | |
| Download: ML20059A185 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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REGION V
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50-528/93-47, 50-529/93-47, and 50-530/93-47
License Nos.:
NPF-41, NPF-51, and NPF-74 Licensee:
Arizona Public Service Company P. O. Box 53999, Station 9012 Phoenix, Arizona 85837 j
Facility:
Palo Verde Nuclear Generating Station (PVNGS)
Units 1, 2,-& 3 Inspection at:
PVNGS Site, Wintersburg, Arizona Inspection Dates:
November 8-10, 1993
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Inspector:
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H. Dean Chaney, Senior Radiation Specialist Date ' Sign'ed Approved By:
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- 1 S O-a James H. Reese, Chief, Dat6Sidned Facilities Radiological Protection Branch Summary:
Areas Inspecte_d: This was a special announced inspection of the licensee's preparations for the January 1, 1994, implementation of changes to 10 CFR Part 20 (Sections 2c 1-20.602), as set forth in Federal Register 56 FR 23377, dated
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May 21,1991.
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Results: Overall, the licensee appears to be capable of implementing all of
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the changes to 10 CFR Part 20 as referenced in FR 23377, on January'1, 1994.
No violations or deviations were identified.
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9312300048 931216 PDR ADOCK 05000528
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DETAILS 1.
PERSONS CONTACTED Licensee
- J. Levine, Vice President, Nuclear Production r
- D. Kanitz, Sr. Engineer, Nuclear Regulatory Affairs
- M. Shea, General Manager, Radiation Protection (RP)
- T. Grey, Supervisor, RP Technical Support
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- H. Lantz, Supervisor, RP Technical Support
- A. Haugen, Auditor, Quality Assurance
- W. Hoey, Manager, RP Technical Support Others
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- W. Britz, RP Consultant, Quality Assurance
- A. Ogurek, Consultant, Nuclear Oversight
- R. Henry, PVNGS Site Representative, Salt River Project
- J. Draper, PVNGS Site Representative, Southern California Edison
- Indicates those in attendance at the Exit Meeting on November 10, 1993.
Follow up telephone conversations with Messrs.
T. Grey and W. Hoey were conducted on November-29 and
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December -3, 1993.
2.
OCCUPATIONAL RADIATION EXPOSURE (83750)
The licensee's preparations for the January 1,1994, implementation of revisions to 10 CFR Part 20 (Sections 20.1-20.602), as set forth in Federal Register 56 FR 23377, dated May 21, 1991, was_ reviewed. This review focused on the following areas of licensee effort to implement the new Part 20 (renumbered Sections 20.1001-20.2402).
e Radiation Protection Program programmatic changes involving:
Annual radiation exposure limits (occupational and nonoccupational) and the total dose cor. cept.
- New radiation dose terminology.
- Internal radiation exposure control and monitoring.
- Planned Special Exposures.
- Very High Radiation Area Controls.
- Declared pregnant women and dose to the embryo / fetus.
- Revised radioisotope exposure and effluent concentration limit ~
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Respiratory protection equipment use assessment.
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e Routine reports and event notifications.
Previously existing RP Program attributes and-supporting activities involving the following were also reviewed:
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Periodic RP Program reviews and assessments.
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Employee radiation protection training.
e RP instrument calibration.
e ALARA program and prospective job dose assessments e
Radioactive effluent release limits.
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Radiological posting and monitoring.
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Enhancements to the radiation dose assessment and radiological
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controlled area access control computer system.
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The inspector determined that the licensee had accomplished the following with regard to implementing the revisions to the new Part 20:
Established a dedicated team of RP professionals _for development
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of the implementing program.
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Performed a detailed review of each Part 20 change and established
individual technical position (s) for each change. These positions
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were developed in concert with a full nuclear power industry
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effort, including a concerted Region V nuclear power licensees review and development effort aimed at achieving implementation consistency among the Region V facilities.
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Actively participated in the NRC's que: tion and answer program,
_1 aimed at establishing an NRC and industry consensus on Part 20 changes and their meaning.
- Had recognized industry experts present formal overviews of Part 20 changes for the RP technical staff, including some Radiation Protection Technicians (RPTs).
e Issued a purchase order for development and installation of a new computerized radiation exposure management and access control
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system.
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Converted licensee implementing positions into programmatic / policy e
and implementing documents.
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- Performed evaluations of expected ru.. tion doses for site personnel exposures (external and internal). Historical records were used to perform the evaluation, o
Evaluated the effect of the lower dose limits for the public of the licensee's currently defined restricted area perimeter.
- Implemented respiratory protection device reduction program for.
i the last three unit outages at the PVNGS site.
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e Established a training program for general employees, radiation workers and the RP Staff.
The above represented some of the licensee's activities directed at achieving the January 1, 1994, implementation date. The Following i
observations were made by the inspector regarding the licensees
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implementing procedures and plans.
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An extensive set of procedures detailing the major program area
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f requirements (Radiation Protection, Respiratory Protection, ALARA, etc.,) were developed, e
Program implementing procedures were found to be well written and user friendly.
e Approximately 98 percent of the identified implementing procedures have been approved for issue.
e One type of high radiation area warning sign being developed will apparently not meet the wording requirements set forth in 10 CFR Part 20.1902(b).
e The licensee's new computerized radiation exposure and access control system has not successfully passed all of the licensee's factory acceptance tests. The inspector verified that the licensee was capable of implementing the new Part 20 requirements using manual backup methods.
The licensee's procedures for implementing the new Very High
Radiation Aree controls of 20.1602 do not adequately incorporate the guidance of NRC Regulatory Guide 8.38, " Control of Access to High And Very High Radiation Areas in Nuclear Power Plants."
e The licensee has elected to monitor occupationally exposed workers for both internal and external exposure, even though evaluations had shown internal exposures would be below the required.
monitoring threshold.
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- The licensee's Quality Assurance Department was conducting an in depth audit of the new Part 20 implementation program and its effectiveness. A contracted RP technical expert was being used on the audit staff.
The inspector determined that the licensee was capable of implementing.
all of the Part 20 changes on January 1, 1994. No violations or
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deviations were identified.
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Exit Meetina An exit meeting was held on November 10, 1993, with members of the licensee staff identified in Paragraph 1 of this report. The items
identified in this report were discussed at that time. The licensee did not identify as proprietary any of the materials provided to or reviewed
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by the inspectors during the inspection.
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