IR 05000361/1981002
| ML19343C687 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/17/1981 |
| From: | Book H, Fish R, Hamada G, Wenslawski F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML19343C685 | List: |
| References | |
| 50-361-81-02, 50-361-81-2, NUDOCS 8103250031 | |
| Download: ML19343C687 (7) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION V
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Report No.
50-361/81-02
Docket No.
50-361 License No.
CPPR-97 Safeguards Group Licensee.
Southern California Edison Company P. O. Box 800 Rosemead, California 91770 Facility Name:
San Onofre 2 Inspection at:
San Onofre Site, San Diego County, California
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Inspection conducted:
January 26-30, 1981 Inspectors:
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R. F. Fish, Radiation Specialist
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G. Hamada, Radiation Laboratory Specialist Date Signed Approved by:
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F. A. Wenslawski, Chief, Reactor Radiation Oate' Signed Saety.Sectpn Ott 0-A i'JlS'l Approved by:
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H. E. Book, Chief, Fuel Facility and Materials Date Signed Safety Branch t
Summary:
Insoection on January 26-30, 1981 (Report No. 50-361/81-02)
Areas Inspected:
Routine unannounced preoperational inspection of licensee action on previous inspection findings, preoperational testing procedures, process and effluent radiological monitoring systems, area and emergency radiation monitors, staffing and organization, training and laboratory capability.
The inspection involved 41.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of onsite-time by two inspectors.
Results:.No items of noncompliance or deviations were identified.
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RV Form 219 (2)
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DETAILS 1.
Persons Contacted
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Southern California Edison Company (SCE)_
J. M. Curran, Plant Manager
- H. E. Morgan, Superintendent, Units 2 and 3
- P. A. Croy, Project QA Supervisor, Units 2 and 3
- D. Stonecipher, Supervisor, Operations QA/QC R. Fitch, QA Engineer B. Sanano, QA Engineer D. Br'eg, Test Operations Supervisor (HVAC/ Rad Waste)
W. Ray, Lead I&C Startup Engineer
- J. Albers, Chemical cnd Radiation Protection Engineer S. Medling, Chemical and Radiation Protection Engineer Others R. Gray, Radiological Engineer (Contractor)
- Denotes those present at exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (80-14-01):
Primary calibration of process and effluent radiation monitors. The primary calibration data and
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related curves for the monitors presently possessed were examined.
This information has been stored in the EDM (document control)
office.
The gas monitors had been calibrated with two different concentrations of krypton-85 gas. The liquid monitors were calibrated with two different concentrations of cesium-137 and one concentration of cobalt-60.
The particulate monitors were calibrated with sources of cobalt-60 and cesium-137 and the iodine monitors were calibrated barium-133 and cesium-137 sources.
(Closed) Unresolved Item (80-14-02):
Biweekly inspections for erosion during transmission line activities. San Diego Gas and Electric sent a letter report, dated January 6, 1981, to SCE describing the activities associated with the construction of the transmission line between the SONGS and Talega Substations.
According to the report, weekly field inspections were made during the grading
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activity that occurred during the period October 1978 through May 1979. As the result of the inspections, some erosion control work was performed. On October 23, 1980 Civil / Structural and Land Planning Engineers conducted an inspection and found that plant growth had returned to a state of equilibrium along the entire transmission line.
Hydroseeding of the access road bank slopes to one tower was performed on October 28, 1980 and inspection will continue through the rainy season until the area returns to equilibrium.
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-2-3.
Precoerational Testing Procedures
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During the inspection, the following three preoperational testing procedures were examined. Their format was found to be as described
in paragraph 3 of IE Inspection Report No. 50-361/80-20.
a.
Procedure No. GT-500-06, Revision 2, General Test Procedure for Testing, Balancing and Adjusting HVAC (heating, ventillation and air conditioning) Systems.
This is a general test procedure that is intended to be incorporated, as applicable, into the preoperational testing procedures for the various HVAC systems.
It establishes the sequence of operations to be performed and provides the various data recording sheets to be used.
A random examination of sequences did not identify any deficiencies in this procedure. The procedure had been approved by the BPC (Bechtel Power Corporation) Startup QA Superviscr, The BPC Project Startup Engineer, and the Prerequisite Test Operations Supervisor, b.
Procedure No. 2PE-516-01, Revision 0, Fuel Handling Building Normal and Emergency HVAC This is the procedure for the preoperational testing of the Fuel Handling Building HVAC System.
The procedure has been approved, as indicated by signature, by the author, the Test Procedure Preparation Supervisor, the TWG (Test Working Group) Chairman and members, and the SCE Startup QA Supervisor. According to the applicant, this procedure will require at least one additional revision because the data sheets resulting from incorporating procedure No. GT-500-06 will need-to be attached to the procedure. Also, two additional
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general test procedures addressing the testing of HEPA (high
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efficiency particulate air) and charcoal filters will be incorporatad when they have been completed. The prerequisites include completion of the preoperational testing of the Process
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Radiation Monitoring System and the holding of a pretest indoctrination meetir.g to familiarize test and operations personnel with the test requirements. Portions of the procedure were examined in detail. With the assumption that the above described changes are made, the procedure appeared to provide the necessary testing to assure the system would operate as described in the FSAR.
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Procedure 2PE-511-02, Revision 0, Control Room Complex Normal and Emergency HVAC This procedure had just been revised to incorporate procedure No. GT-500-06 and the related data sheets.
The procedure may
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-3-need some additional modification when the general test procedures for the HEPA and charcoal filters have been completed.
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Those portions of the procedure that were examined in detail appeared to provide the necessary testing to assure the system would operate as described in the FSAR.
No items of noncompliance or deviations were identified.
4.
Process and Effluent Radiol _ogical Monitoring Systems The inspection included a checking of the locations of the process and effluent monitors and, where applicable, the sampling lines leading to and from them. A total of 15 monitoring systems have been identified in Table 11.5-1 of the FSAR.
Eleven (11) of these systems were found to be installed as described in the FSAR (11.5.2).
Of the remaining four, three (containment purge and plant vent stack wide range, main steam line and normal sample lab isolation monitors) have not yet been received.
The final unit, the condensor air ejector gas monitor, was found to be in the Turbine Building as described; however, it was not determined whether this was a single unit with two ranges or a second unit with a wide range was still to be installed.
While checking on' the process and effluent monitors, the sampling lines to these monitors were also examined. With one exception, the sample lines going to the airborne monitors included 45 degree
. angle bends and 90 degree angle bends with large radii. -The sampling lines to the plant vent stack and radwaste disposal area vent airborne monitors were estimated to be in excess of 50 feet, a-portion of which was exposed to atmospheric temperature and weather.
The' sample line to the condensor air ejector monitor included some very short radius 90 degree. bends. According to the applicant's personnel contacted, the effect of the long sample lines, some of which are exposed to atmospheric temperatures, had not been evaluated with respect to the particulate and iodine samples being representative of the effluent stream.
Also, there had not been any. evaluation of possible effects on the representativeness of the condensor air ejector samples due to the short radius 90 degree bends in.the sample lines (there are no effects on noble gas sampling).
No items of noncompliance or deviations were identified.
5.
Area and Emergency Radiation-Monitors
.While checking on the monitoring systems described in the previous paragraph, area and emergency radiation monitors in the same general locations were also observed. These included all of those monitors
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-4-listed in Table 12.3-2 of the FSAR except for the one in the radiochemistry lab and four of the seven located inside the containment building.
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The two high range monitors in the containment building have not been received and installed.
One of the containment monitors was inside a locked area and, thus, was not accessible.
The containment monitor next to the personnel access lock has a second readout at the west end of the penetration building on the 45 foot level.
Ali of these monitors readout in the area of the control room.
No items of noncompliance or deviations were identified.
6.
Staffing and Organization At the time of the inspection, a total of ten (10) persons were assigned to the Chemical and Radiation Protection organization for Units 2 and 3.
These 10 consist of two Engineers, one of which is acting as the group supervisor, a Radiation Protection Foreman, a Technician acting as a Radiation Protection Foreman, and 6 technicians.
One additional technician will be added to the staff on March 1,198!.
Of the six technicians, two presently meet the qualifications in Paragraph 4.5.2 of ANSI N18.1-1971, " Selection and Training of Nuclear Power Plant Personnel."
The applicant has provided contractor support to the Chemistry and Radiation Protection organhation.
NUS Corporation has provided 4 persons to write procedures in the areas of chemistry and health physics. The procedure writing involves both Unit I and Units 2 and 3.
In addition, a Radiological Engineer has been hired for i
about 6 months to work for the Supervisor of Chemistry and Radiation Protection, Units 2 and 3.
The contract Radiological Engineer's assignment has included some training of the new technicians.
The applicant explained that changes in the Site organization will l
occur in the near future; however, they must be approved by the NRC prior to implementation because a change in the Unit 1 technical i
specifications is required. The proposed change will impact on the Chemistry and Radiation Protection' organization.
First, Chemistry and Radiation Protection (or Health Physics) will be separated with the manager of the latter reporting to the Plant Manager and the
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supervisor former reporting to the Assistant Plant Manager - Technical.
j The technicians will be divided into chemistry and health physics
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responsibilities with separate qualifications and training for each.
The new organization will provide'for additional personnel in the areas of chemistry and health physics over the current organization.
No items of noncompliance or deviQbri were identified.
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Training
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The four new technicians have received some training, but it has been stopped because of the need to use them during the "precore hot functional test." This test was initiated during the week of January 26, 1981 and is scheduled to last for a period of 54 days at an elevated temperature. The new technicians have received some training in the area of plant systems. Training connected with procedures' related to health physics and radioactive waste cannot be started until after the procedures have been written an-approved.
It is hoped that the procedure writing process will be completed by mid February 1981. There does not appear to be a formal training program to assure that the chemistry and health physics technicians have been adequately trained prior to loading fuel into Unit 2.
tio items of noncompliance or deviations were identified.
8.
Laboratory Capability Presently, the status of the radiochemistry laboratory is such that its capability to analyze flRC qualification samples will not be attained until sometime in May of this year. While the laboratory is in place and some equipment have been installed, certain key systems (Viz, the gamma spectroscopy and beta systems) have not as yet been brought on line.
These systems are expected to be ready
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for performing measurements by sometime in April. When the laboratory is ready to analyze the qualification samples, arrangements will be made with RESL (Radiological and Environmental Sciences Laboratory, Department of Energy, Idaho) to have these samples fabricated and sent to the Unit 2 laboratory.
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'9.
Exit Interview At the conclusion of the inspection, the inspector met with those persons identified in Paragraph 1 of this. report.
Mr. D. E. Nunn, Manager of SCE QA, was also present. Mr. R. J. Pate, NRC Senior Resident Inspector was in attendance. The scope of this inspection and the findings were described. The applicant was informed that there were no items of noncompliance or deviations.
The following items were also discussed, a.
The examination of the sample lines leading to some of the process and effluent monitors disclosed two details that may effect the representativeness of sample collection relative to these monitors.
The specifics described in Paragraph 4 of this report were discussed.
The possible effects of these two datails (long lines and short radius right angle bends) on the adequacy of the sample collection for particular activity and radiciodines should be evaluated.
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The work load of the Chemistry and Radiation Protection organization
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is increasing as preoperational testing proceeds. The SCE
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staff will need to be expanded in the area of chemistry and
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health physics prior to fuel loading to provide the personnel to perform the required functions.
These new staff members
will require training to be able to perform their assignments.
and assist with.the increasing work load. The importance of
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increasing the staff as soon as possible was stressed.
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