ML20126A669
| ML20126A669 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/22/1983 |
| From: | Winso J GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
| To: | Wigginton J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML20126A656 | List: |
| References | |
| RTR-NUREG-737 NUDOCS 8506130422 | |
| Download: ML20126A669 (3) | |
Text
Enclosure 1 r ay.ug:,,
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GA Technologies Inc.
P.o. Box 01608 sam osco. cAtromwA s2iss July 22, 1983 f619) 455 3000 Mr. Jim Wiggington Office of Inspection and Ehforcement U. S. Nuclear Regulatory Commission E-W/S 312A Washington, DC 20555
Subject:
Concerns at San Onofre Nuclear Generating Station Relative to GA Technologies Inc. Wide Range Gas Honitor Systems
Dear Mr. Wiggington:
Per our recent telephone conversation, the following co:r.ments are offered relative to the subject concerns.
It should be noted that the San Onofre Wide Range Gas Monitors (WRGMs) were shipped in February 1981 and were the first field installation of the GA Technologies WRGM.
GA personnel c
worked very closely with Southern California Edison and Bechtel personnel at that installation to resolve problems which arose and also to improve the product.
A ntaber of hardware and software design changes were effected as a result of that effort.
All of the concerns which we discussed have been corrected by these design changes and have been or are being implemented in all other installations of the WRGM.
Specific comments to the concerns discussed are as follows:
1 1.
High Range (RD72-1 and RD72-2) and low Range (RD52) detectors calibration:
Calibrations performed by Southern California Edison with an NBS 4*"g traceable source indicated that the GA Honitor was producing a o
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reading that was excessively high and beyond the accuracy range specified by the San Onofre specification (but not beyond the factors required by Reg. Guide 197 Rev. 2).
Upon investigation, o
GA determined that the gas used for primary calibration by GA had 7
introduced errors which were not detected.
For this reason, new samples of NBS traceable gas was ' purchased and the primary g<
calibrations were re-performed.
m During this recelibration, it was determined that the high range ma.o detectors RD72-1 and RD72-2 had unique characteristics which would require a direct calibration of each unit to reach an optimta accuracy figure.
It was also determined that the solid source calibration did characterize the reading obtained directly with a gas sample to a highly accurate degree.
Details of these 59 4
conclusions are included in the re-issued calibration reports
[
E-255-961 Rev. 2 (for the RD72) and E-115-647 Rev. 4 (RD52) which
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are attached to this correspondence.
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GA is currently in the process of re-calibrating all detectors in the field to insure an optimum accuracy and all customers of the Wide Range Gas Monitor have been notified of this policy.
The -
exact schedule for this calibration is being worked out between each of the customers and GA.
2.
Software Qianges:
Several improvements in the software program in the Microprocessor (RM-80) associated with the Wide Range Gas Monitor were made by GA on the San Onofre Units. The concerns described relative to the appropriate stack area were a problem in the early GA System in that the Microprocessor Controller did not recognize that stacks with different cross-sections could be selected.
PROM units with the new software have been distributed by Fco 033, June 22,1982.
In addition, changes were made to:
a)
Add programming to suppress noise being induced into the detector electronic circuitry when either pump motor was energized or de-energized.
b)
Correct an error condition in the program used to sense loss of sample flow.
c)
Added feature to allow for resetting the output of the smoothing algorithm to more easily establish background.
3 Oscillations of signal:
The problem referred to is believed to be an Electromagnetic Interference (Noise) problem which resulted from insufficient shielding of the CdTe High Range detectors.
This problem has been corrected by changing connections on the OdTe detectors and has been implemented by Field Change Order (FCO) 032. (July 7,1982)
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59 4 2
4 Wiring Deficiencies:
An RM80 Microprocessor Junction Box was reportedly miswired and rewired by SCE in the field.
Investigation indicate that the g
wiring either was proper or was brought to a proper state by SCE personnel.
In any event, all the related documentation has been reviewed and determined to be correct.
Also, the unit is currently wired to its proper configuration.
GA believes no further action is required for this item.
If there are any further questions concerning these items or any other items relative to GA Technologies Radiation Monitoring Systems.,,please contact the undersigned at (619) 457-8845.
Sincerely,
[yC.O b O J. H. Winso 1
JIN/11a bec:
W. Compas D. Eit: man D. Kau
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R. Perkins G. Simmons 4
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UNITED STATES NUCLEAR REGULATORY COMMISSION d
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.,I REGION V 14s0 MARIA LANE,sulTE 210 Q,
% *.. *,&g WALNUT CREE K.CALIFoRNI A e45ss cr MAR 071985 Docket Nos. 50-206, 50-361, 50-362 Southern, California Edison Company l
2244 Walnut Grove Avenue i
Rosemead, California 91770 Attention:
Mr. Kenneth B. Baskin, Vice president Nuclear Engineering, Safety and Licensing Department Gentlemen:
Subject:
NRC Inspection San Onofre Units 1, 2 and 3 This refers to the routine inspection conducted by Messers H. North, C. Sherman and M. Grayson of this office on January 28 - Februsry 1, and telephone conversations on February 8 and 12, 1985 of activities authorized by NRC License No. DPR-13, NPF-10 and NPF-15, and to the discussion of our findings held by Messers North and Grayson with Messers. Haynes and Krieger and other members of your staff at the conclusion of the inspection.
4 Areas examined during this inspection are described in the enclosed inspection report. Within these areas, the inspection consisted of selective examinations of procedures and representative records, interviews with personnel, and observations by the inspector.
No items of noncompliance with NRC requirements were identified within the scope of this inspection.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room.
Should you have any questions concerning this inspection, we will be glad to discuss them with you.
Si erely,
))
hAA>_ _ _
^
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F. A. Wenslawski, Chief Emergency Preparedness and Radiological Protection Branch
Enclosure:
Inspection Report No. 50-206/85-03,50-361/85-02,50-362/85-02 cc w/ enclosure:
D. J. Fogarty SCE d.
H. B. Ray SCE J. C. Baynes SCE (San Clemente)
State of CA
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION V c
i Report Nos. 50-206/85-03,50-361/85-02,50-362/85-02 3
Docket Nos. 50-206, 50-361, 50-362 License Nos. DPR-13, NPF-10, NPF-15 Licensee: Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name: San Onofre Units 1, 2 and 3 Inspection at: San Onofre Nuclear Generating Station Inspection conducted: January 28 - February 1, 1985 and telephone conv rsations on February 8 and 12, 1985
.3 85" Inspectors:
R'. S. North, Senior Radiation Specialist Date Signed b
OM 2cn 3/6/ W M.Grafsdp,Radiatic@pecialist Date Signed
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$/n C. Sherman, Radiation Specialist Date Signed Approved by:
M Nob s 2/6 / f(
GT P. Yqh4, Chief Da'te Signed Facilitill1r Radiological Protection Section Summary:
Inspection on January 28-February 1, and telephone conversations on February 8 and 12, 1985 (Report Nos. 50-206/85-03, 50-361/85-02 and 50-362/85-02)
Areas Inspected: Routine, unannounced inspection of licensee action on previous inspection findings, organization and management controls, external occupational exposure control and personal dosimetry, followup of onsite events, inquiry into possible high beta exposures at Unit 2, review of licensee reports, facility tours, Unit 2/3 HP laboratory instruments, waste shipment documentation error and followup on Information Notices.
The inspection involved 86 hours9.953704e-4 days <br />0.0239 hours <br />1.421958e-4 weeks <br />3.2723e-5 months <br /> onsite by three NRC inspectors.
Results: Of the areas inspected no violations or deviations were identified.
One unresolved ites relating to possible high beta exposures in Unit 2 was identified.
Details Persens Contacted.
'*J. Haynes, Station Manager
- R. Krieger, Deputy Station Manager J. Albers, Health Physics'(EP) Supervisor Unit 2/3 J. Aspevig, HP Foreman i *E.<Bennett, Quality Assurance (QA) Engineer lL. Bray, BP Engineer 4
D. Brevig, Supervisor Chenistry S. Brooks, General Foreman, Radwaste, RHC J. Brown, HP Technician, Rad Services M._ Grove, HP Foreman
- D. Herbst, Supervisor ISEG i
T. HIrring, Supervisor, Technical Services, Radwaste
- R. Jervey, QA Engineer J. Kelly, Supervisor Radwaste
- P. King, Supervisor Operations QA
' P. Knapp, Manager HP 4
i
- R. Kurisu, Supervisor,' Corporate Document Services
- T. Mackey, Supervisor Compliance D. Madson, HP Technician, Rad Services R. Neal, Supervising Engineer, NSSS, Electrical Engineering P. Nelson, KP Technician
- G. Psckham, Supervisor Dosimetry
- J. Reilly, Manager, Technical Division R. Reiss, QA Engineer R. Rosenblum, Manager, Nuclear Safety Group, Corporate
- M. Speer, Compliance Engineer D. Stickney, Cognizant Engineer, Unit 2/3 Rad Monitoring Systems i
K. Swoope, HP Engineer
- R. Warnock, Supervisor, HP Engineering
- P. Wattson, compliance Engineer
- J. Wray, Senior Health Physicist, Corporate i
F. Yang, Dosimetry Shift Supervisor
! *Denttes those present at the exit interview on February 1,1985.
In addition to the individuals identified above, the inspectors met and held l
discussions with other members of the licensee's and contractor's staff.
l 1
Lien see Action on Previous Inspection Findinas l
(0p n llowup (50-361.50-362/84-12-01) t Itsp;ction Repo os. 50-361/84-50-362/84-12 addressed concerns l
relcted to the nagn o
uid radwaste releases when compared with TSAR estinated releas icensee's response to the concerns id::tified and ssed in Insp on Report No. 50-361/362/84-12 were exaained.
ebruary 1,1985 the 1 e established a project i
ded to reducing liquid effluents. W three months the licensee
- cts to have plans established for a' course o on.
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effluent had established that the nuclides of greatest concer niobium and cobalt, were present as colloids which were not removed the existing filtration and ion exchange system. The licensee lans to test ilters.to identify those which are most effective in r ving colloidal terial. The licensee stated that no recycling of wat to the reactor co lant system (RCS) was attempted due to possible uni entified con amination with organic material.
This problem been addressed in seve 1 IE Information Notices and an INPO Signific t Operating Exper nce Report. The licensee stated the signif'cance of contamination of the CS with organic. material was still under nyestigation. A review.
m of liqui vaste release estimates in the FSAR v planned since it had been prep ed before the organic contamination roblem was identified.
FSAR estima es of releases were based on recy ing liquid waste.
The study wil address possible waste sour e separation including storm, oily waste and loor drains. The license stated that construction of additional stora capacity to minimize eleases was not possible due to land use limitatio s.
The licensee's al is to achieve a 10 fold reduction in the le 1 of liquid wast s.
The licensee's efforts to reduce liquid radwas effluents wil be examined during a subsequent inspection.
(Closed)(50-206/82-36-04 Inspec or identified item involving saturation of the operational radiati no itoring system (ORMS) channels. The licensee issued procedure S
.2-1 which provided for administrative control over down scale fail This procedure gave plant operators information on recognizing i condition and provided for appropriate action. This procedure va foun acceptable by the inspector. This matter is considered clo d.
(Closed)(50-206/84 ) Inspector i entified item involving correction factors for main stea line monitor.
e licensee has incorporated these correction factors i EPIP S01-VII-40-10. The procedure was examined by the inspector and f und to implement the idance of NUREG-0737 and Regulatory Guide 1.97 Rev. 2.
The inspecto had no further questions on this matter.
(Closed)(50-20 /82-36-05) Inspector identified i em involving control of Waste Gas Dis arge Valve SV99. The licensee has ompleted transfer of control of t is valve from R-1214 to R-1219. Testi of R1219 and control of 99 was completed prior to return to se ce. The inspector verified examination of SONGS Retrofit Station Turn ver Form for DCP 83-037-0.00SJ(Z) and DCP-83-037-01.01SJ and by discuss n with personnel that th work was completed satisfactorily. This matter is considered closed (Ope of liqu(50-206/82-36-06) Inspector identified item involving rovement id effluent discharge monitor R1218. By letter dated Oc ober 9, 1994 E. Ray (SCE) to J. Martin (NRC) the licensee committed to installation and testing of a new nonitor or to notify the NRC if air scheduled installation date was delayed.
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The inspector was notified that the completion date will likely be three t
months beyond that initially projected. The inspector determined that the basis for delay was acceptable and would not violate any regulatory requirement. This matter will be resolved after satisfactory completion of installation and testing of monitor R-1218.
(0 pen)(50-361,50-362/83-08-03) Inspector identified ites involving effluent monitor sample line plateout testing. A report on plateout tests prepared by the licensee's contractor had been received in final ford by the licensee. The licensee representative agreed to make this report available to the inspector after it had been examined within the licensee organization. The report and the licensee's implementation of plateout correction factors will be examined in a subsequent inspection.
(Closed) (50-361, 50-362/83-08-01, -02) Inspector identified item involving problems with calibration of the General Atomic (GA) wide range gas monitor (WRGM) detectors RD-52 & RL-72. The licensee hss received updated topical reports from GA E-255-961 Rev. 2 (RD-72) and E115-647 Rev. 4 (RD-52) and reviewed them for applicability. The licensee had
_.A installed a vendor field change to improve repeatibility of the calibration constant with the RD-72.
The licensee reports that even with
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the field change reproducibility is not as good as desired. The licensee, therefore, has continued to perform primary calibrations with Xe-133 gas and is developing a transfer calibration program using Kr-85 gas.
This matter is considered closed at San Onofre based on the primary calibration program implemented by the licensee.
This matter will be referred to NRC:IE for review of generic applicability.
No violations or deviations were identified.
Organization and Management Controls ho nificant changes have occurred in the Health Physics Depar t organization since the inspection document n Inspection Report Nos.
-206, 361, 362/84-02.
The organiza n includes the Unit 1 HP staff of 31, it 2/3 HP staff of 57, Radv e staff of 93, Dosimetry staff of 47 and a' ngineering staff of The Health Physics Manager had a total staff of 2 neluding 117 and 120 contract employees on December 31, 1985.
The con et esp ees were concentrated principally in the Radwaste (84) and Dosine
- 26) groups.
The licensee is presently no ng in the ection of site wide qualification of all EP 7 icians.
To ac ve the desired goal HP Technicians will need complete the Qualific ons Manual and pass the journeyman exam on a Units.
In addition for an Technician to be qualified to appr e Radiation Exposure Permits (REP ree years of power plant EP erience is required. A new position o General Foreman for the EP T icians is being considered. The position w Id be nonsuperv ry and would function to coerdinate allocation of chnician resourc to the three units.
Th tation Chemistry Manager report s to the Manager, Technical Division.
e Chemistry Department includes Units 1 and 2/3 laboratories, Effluents Special (engineering).
The available staff includes 45 SCE and 14
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contractor staff.
In the past 1 years the number of contractor employees has been reduced by approximately 50%.
i Tbn EP and chemistry orgnizations. incorporate training and retraining programs which Anclude qualification manuals, formal classroom training and self study. Based on discussions with licensee personnel, management had effectively considered training and had coordinated with the Training Department.
No concerns related to inadequate management support were identified.
- .All' managers, including the Health Physics Manager, are required to spend three hours per week in the plant.
A published schedule requires the canagers to examine areas other than those for which they have specific Reports of the managers observations responsibility every other week.
During weekly staff meetings managers report on the number are required.
of hours spent in the plant, on matters of interest and on identified weaknesses and corrective actions.
No violations or deviations were identified.
External Radiation Protection A.
Review of Changes to Facilities, Equipment, and Procedures L
The inspector reviewed changes in equipment, facilities and proc-dures which impact the licensee's programs for external exposure control or personnel dosimetry.
No significant changes in facilities, equipment, or procedures have occurred since the last inspection which would adversely affect the The licensee has licensee's external radiation protection program.
plans to move the TLD readers from trailer F-47 to the AWS building sometime around March 1985. The dosimetry department has recently There have been a number of purchased 800 to 1000 finger rings.
procedural changes during 1984 which are principally administrative The-inspector discussed. licensee plans to simplify and
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in nature.
clarify several dosimetry and contamination incident control and tracking procedures.
See report paragraph 4(D) and (E) for details.
B.
Dosimetry During the tour of the licensee's facility no instances of incorrect dosimeter placement or failure to utilize pocket dosimeters in accordance with Radiological Exposure Permits (REP's) were observed.
The license.'s dosimetry program was found to be consistent with 5
licensee implementing procedure S0123-VII-4.1.2, Rev. 2, " External Radiation Dosimetry".
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The inspector selected 7 licensee personnel monitoring files for review to determine whether records were being maintained in accordance with implementing procedure S0123-VII-4.1.1 " Personnel Monitoring Files". This review indicated that in several instances R
some of the the required monitoring information had not yet been placed in the monitoring files. Due to time limitations these s
.