ML20027E168
| ML20027E168 | |
| Person / Time | |
|---|---|
| Site: | 05000000, San Onofre |
| Issue date: | 07/26/1973 |
| From: | Fish R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Coryell G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20027A625 | List:
|
| References | |
| FOIA-82-394 NUDOCS 8211120185 | |
| Download: ML20027E168 (9) | |
Text
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- 9., s July 26, 1972 G. P. Coryell, Euel Facilities Inspectop !
Region III, Directorate of Regulatory Operations SURVEY OF IRRADIATED FUEL SHIPPING CASKS, SAN ONOFRE REACTOR Attached is a copy of a survey record obtained during my recent inspection of the radiation safety program at the San Onofre facility. The survey is for smearable contamination on the three irradiated fuel shipping casks.
All three casks were received at San Onofra during August 1971 Cask No. 470035 was placed in the pool of the fuel storage building sometime during the period between the receipt and the date of the survey (January 4, 1972). This explains the high values for numbers 1 - 10 on the record. The other results represent the conditions of receipt for the other two casks since they were only stored during the period.
Please
,gte that all results (beta-ganrna and alpha) are in units of disintegrations per minute per square foot.
If you have any questions about the interpretation of the survey record, please let me know.
Original sv.rJ by R. F. Fish, Jr.
R. F. Fish Reactor Inspector Enclosure As stated orrect >
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i,.1 U. S UCLEAR REGULATORY COMMISSION
' OFFICE OF INSPECTION AND ENFORCEMENT kEGIONV 4
CIE Inspection Report No.
50-206/75-01 Licensee Southern California Edison Company Docket No.
50-206 2244 Walnut Grove Avenue License No. DPR-13 F.csemead. California 91770 '
Priority Facility _
San Onofre Unit I category c
Location Camp Pendleton, California Type of Facility PWR (450 MWe, 1347 MWt)
Type of Inspection Routine, Unannounced Dates of Inspection January 20-23, 1975 Dates of Previous Inspection October 7-10, 1974
$2//8/7I Principal Inspector "R.' T. Dodds, Reactor Inspector
/Da t'e Accompanying Inspectors y
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R. F. Fish, Radiation Specialist
/Dade Date Other Accompanying Personnel:
None Reviewed by fA wC2 '
G. S. Spencdr, Chief, Reactor Testing and Operations Date Branch VT -
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' H. E. Book, Chief, Radiological and Environmental Date Protection Branch f
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\\. b.
The licensee has initiated action to implement the additional environmental monitoring programs required by Appendix B to the technical specifications which became effective on November 22, 1974. A QA manual applying to all activities required by Appendix B was being prepared for submission to the Commission.
The licensee had requested bids from outside the company for.
performing activities in Sections 3.1 and 4.0 of Appendix B of the technical specifications.
- 16. Primary Coolant Quality Samples of primary coolant water have been normally collected daily for five days in a week.
Once a week a portion of the sample has been analyzed in the gamma ray spectrometer to determine the average energy of the isotopes present after a decay period of four hours. The average energy is used to determine the limit of activity allowed in the primary coolant by technical specification 3.1.1.
The analyses of the primary coolant water samples for the year 1974 were examined. The allowable limit varied over the range of 201 to 510 microcuries/ cubic centimeter. The analyses showed the actual activity present in the primary coolant water varied over the range of 0.008 to 0.238 microcuries/
cubic centimeter.
- 17. Shipping of Spent Fuel The licensee has a procedure for receiving, loading, and shipping the spent fuel cask used to date.
The procedure requires the completion of six forms which contain pertinent information to be retained - receipt form (cask condition), shipping report, notification of consignee, equipment (truck and trailer) inspection, fuel shipment check off list, cask coolant and water analysis.
The licensee's records also include a copy of the bill of lading and the survey records for the receipt of the cask and after loading.
The records showed that during 1974 there were three such s'nipments of one element each. The actual receipt of the cask and loading of the spent fuel has been performed by Westinghouse personrel under contract to SCE.
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f U. S. ATOMIC ENERGY C0:e:ISSION DIRECTOPJ.TE OF REG'JIATORY OPEPATIONS PIGION V 050-0206/72-04 RO Inspection Report No.
Docket No. 050-0206 Southern California Edison Co.
' Licensee:
License No. (s) DPR-13 Priority Facility:
San Onofre Unit No. I Category C
en15fnrnin Location:
con cl or,gn, o ;
Westinghouse PWR, 450 We,1347 MWt Type of Facility:
Type of Inspection: Routine, unannounced Dates of Inspection:
October 25-27, 1972 July 10-13, 1972 Dates of Frevious Inspection:
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(Date) 1 Principal Inspector: A. D. JoEn 'on, Reactor Inspector
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(Date)
AccompanyingInspectory:'W.G.Albpt, Reactor Inspector f
8 (Date) s None Other Accompanying Personnel:
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- 28%C#m (Date)
Reviewed by:
G.S.Spenber, Chief,ReactorConstruction and Operations Branch
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O e.
Continuous Particulate and Iodine Stack Monitor - The licensee stated that management approval had been obtained to install a particulate and iodine sampler to continuously monitor stack effluents.
The licensee also indicated that the system should be designed _and insta? led within the next six months.
f f.
Contamination Control - The inspector observed a portable radiation survey instrument located at the entrance to the exclusion area containing reactor coolant cleanup equipment where significant levels of contamination are encountered at times. The licensee stated that, in addition, a portable survey instrument has been located at the area where fuel casks are loaded onto the trailer. Also, whenever significant levels of contamination are encountered within the restricted area of the plant, monitors will be provided to enable personnel to check themselves as they leave the particular area and thus more effectively confine significant levels of contamination to localized areas.
3.
Unusual Occurrences a.
Steam Generator Leakage - Leakage of primary coolant into the
- secondary coolant has occurred as a result of defective tubes in both the A and C steam generators.
The following was learned from an examination of the licensee's records of the circumstances associated with the leakage in each steam generator.
(1) Steam Generator "C" An increase in the concentration of radioactivity was detected in the generator blowdown on July 8, 1972. Further analyses of samples taken on July 10, 1972 confirmed that "C" steam generator was the source of the activity. The leakage was calculated daily from activity concentrations until July 18, 1972 at which time the leakage rate was recorded to be approximate 1g 100 gallons / day.
The unit was removed from service on July 19, 1972 to locate and isolate the defective tubes in the steam generator.
According to the records, the secondary side of the generator was hydro-statically test at 800 psig and a defective tube was identified.
In addition 819 tubes were checked for defects by use of the eddy current test technique. According to the licensee, there
,q U. S. ATOMIC EllERGY C')MMISSION e
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DIRECTORATE OF REGUllsTORY OPERATIONS REGION V RO Inspectio'n Report No. 050-0206/72..
Subj ect: Southern California Edison Company San Onofre Nuclear Station Unit No. 1 License No. (s) DPR-13 Location: San Clemente Priority California Category C
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Type of Licensee: Westinnhouse - 450 Mm. PWR 1
Type of Inspection:
Routine, Unnnnounced ii li ll Dates of Inspection: July 10. 11. 12 and t's.
1977 i:
' :l Dates of Previous Inspection: April 30. Hw 1 nnd 10. 1977 Principal Inspector:
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A. D. Jo n on, en tor Inspector
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e' /F Accompanying" Inspectors:
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W'. G. Alb
,-Pedctor In'spector
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R. F. Fish ndiation Sp'e/iaIist
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Other Accompanying Personnel: None 8
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, Chief, Reac' tor Construction and
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Operati Branch Proprietary Informati
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'At 5 : 25 a.m. on June 5, 1972 an operator, while cleaning the' control panel, bumped the gain potentiometer dial on nuc1 car instrument channel 1206.
This activated the dropped rod circuitry and resulted in a unit runback from 450 Uwe to 260 Mwe.
The unit returned to 450 Mwe at 5:57 a.m.
The dials on the potentiometer have been replaced with ones having locking devices to preclude accidental movement.
e.
The reactor scranned on April 30, 1972 due to a high steam generator level caused by a feedwater regulator failure. A special inspection was conducted by RO:V to investigate the cause and corrective action.
The results of this inspection were reported in RO Report No. 050-206/7202.
f.
The initial shipment of spent fuel assemblies for reprocessing started in March 1972.
Sixteen assemblies had been shipped to Morris, Ill. by June 30, 1972.
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2.
Organization and Administration Plant organization structure and changes in personnel assignments.
a.
b.
Onsite safety review commit tee minutes.
c.
Watch engineers logbook (February-June 1972) d.
Control operators logbook (July,1972) e.
Operation monthly summary reports (January-June 1972) j f.
Unusual occurrence reports (February-June 1972) g.
Responsibilities and activities of SCE and Westinghouse during refueling outages.
j h.
Division orders and instructions establishing supe'rvisory review responsibilities and methods for preparation of control operator and watch engineer logbooks.
3.
Procedures a.
Revision request under review.
(5) b.
Temporary operating instructions.
(5) c.
Routine reactor coolant system inspection for fluid leakage, d.
Documentation of reviews and opprovals of 14 procedure changes.
e.
Division and station orders controlling dissemination of information to plant personnel.
f.
Refueling surveillance nnd responsibilities.
(SCE & Westinghouse) 4.
Reactivity and Power Control a.
Cycle 3 beginning of Itfe (noL) physics tests and results.
b.
Daily reectivity follow data.
c.
Investigation results of a shif t of 25-30 ppm in the reactivity follow curve.
(April) d.
Control rod drop test data.
e.
Incore temperature maps.
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5.'
Elect ical i
n.
SCE's protection engineers evnluation of paralleling power sources during generator antimotoring period.
b.
Relay test history forms. (1972)
Circuit breaker test inspection data.
(1971) c.
d.
Transformer combustible gas data.
(1972) e.
Disconnect inspection data.
(1972) 6.
Power conversion System "C" stenm generator leaknge (R0 Inquiry Report No. 206/7204) n.
b.
Feedwater regulating valve positioners.
i 7.
Primary Coolant Systems Plan to install continuous recorders on temperature sensors a.
located in the cold legs of B nnd 0 loops.
b.
Evnluation of desirability of starting primary coolant pumps during a reactor depressurization condition from feedwater control malfunctions.
(No change in procedure recommended) c.'
Plan to install an additional reference column for the pressurizer level and pressure sensing instrumentation.
.d.
Vessel head stud protection during shutdown periods - Refueling 1
instructions RF-2 and RF-9.7.
c.
Primary coolant Icagage test data.
(1972) f.
Examined instructions (S-3-1.9 and S-3-5.23) and performance of a hot leak rate test.
(See Paragraph 16 of this repo:t) i g.
Use of Vane type flow switches (none).
8.
Auxiliary Systems 4
Plan to install an additional power supply to volume control a.
tank shutoff valve.
b.
Plan to install a recorder on the volume control tank Icvel sensing instrumentatio..
n 9.
Fuel Handling i
Observed performance of fuel nhlpment including cask lid placement, a.
removal from loading pit, initini wash, decontamination, lid fastening surveying and loading of ca sk on truck.
b.
Antisiphoning protection for spent fuel pit.
(See Paragraph 17 of this report) 1 e
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been established for changing inline filters in the auxiliary building.
According to this REP, the following protective clothing and gear were i
to be worn when changing the filters:
coveralls, underwear, surgical cap, shoe covers, gloves, and face shicid.
On July 11, 1972 a maintenance employee was observed entering the auxiliary building for the purpose of replacing an inline filter. He wore the following protective clothing:
a surg'ical cap, gloves, laboratory coat, plastic shoe covers taped at i
j the top.
Rubber shoe covers were locnted inside the main entrance to the building and it was reported that a face shield was kept inside the
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building for this type of activity.
During the management interview it was reported that, shortly af ter the observation, the maintenance employee was instructed to leave the auxiliary building inmediately and dress as required.
Also a monitor had apparently informed the maintenance employee that he was improperly dressed before he entered the auxiliary building.
Appropriate Icvels of supervision were notified of the
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observed deficiency and management has taken action to assure compliance
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with the REP require'ments.
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/ 23.
Use of Portable Survey Meters f
On July 11, 1972 a tour was made of the facilities outside the contain-ment sphere and the loading of a cask containing an irradiated fuel element onto a trailer for. shipping to a reprocessing facility was observed.
Plant personnel were observed entering and Icaving an exclusion area where no survey instrumentation was provided at the entrance. An examination of the survey records showed that this exclusion area, containing reactor coolant cleanup equipment, had l
removable contamination which sometimes reached the level of a few hundred thousand disintegrations per minute per square foot.
The exclusion areas are all located within controlled areas. Appropriate survey and monitoring instrumentation is located at the entrance to controlled areas.
The cask loading operation took place in the yard at the end of the turbine deck.
Because of the modified design of the cask, a very small amount of low Icvel contaminated water drained from the cask during the operation of lowering the cask to its final shipping.
position.
Absorbent material had been positioned to collect this drainage.
No portable or other survey instruments were in the area where the loading uns taking place. The cask was decontaminated and surveyed prior to' being removed from the fuel storage butiding.
After being loaded onto the trailer, another survey of the cask was made and necessary additional decontamination of.. small area was performed to reduce removable contamination levels to less than the allowable limit of 2200 disinte-grations per minute per 100 cm.
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