ML20107G195
See also: IR 05000219/1975001
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RO:I Form 12
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(Oct 74) (llev)
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U.S. ATO> llc ITERGY CO'NISSION
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DIRECTORATE OF REGULATORY OPERATIONS
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REGION I
M, !;-j
RO Inspection Report No:
50-219/75-01
Docket No:
50-219
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Licensco:
Jersey Central Power and Light Company
License No: DPR-16
Madison Avenue at Punch Bowl Road
Priority:
Morristown, New Jersey 07960
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Category:
Location:
Oyster Creek, Forked River, New Jersey
Safeguards
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Group:
Type of Licencec:
Type of Inspection:
Snecial, Announced
Datos of Inspection: January 14-15,__17 and_20, 1975
Dates of Previous Inspection: November 19-22, 1974
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A /# 7)
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Reporting Inspector:
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E. G Gree
n Re et r Inspector
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Accompanying Inspectors:
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D. L. Ca
ton, Senior Reactor Inspector
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Date
Date
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Date
Other Accompanying Personnel:
None
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Date
Revicued By: _ f gV _ d a_
8[_[4-
D. L. Caphton'" enior keactor Inspector
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IE:I Operations Branch
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9604230139 960213
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DEKOK95-258
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SUMMARY OF FINDINGS
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Enforcement Action
A.
Infraction
1.
. Contrary to 10 CFR 50.59(c) and Supplement 2 to Amendment No. 68 -
Application For A Full Term License dated December 12, 1972, no
change was requested or authorized to;the commitment regarding
correction of exceptions concerning:
(a) capacity plate for the
auxiliary five (5) ton hook, (b) cab ladder and railing require-
ments and (c) crane warning device to signal crane movement.
(Details'5.1)
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B.
Deficiencies
None
Licensee Action on Previously Identified Enforcement Items
Not inspected
Design Changes
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Not inspected
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Unusual Occurrences
None
Other Significant Findings
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A.
Current Findings
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1.
Acceptable Areas
a.
Plant Logs and Records
An. audit of plant logs and records was conducted related to
spent fuel shipment.
(Details 3 and 5)
b.
Spent Fuel Handling Operations
)
Spent fuel shipments are in progress from Oyster Creek to
NFS, West Valley, N.Y.
Initial shipment was made January
18, 1974.
(Details 5)
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c.
Fuel Shipment and Survey Records
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An audit was conducted of fuel shipment and Health Physics
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survey and smear records.
(Details 6 and 7)
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d.
Chromate Water Removal
No chromated water now remains in temporary tank car storage
on site. Five (5) tank cars have been flushed and two (2)
have been released and removed from the site. .(Details 8.c)
e.
Bank Stabilization Program
Grading work is continuing along the length of the discharge
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canal.
(Details 8.d)
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B.
Status of Previously Reported Unresolved Items
Shift Manning Requirements (IE Inspection 74-07)
Licensee has assigned Radiation Technicians for operating shif ts.
Item is considered closed.
(Details 2)
Management Interview
An exit interview was conducted on January 20, 1975 with Mr. J. T. Carroll,
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Station Superintendent.
Inspection results were discussed further with
Mr. D. A. Ross, Manager, Nuclear Generating Stations by telephone on
February 19, 1975.
Items discussed are summarized below:
A.
General
The inspector summarized the scope of the special announced inspection
relative to review of records, procedures and handling operations in-
volving spent fuel shipments from the Oyster Creek site.
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B.
Personnel Safety - Cask Drop Protection System (CDPS) Area
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The inspector stated that he had observed inconsistencies in wearing of
life preservers by personnel in the spent fuel pool area and noted that
no hand rails were installed in the area of the CDPS for Safety.
A licensee representative acknowledged the inspectors remarks, and
stated that actions would be implemented to install an appropriate
barrier.
(Details 8.b)
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C.
Fuel Cask Handling Procedure
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'The inspector stated his position that the referenced procedure should-
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be reviewed and refined as necessary following initial shipment. Loca-
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tion of stop removal in the procedure was used as an example of the
inspector's concern.
A licensee representative stated that plans included a review and
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critique conducted by responsible personnel involved in handling
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operations.
(Details 4 and Sh)
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D.
Enforcement Action
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The Infraction listed under Enforcement Action above was identified as
an apparent item of noncompliance.
(Details 5.1)
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DETAILS
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1.
Persons Contacted
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Mr. D. A. Ross, Manager, Nuclear Generating Stations
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Mr. J. T. Carroll, Station Superintendent
Mr. D. L. Reeves, Chief Engineer
Mr. J. P. Maloney, Operations Supervisor
Mr. R. F. Swift. Maintenance Engineer
Mr. E. I. Riggle, Maintenance Supervisor
Mr. E. D. Skalsky, Radiation Protection Supervisor
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Mr. R. L. Stoudnour. Staff Engineer
Mr. F. H. Rodies, Engineering Assistant
Mr. G. Hicks, Shift Foreman
Mr.
D.' Arbach, Radiation Protection Foreman
Mr. D. Kaulback, Radiation P'rotection Foreman
Mr. F. Anderson, Mechanical Maintenance Foreman
Mr. T. L. Johnson, Instrument and Electrical Foreman - Nuclear
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Mr. B. Mays, Operating Foreman
2.
Administration and Organization
Shift Staffing - Radiation Protection
The inspector was appraised that effective January 5,1975, Radiation
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Technicians were assigned by the licensee, to operating shifts (one
per shift).
Implementation of this change meets the Regulatory staff
position on shift manning for nuclear power plants.* This item is con-
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sidered resolved.
3.
Logs and Records
The following logs and records were reviewed without comment except as
noted elsewhere within this report:
a.
Refueling Level Access Log - January 17-20, 1975
b.
Refueling Level Exposure Log - January 17-20, 1975
Spent Fuel Cask Handling Procedure 219 Revision 0, dated January 14,
c.
1975.
- IE-Inspection Report. 50-219/74-07, Details 3a.
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4.
Procedures
Fuel Handling
The inspector reviewed Plant Procedure 219, Rev. O dated January 14,
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1975 - NFS 4 SPENT FUEL CASK HANDLING PROCEDURE. The inspector veri-
fica that procedural changes required during the course of initial
procedural usage were completed in accordance with Technical Speci-
fication requirements. This procedure was discussed at the exit inter-
view with respect to additional PORC review and refinement subsequent
to initial shipment. This item will be reinspected during a future
inspection.
5.
Fuel Handling
a.
General
The inspector observed preparations for initial spent fuel ship-
The licensee was using the NFS 4 shipping cask.
Ship-
ments.
ments were scheduled for storage at Nuclear Fuel Services, Inc.,
West Valley, N. Y.
The carrier was Tristate Motors.
The initial
shipment of spent fuel bundles (two) designated JC 236 and JC 332
departed the Oyster Creek site on January 18, 1975. The NFS
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cask initially arrived on site January 13, 1975. According to
licensee representatives, arrangements have been made to transfer
approximately 240 fuel bundles on a long term basis. The licensee
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plans to terminate operations for receipt of new fuel, and during
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the annual refueling outage scheduled to begin March 30, 1975.
b.
Spent Fuel Pool Status
Prior to initiating spent fuel shipments the spent fuel pit con-
tained 308 fuel bundles. Total fuel pool capacity is 840 bundles.
Completion of licensee shipments will result in full core off-load-
ing capability.
This item is considered open pending reestablish-
ment of total core off-loading capability by the licensee.
c.
Crane Testing Requirements
The inspector reviewed the crane load test record for the facility
100 ton crane.
Records indicated that testing was conducted on
January 3,1975 utilizing the double hook and again on January 11,
1975 using the single hook.
Load application was the top north
reactor shield plug - total weight approximately 86 tons.
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inspection report documentation (QAIR No. 75-01 dated January 13,
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1975) verified crane testing for all modes of handling the load.
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A magnetic particle check was performed on the 100 ton crane hook,
results dated January 2, 1975.
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The inspector additionally verified on a sampling basis that
- procedures including preoperational checklists and physical
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exams for crane operators as defined in OSHA and Safety _ Code
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B30.2.0 were used for test performance and operational re-
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_quirements.. These items were considered acceptable *.
d.
Cask Dimensions, Weight, CG Location Lif ting Devices and
Handling Characteristics
The inspector reviewed documentation prepared by the licensee's-
consultant dated January 14, 1975, which indicated a compari-
son of the NFS-4 spent fuel shipping cask and yoke design had
been completed with respect to designs described in Supplements
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1 and 2 to Amendment 68 to the JCP&L application for a full term
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_ license. Characteristics were considered to be within the env-
elope of parameters established in the referenced supplements.
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This item was considered acceptable **.
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Diametral Clearance Between Case Base Plate and Top Plate
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Opening
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The inspector observed various portions of the cask manipulations by
the licensee and traverse from the refueling floor to the top plate
and entry into the cask drop protection system. The licensee con-
structed a mockup to demonstrate the ability to repetitively (twice)
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position the cask load within accuracies required by the transfer
path and insertion area. This item was considered acceptable ***.
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Cask Base Plate Attachment
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The inspector reviewed documentation from NFS dated January 13,
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1975 providing approval for the usage of a base plate as re-
quired by the Oyster Creek Cask Drop Protection System and the
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method of attachment'of the base plate to the NFS-4 cask.
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inspector also observed initial attachment operations during this
inspection. This item was considered acceptable ****.
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Limit Switch Performance Testing
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The inspector verified that two vertical limit switches were pro-
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vided to limit the height the cask was raised to six inches above
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the top plate of the guide structure. Both crane limit switches
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- DL letter to JCP&L dated April 13, 1973, Condition 7
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- IX letter to JCP&L dated April 13, 1973, Condition 1
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- DL letter to JCP&L dated April 13, 1973, Condition 2
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- DL letter to JCP&L dated April 13, 1973, Condition 3
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were set to limit vertical travel to approximately 5-5.5 inches
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above the CDPS' top plate upper surface. Additionally, procedur-
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- al requirements included "Go-No-Go" gauge verification to pro-
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vide assurance that base plate height did not exceed three (3)
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inches with respect to the CDPS top plate. This item was con-
sidered' acceptable *.
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h.
Bridge and Trolley Safety Controls and Procedures
The inspector verified that visual aids consisting of guide lines,
and mechanical rail stops had been installed. Stops were mounted
on bridge rails to prevent over travel of the crane in the North
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and South directions and on the trolly rails to prevent over
travel in the West direction. The inspector also verified that
stop installation was conducted in accordance with approved
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written procedures, and reviewed documentation from the licensee's
consultant dated May 21, 1973, establishing a perferred/ required
path of travel over the operating floor, to insure structural
safety of the floor system. This item was considered acceptable **.
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Observations of spent fuel shipping cask handling operations and
procedures for initial shipment disclosed no inadequacies with
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respect to path restrictions. The removal of the north rail stop
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following loaded cask withdrawal from the CDPS, prior to movement
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into the decontamination area was discussed at the exit interview.
This item is considered'open.
ggy
1.
Overhead Crane Compliance with OSHA
29 CFR 1910 Subpart IV 1910.179
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The licensee had stated in Supplement No. 2 to Amendment No. 68
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to the Application For a Full Term Licensee dated December 12,
1972 that the following areas were in the process of being cor-
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rected.
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(1) Crane warning device to signal crane movement
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(2) Cab ladder and railing width, diameter and spacing
(3) Capacity plate installation on auxiliary 5-ton hook
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The inspectors review indicated that no corrective action had
been taken concerning these items.
(INFRACTION)
DL letter to JCP&L dated April 3, 1973, Condition 4
- DL letter to JCP&L dated April 3, 1973, Condition 6
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The licensee installed a crane warning device prior to cask
handling operations and usage was observed by the inspector.
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6.
Fuel Shipment Records
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The inspector reviewed the following documentation related to fuel
shipment.
These items were considered acceptable.
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a.
Check Off Sheet (Fuel in Cask)
Assembly Identification No. JC 236
Burnup 21,150 MWD /MT
Assembly Identification No. JC 332
Burnup 19,850 MWD /MT
Reactor Discharge Date - April 1974
Estimated Heat Rate 2.69 KW (11.5KW) maximum
b.
Cask Temperature Records
Following removal of the spent fuel cask surface cask temperature
was measured by the licensee to be 71 F.
Spent Fuel Pit water
temperature was 800F. Three hours following cask loading water
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samples indicated a temperature rise of the cask cavity of 80F.
Based on a decay heat output of 2.69KW, the licensee did not
utilize methanol added to the water in the cask cavity for freeze
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protection.
c.
Radioactive Material Shipment Record
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Data covered shipment No. OC-23-75, Carrier Tristate Motor,
Label Yellow III, denoting no significant removable activity
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on outer surface of container based on surveys SS 91-75,
92-75, 93-75 and 94-75.
Shipment record was Health Physics
approved for DOT certification on January 18, 1975 and involved
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a total activity of 9.2805x10 Ci.
Measured dose rates (mr/ hour)
were 40 mr at contact, 25 mr at one foot and 10 mr at three feet.
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d.
Uniform Straight Bill of Lading
Round trip move with container empty to Oyster Creek and returned
to NFS with fissile radioactive material Cask No. NFS-4(A) Fissile
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Class III containing Fuel assemblies No. JC-236 and JC-332.
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parture at NFS, January 12, 1975. Arrival at Oyster Creek, January
12, 1975, with departure of loaded casks January 18, 1975.
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7.
Radiation Protection
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NFS 4 Cask Radiation and Smear Survey Results
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Initial
a.
Cask Arrival on Site
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The inspector reviewed radiation survey record No. RS 031-75 dated
January 13, 1975 which was performed following the on site receipt of
the empty NFS 4 cask.
Initial survey results indicated no signi-
ficant radiation level above background. Smear survey record No.
067-55 dated January 13, 1975 involved 75 smears with results
varying from 320-1010 d/m, Beta-gamma.
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b.
Removal of Loaded Cask From Spent Fuel Pit
The inspector observed the following surveys taken by the licensee
subsequent to loading of spent fuel bundles No. JC 236 and JC 332
on February 17, 1975 and upon withdrawal of the cask from the CDPS.
(1) Cask removal from spent fuel pit - 25 mr at three inches and
seven (7) mr at eight (8) feet.
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(2) Cask removal from spent fuel pit
.30 mr at three inches.
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(3) Cask fully withdrawn - 30mr at three inches was the maximum rad-
iation level detected
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c.
Cask Decontamination Results
The inspector observed initial cask decontamination efforts. The
cask was initially rinsed upon removal using demineralized water
prior to decontamination in the cask cleaning area, where exposed
cask surfaces were decontaminated.
Smear Survey results were as
follows:
(1) First Decontamination 35 smears varying from 1040 dpm to 20,000
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dpm Beta-gamma (Survey 089-75 dated January 17, 1975)
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(2) Second Decontamination 30 smears varying from 90 dpm to 7,870 dpm.
Beta-gamma.
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(3) Third Decontamination 46 smears varying from 40 - 980 dpm - Beta-
gamma, and one smear taken at cask top reading 3,360 dpm - Beta-
gamma.
(Survey 090-75 and 091-75 dated January 17, 1975.)
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(4) Fourth Decontamination Nine smears varying from 4C - 190 dpm
Beta-gamma. Survey 093-75 dated January 18, 1975 and 26 smears
of cask bottom and water samples varying from 0-560 dpm - Beta-
gamma (Survey 094-75 dated January 18, 1975)
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d.
Cask Survey for Release from Site
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The inspector reviewed the Health Physics survey for release and
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cask shipment which indicated the following.
(1) gamma radiation - 5 mr/ hour - neutron 0 mr/ hour (six feet from
trailer)
(2) gamma radiation - 10 mr/ hour - neutron 0 mr/ hour (three feet from
cask)
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(3) Smearable contamination (dpm alpha /100 cm2 - 0)
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(4) Smearable contamination (dpm - beta gamma /100 cm2 - 980 maximum)
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e.
Vehicle Survey Record
The inspector reviewed the transport vehicle survey record fol-
loving cask loading.
Survey results are depicted in Figure 1.
MAXIMUM LEVEL AT SIX FEET
4,g
Before loading 0.2 mr
After loading 5.0 mr
Inside Cab 0.2 mr
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Before loading 0.2mr
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After loading 1.0 mr
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After loading 0.3 mr
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Before loading 0.2 mr
After loading 4.0 mr
Figure 1
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8.
Miscellaneous
a.
Personnel Control - 119' Elevation, Refueling Floor
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The inspectors observed health physics and access controls in
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effect during the conduct of fuel shipment operations. Access
was restricted by security personnel, RWP coverage was provided
(50 mrem exposure limit) and two (2) health physics technicians
were observed present on the refueling floor.
Personnel involved with jib crane and fuel handling tool manipu-
lations were determined to be licensed reactor operators. Cask
handling operations were conducted by the licensee's maintenance
group.
b.
Personnel Safety
Observations of cask handling operations in the vicinity of the
spent fuel pool indicated inadequate hand rails to protect per-
sonnel and inconsistencies in wearing of life jackets while
working with the cask and CDPS. A life ring was observed to be
available. Resolution of this matter was discussed with cogni-
zant licensee representatives and at the exit interview regarding
equipment use and removable hand rails.
This item will be re-
viewed during a future inspection.
HISEfl
c.
Chromate Water Storage Status *
A review of licensee records and discussion indicated that all
trucks and tanks located on site have been emptied.
Five trail-
ers have been flushed, and two trailers were released and removed
from site. Processing of permanently stored chromate water, and
tank and truck disposition remain outstanding. A licensee re-
presentative stated that work in this area would be resumed in
about two weeks. following winterizing of equipment.
This item
remains unresolved.
d.
Bank Stabilization Program **
The inspector ou erved grading equipment at work along th'e length
of the facility discharge canal. Estimate of completion status of
this program was undetermined.
- IE Inspection Report 50-219/74-18, Details 13.c
- IE Inspection Report 50-219/74-16, Details 3a
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