ML20106J962
See also: IR 05000219/1973016
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NOV 151973
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J. P. Stohr, Senior, Environmental Protection and Special Programs
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Section, Directorate of Regulatory Operations, Region I
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INSPECTOR'S EVALUATION
RO INSPECTION REPORT No. 50-219/73-16
JERSEY CENTRAL POWER AND LIGHT COMPANY (JCPL)
OYSTER CREEK NUCLEAR STATION (OC)
The above inspection report documents the findings of my review of the
licensee's environmental monitoring program. This inspection was con-
ducted primarily as a follow-up to an earlier inspection (R0 Inspection
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Report 50-219/73-03) at which time 13 violations were identified. This
current inspection revealed that corrective actions had been taken as
stated by the licensee in his letter dated May 22, 1973.
No new viola-
tions were identified during this inspection.
The inspector noted that although no violations were identified, the
monitoring programs themselves were unchanged and as such, remained
deficient.
The licensee stated that an upgraded environmental program
was scheduled to be included with an upcoming submission of Environmental
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Technical Specificati - 9 on November 1, 1973. This new environmental
program should be evaluated rather closely to insure that it meets cur-
rent standards.
The major problem identified during this inspection was the supervision
and evaluation being provided by the licensee with respect to the cur-
rent programs existing at the OC site.
If this level of supervision
and evaluation are allowed to continue without change into the upgraded
program, many of the objectives of this program may be negated.
The
individual in charge of the program is extremely conscientious and as
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such can see that the samples are taken as required. As far as the
evaluation of resultant data, no individual at the site possesses suf-
ficient depth in this area to provide any meaningful evaluation and
from my observations and discussions with licensee personnel, no one
at the corporate level (JCPL or CPU) has shown any concern or interest
in this area.
It appears that although the outer compliance with Technical Specification
has been achieved, at -least for the present, management attitude remains
apathetic.
This attitude may change with the upgraded program but I saw
no evidence of any change at this time. The Station Superintendent and
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9604120001 960213
DEKOK95-258
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J. P. Stohr
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Technical Supervisor were both responsive to our ir.quiries but neither
ins the proper background to handle this problem without support from
higher corporate management.
It is recommended that this matter be
reviewed in greater detail subsequent to the sutxnission of the upgraded
program.
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, Dr. Charles 0. Gallina
, ~ ) Radiation Specialist
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Jersey Central Power & Light Company j/fl(
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MADISON AVENUE AT PUNCH BOWL ROAO + MORRISTOWN, N. J. 07960 * 201539-6111
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November 13, 1973
Mr. A. Giambusso-
Deputy Director for Reactor Projects
Directorate of Licensing
United States Atomic Energy Commission
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Washington, D. C. 20545
Dear tir. Giambusso:
Subject: Oyster Creek Station
Docket No. 50-219
Hydraulic Shock and Sway Arrestor Failure
This Ictter serves to report a failure of one (1) hydraulic shock
and cete nrrector unit (11SSA) ,on the ste?.m line for isolation condenser !!E01B.
found while per/orming a monthly check of all units in the reactor building
externa), to the drywell, as recorrended by the Plant Operations Review Comnittee.
This event is considered to be nn abnormal occurrence as defined in the Tech-
nical Specifications, paragraphs 1.15D and D.
Notification of this event, as
required by the Technical Specifications, parrsraph 6.6.2.a
was made to AEC
Regicn 1, Directorate of Regulatory Opciations, by telephouc cn Saturday,
Nove:cbcr 3.1973, and by telecopier on Monday, flovember 5,1973.
hhile conducting an inspection of the hydraulic shoch and sway
arrestors (snubbers) located on verious systems in the reactor building, but
outside of the drywell, the accumulator on one unit on the steam lino to the
"B" isolation condenser was fcund to be devoid of fluid.
Additionn11y, another unit on the steam line to the "A" isolation
conden'.er vr.s initially reported to be failed, but further inspection anri eva)-
uation by the mechanical maintenance foreman and the maintenance engineer re-
sulted in the unit being considered to be operable but low in accumulator fluid
' level.
Upon disassembly and inspection of the accumulator installed on 1.he
"B" isolation condenser, th'c spring loaded piston ring was four.d to be fn31cd.
Althcugh no deterioration or other unusual conditiens could be visually determined,
the U-cup on the accunulator piston head apparently was degicded to a point
where it allowed the fluid to leak out.
The unit had not been rebuilt during
either the Spring 1973 Refueling / Turbine Generator Inspection nor during the
September 1973 Snubber /Turbino Control kalve Outage.
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Giambusso
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November 13, 1973
Pertinent data is as follows:
Manufacturer:
Bergen Paterson Pipe Support Company
Type:
HSSA-10
Serial No.:
469946
The initial inspection report indicated that one unit on the steam
line for the "A"
isolation condenser and one unit on the "B" isolation condenser
were inoperable.
Consequently, as per the requirements of the Technical Specifi-
cations, paragraph 3.8,0, an orderly plant shutdown was commenced upon notification
of the situation. Meanwhile, an immediate reinspection was made on both snubbers
with results as previously indicated. Nevertheless, preparations for an orderly
shutdown continued until the accumulator for the snubber on the "A"
isolation
condenser could be filled to a satisfactory Icvel. This action was completed by
1845 Friday, November 2, 1973. The load drop which had been started was halted,
and the plant returned to its previous operating level of 595 FMc(g).
Follow-up
action included replacement of the accumulator on the snubber installed on the
"B" isolation condenser steam line, then replacement of the entire snubber unit
on the "A" irutation enndenser steam line, since it had been Icaking. This
19U' iciday evening.
A follow-up check was then
action was com, meter
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made on Sat urdav evening to insure that no further fluid loss was occurring.
, < ndmeat 67 to the FDSAE details the requirements for at 1 cast one
isolatica c .Genwr to be availablo es a heat sink in the event of a loss of
coolant acH Jent.
Both condenscr* would have been abic to perform this function;
however, had an certhquake occmed which would have required proper functioning
of all instadt
W .w the stean line to the "B" condenser may not have been
abic to withstam the anticipated forces.
Consequently, should a rupture then
have occurred, a relet
af reactor steam to the secondary containuent would have
resulted.
Analysis of this accident has been made assuming a valve closure time
of 60 seconds after the break, and found to be less severe than a rupture of the
main stesn line and subsequent closure of the main steam isolation valves.
The
significance of this event then is the increased probability of stear release
to the secondary containment which, had thht occurred with subsequent unit
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isolation, then would have resulted in a loss of redundancy of the isolation
condensers to act as a heat sink.
In lieu of waiting an additional month to reinspect snubbers located
in the reactor building, this reinspection will be conducted within the next two
weeks.
Based upon the inspection findings, a determination will be made as to
an acceptable future inspection frequency.
In addition, four snubbers previously not included in the inspection
program, two of which are located on the No. 2 containment spray system and
two on the No. I core spray system, will be inspected promptly and will be in-
cluded in subsequent inspections.
It is further intended that the ethylene propylene seal procurement
effort be continued such that any units rebuilt in the future would contain
seals of this material.
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. Mr. Giamb'usso.
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-November 13, 1973
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Enclosed .are forty (40) copies of this report.
Very truly yours,
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Donald-A. Ross
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Manager, Nuclear Generating Stations-
DAR:cs
Enclosures
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cc: : Mr. J. P. O'Reilly, Director -
Directorate of Regulatory Operations, Region I-
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