ML20107C589
Text
.. -.
i.
5 l
6 a
JERSEE CENTRAL POWER & LBMT C0.
J. G. Esppler. 30:4 BOWER 30. 50-219 I
. ;,w.
Attashed is a espy of the yesposed bleeL sheet der the W M 8 eat}ity,' [y 4
t l
a asyy of iduish uns M to Feet ',
4 l
effsee by smashdie em 1/3/72.
j 1
i.
i 4
i R. T. Carlson, RO:1 i
i 1/3/72 l
i t
i.
4 f
i'
, b i
l t
.p.
+
k l'
l 9604170415 9/.213 PDR FOIA DEKOK95-258 PDR f
--+
d DRAFT DIRECTORATE OF REGULATORY OPERATIONS NOTIFICATION OF AN INCIDENT OR OCCURRENCE Facility:
JERSEY CENTRAL POWER & LIGHT CCNPANY (0YSTER CREEK)
Problem:
RO Region I (Newark) was informed by the licensee by telephone on December 29, 1972 that a primary system relief valve had failed to rescat when actuated following a turbine trip and reactor scram from full power earlier that day. Failure of the relief valve to reseat resulted in a blowdown of an estimated 50,000 gallons of primary coolant to the containment torus. The following preliminary infor-mation was provided by the licensce:
1.
At 6:08 a.m. on December 29, 1972 with the reactor operating at full power (650 MWe gross), a turbine trip and reactor scram occurred when an operator inadvisedly opened a switch panel serving the turbine control system.
2.
During the ensuing transient, reactor pressure increased to 1070 psig at which point the relief valves functioned as intended.
However, one relief valve failed to rescat, resulting in the discharge of an estimated 50,000 gallons of primary coolant to the torus.
3.
Reactor pressure decreased from 1000 psig at the start of the l
occurrence to 660 psig within two minutes and 200 psig within sixty 0
mi nu te s.
Reactor vessel cooldown during the first hour was 156 F.
l
)
i
4 f.
2-The Technical Speci.fication bases assume 10 emergency cooldowns of.300 F./hr. (normal cooldown limit - 100 F./hr.).
4.
At tne time of the-scram, an attempt-was made per procedure to switch from run mode to startup mode,. thus bypassing the containment
. isolation function in order to retain the main condenser hotwell as a heat sink.
In this instance, the bypass key broke in the mode switch, resulting in isolation of the drywell when the reactor pressure reduced to the isolatlon trip point of 850 psig.
One of the four main steam isolation valves (No. NSO4B) failed to close at the time of initiation, i
5.
Both isolation condensers were initiated manually. The A system l
functioned satisfactorily; however, the condensate return valve on the B unit did not open as a result of failure of the valve motor.
-]
i I
6.
There were no significant radioactivity releases to the environs or personnel exposures as a result of this occurrence.
i
- The plant is currently in the cold shutdown condition. The licensee is i
investigating the cause of the failures with the primary coolant relief 1
i valve, the main steam isolation valve and the B isolation condenser
[
condensate return valve. Disposition of the 50,000 gallons.of reactor J
coolant which has mixed with the chromated (rus.t inhibitor) torus water is of immediate concern to the licensee in that the amount exceeds available storage capacity and the presence of. the rust inhibitor prevents discharge is 1
n
.2 a.
p
?-
l w
{.,
i 7,
3-to.the environs. The plant will be returned to' operation following completion
_ of the) investigations and repairs as'necessary.
J t
Ac_ tion:
1 1.~' An-RO inspector.is at the site to obtain' detailed information on the
~
occurrence. ' Further action by RO'will be based on the results of 'this t*
inspection.
l
[2..
Region I has informed the State of New Jersey and the Northeast Office of the Division'of Public Information b'y telephone, a
3.
Commissioner Ramey's Technical Assistant, Comissioner Doub's Technical ~
I Assistant and the Staff of the Joint' Committee on Atomic Energy are being in-l formed by copy of this notification.
l 4
1 L
i
['ht.
2, M.
7]
Prepared by:
Robert T. Carlson l
1 4
.I 1
s n
9
'.m..
l..
A. k -
w+
h -'
r
.u
-,...;w
.-m..-
w
--m
-sv.e--
n 3
q.
UNITED CT ATES
- f~
ATOMIC ENERGY COMMISSION DenscTon Avs or nsoutAvony oran AvsoNS nsGloM t 970 BROAD STREET k
NEW ARK, NEW JERSEY 07102 sts e R0 Inquiry Report No. 50-219/72-320 l t..
Licensee:
Jersey Central Power & Light Company Madison Avenue at Punch Bowl Road Morristown, New Jersey 07960 License No.:
DPR-16 Facility:
Oyster Creek - BWR Forked River, New Jersey Descriptive
Title:
Equipment Failure - Floor. Drain Sample Tank Recirculation Line A
/
/
b Prepared by:
A F. S. Cantrell, Reactor Inspector Date A.
Date and Manner AEC was Informed:
N On December 7,1972, during an inspection at the site.
B.
Description of Particular Event or Circumstance:
When the operator started the recirculation pump for the "A" floor drain sample tank, at about 8:00 a.m., December 6,1972, he noted t
4 a slight decrease in tank level.
He immediately went.to the sample tank area (which is outside the radwaste building) and observed water spraying against the building and running down into the curbed area around the tanks, and spraying on the sidewalk outside the curbing.
He immediately went back inside and stopped the pump. A tank inven-tory showed that 50 gallons of water was lost from the tank. An inspection in the area showed that the drain line inside the curbing was valved to go to the discharge canal rather than to return to the radwaste building. As a. result, only approximately 1 gallon of water was recovered.
l i.
4 7
~
~ ~ -,
gg4W3
~
(
t i
l' C.
Action by Licensee:
1.
A sample of water was obtained from the tank and was analyzed, with the following results Isotopes Activity (uC1/cc)
Ratio (Activity /MPC)
Gross Activity 2.05 x 10-2 1
Cobolt-60 5.89 x 10-3 117.8 Cesium-144 4.08 x 10-3 453.3 Cesium-137 5.99 x 10 299.5
-3 Kanganese-54 3.55 x 10 35.5 2.
The pipe that failed was on the discharge side of the pump and was located just outside of the building between the building and the tank. This pipe is 3" carbon steel pipe and was re-paired by welding a patch over the failed area. According to the maintenance foreman, he has ordered stainleos steel pipe to replace this line and the comparable line to the "B" fleor drain sample tank.
,gp 3.
The water that landed on the sidewalk outside of the curb was soaked up with a blotter, however, before the area was sur-veyed for contamination, it started raining.
The sidewalk was not smeared for contamination until December 7,1972. At that time, the sidewalk was clear of contamination, however, the area inside the curb was contaminated up to 5000 cpm.
The sand next to the sidewalk was also contaminated.
The upper layer of sand was removed with the contamination.
The licensee issued instructions for the drait. from the curbed area to be cituer valved closed, or to the radwaste building sumps.
4.
The licensee plans to survey other equipment to determine the potential tor this type of corrosion-errosion failure as part of his general study of the operation of the radwaste facility.
5.
The licensee will submit a written report to the Directorate of Licensing within 10 days as reauired by the Technical Specifica-tions.
h
- +
s s
r 5<* ma awat ia
g,,,,,,,,,,
~
h,
],,,,,,,,,,,,.
7,,,,,,,q,,/g j
(
f/EMO C0l!Tf.
ro<
At c.c e nn. % i e, i.,,,.i c si om n o,..,,4,,,.,
ej vo<~...aaomo
.. r u u atou a y
RO INQUTRY REPORT MO.
50-219/72-32Q J. C. Keppler, JERSEY CENTRAL POWER & LIGHT CO.
cart 0 (2)
OYSTER CREEK T o < n.... ad...i>
initiAts at=.ans ec:
2111_xi-- J--- - -"'.
The subject inquirf report is forwarded for RO:!IQ (5) your information.
Distribution will be inade DR Central Files i
i Reg. Standards (3 )
si n<,-
o f T i n. _ n e d n.,,a (1 p by this of fice to the PDR, LPDR, NSIC. DTIE I
to (n...
ao unio in:f vu nuno and State representatives ef ter revicw by the licensee for proprietary information.
cart
-~
(
j ruou (n.m..ao un.i>
meu. ns
,,,,p I
t s \\,
4
,l D. L. Caphton, RO I i
FHQNL WA LATE I;
12/18/72 WM OTHLA tipE' FOA AOCtflo t4L AtwAAr.5 crg + init o. ses..
A I
d 4 l:
I t
i t
e h
5 l
o w
i
'e t
e i
g--
l i
-. -