ML20107A919
Text
,
O
.b.
y 1:D 5
Jersey Central 10 wee & Light Company
~
j
-s M AolsoN AVENUE AT PUNCH DoWL Ro AD,9 MoRRi$ TOWN. N.J. o7960 0 539 6111 October 1, 1973 Q,1 L. '.,
,.,p-
[ug' O'Y p" Q)
Mr. Donald J. Skovholt Assistant Director for Operating Reactors 001b i Directorate of Licensing U.S. Atomic Energy Commission pu p-
Washington, D. C.
20545 0;
(..Is. i.'y
Dear.Mr. Skovholt:
%/
SUBJECT:
Oyster Creek Nuclear Generating Station Docket 50-219 - Outstanding Licensing Items This is to inform you of the status of the Main Steam Isolation Valve evalu-ation in response to your letter dated April 3, 1973.
During the past year on two (2) occasions the outboard MSIV's failed to close upon receiving an iscilation signal. These failures are attributed to sticking pilot operated power valves. Upon inspection of these valves a small amount of fine red dust was found on the sleeve "0" rings.
The outboard MSIV's are presently air operated, whereas the inboard MSIV's are nitrogen gas operated with air as a back-up supply and have not exhibited any similar failures. Thus, in order to upgrade the reliability of the MSIV closure, it is planned to change the gas supply from the current instrument air to nitrogen.
This modification is presently being reviewed by the Safety Review Committee.
To aid in your current and future evaluation of MSIV performance, the following information is provided:
a.
'The minimum clearance between the pilot valve piston and the pilot valve cylinder is considered proprietary information and the vendor will not make it available; but the pistons in the pilot valves do not have increased clearances, contrary to your letter dated April 3, 1973.
b.
The cleanliness of the MSIV's nitrogen gas supply is governed by the cleanliness of the " boil-off" from the nitrogen supply tank, which can be con-sidered pure.
At present there is a "Y" strainer used to prevent large particles from entering the system.
The back-up supply air system's cleanliness is governed by the post filter from the plant's air compressors. The filter media is Glastex GB providing 5-10 micron particle retention. The installation of 3-5 micron filters is presently being considered for both of these systems.
k
?
b 7138 9604150196 960213 PDR FOIA DEKOK95-258 PDR
. 0 (fr. Dsnald J. Skovholt s
Page 2
'd October 1, 1973 The temperature environment for the MSIV pilot operated power valves c.
is'approximately 125-130 F for the' inboard valves, and 150-1650 F for the outbeted valves, d.
The present proventive maintenance program for the MSIV pneumatic control system consists of c1 caning the pilot operated power valves with
~ This program is performed during
. acetone and blowing down the gas lines.
the annual refueling outages.
,Very truly yours, V&
Donald A. Ross
.RLL/DAR/pmd Manager - Nuclear Generating Stations e
c.
?
i n
?
j l
6,.
-, ~.
-y
y j --
To:
James P.'O'Reilly Mrectorate of Regulatory Operations Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
.From:
Jersey Central Power f, Light Company Oyster Creek Nucicar Conorating Station Docket #50 219
~ Forked River, New Jersey 08731
Subject:
Preliminary Abnormal Occurrence Report No. 73-25 The following is a preliminary report being subnitted in compliance with the Technical specifications, para.
graph 6.6.2.
Preliminary Approval:
4 4$ g M _10/1/73
[J. T.. Carroll, Jr.
Date cc: Mr. A. Gianbusso 4
tn-a spp.
l j
I
~
(!
Report No. 73-25
)
SpJECT:
Pallure of 1 solation Condenser initiation relay GK12 to func-tion when acncrgized while perrneming routine surveillance.
'Ihis. event is considered to be an abnormal occurrence as defined in the Technical specifications, paragraph 1.15D. Notification of this event, as required by the Technical Specifications, paragraph 6.6.2.a, was made to AEC Region I, Directorate of l
Reguintory operations, by telephone on Ssturday, September 29, '-
1973, at 1:35 p. m.j and by telecopier.on Monday, October.1, 1973, at 12:00 p. m.
S1_T11ATIOJ{: While performing a routinc surveillance test on the Reactor liigh' Pressure - 1 solation' Condenser initiation switches, con-l tacts on relay 6K12 failed to open within the preset tine delay of 15 seconds after tripping the pressure switch and deenergizing the relay.
QUSEi.
Unknown. The relay has since been removed from the circuit and bench tested and appears to function properly.
i 1
REMDDIAL _ACTIO'i:
i Relay 6K12 was replaced with one from spares. A satisfactory surveillance test was conducted and the isolation Condenser I
System then cortsidered to be operable, 6
Prel'itinary
~
~
s Abnormal Occurrence 2--
pteober 28,:1973 Heport No. 73'-25
()
SAFETY SICNIFICANCE:
As detailed in Amendment 67 to the FIE'R, at least one of the Isolation Condensers is required to set as a means for heat
. removal during a postulated Loss of Coolant Accident. - Actuation of relay 6K12 can he by means or' High Reactor Pressure or inw r.ow Reactor Water 14 vel. It is wired into the logie circuit i
such that tripping of the relay provides one-half of the initia-tion logic for both condensers,.the other one-half being its redundant counterpart on the '$1me Instrument penetration. A second redundant instrument penetr'ation also includes two pres-sure switches, contacts from which' also will initiato both iso-i lation condonsors. The significance of this event'then is the loss of redundancy PEvided to initiate one-half of the signal for placing the isolation Condenser System in service.
6 w
t 4
1 4
4.
i
,s e
a*
6' i 4
t,4*a.,gy 3 e, a y
e se
.e F
1 i
h W
h 6
v.
.6 r
,i 1
-t' To:
Jams P, O'Rr,111y Directorate of Regulatory Operations Region I i
631 Park Avenue King of Prussia, Pennsylvania 19406 i
From:
Jersey Central Power 4 Light Corpany Oyster Creek Nuclear Cenerating Station Docket #50-219 Forked River, New Jersey - 08731 1
Subject:
Prolininary Abnormal Occurrence Report
/3 24, The following is a preliminary report being submitted in compilance with the Technical Specifications, paragraph
~
6.6.2, Preliminary Approval:
kftW 9}2K/ 7.5 k T, Carroll, Jr, Date cc: Mr. A, Giambusso
-?'3 C 5 6 9 O l C V - 3p,
1
'I Abn:rual Occurrence Report No. 73-24
}
l a
SUBJECT:
Violation of the Technical Specifications, paragraph 1.15,li, failure of H.s{n steam Isolation valves NSO4 A and NSO4B to meet
(
acceptabic Icakage ns specified in Tedinical Specification 4.5.F.1.D.
This event is considered to be an abnormal occurrence e de-fined in the Technical Specifications, paragraph 1.15.E.
Noti-fication of this event as required by the Technical Specifications, paragraph 6.6,2,a, was nado to AEC Region I, Directorate of Regulatory operations, on Friday, Septernber 28, 1973, at 3:50 p.m.,
and by telecopior on Friday, September 28,1973, at 5:00 p.m.
SITUATION: At 1801 on Septerter 27, 1973, Main Steam Isolation Valve NSO4B was tested for icskage and the Icakage was measured to be approximately 15.15 SCF11.
At 2035 on September 27, 1973, Main $ team isolation Valve NSO4A was tested for leakage and the Icakage was measured to be approximately 96.59 SCMI.
Both valves, NSO4A and N5048, were operated following the Tractor shutdown and prior to being checked for Icakage. Operation of the valvos during the. shutdown was required to allow odequate 4
4 4
.,, w 3 0...
...r-..
p.-
9 3
ventilation of the reactor vessel, through the main steam I
lines, while perfoming maintenance on NS03B, in order to minimize radiogas concentrations in the drywell.
CAUSR; I,caksge put the valve packing was detected on both NSO4A and N504B which contributed substantially to the Icak rate.
Repai rs to the packing and a rctest. of the valvet. Is required to deter-mine whether any other cause contributed to the excessive valve leakage.
BIMEDIAL ACTIqN:
To be determined.
SAFET/ SID.'Uld.NCE:
To be submitted follruing evaluation.
8
..*e ans e og f