ML20107D038
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To:
James P.
O'Rol13y Directorate of Reguistory Operations Region I 631 Park Avenue King of Prussia. Pennsylvania 19406 From:
Jersey Contral Power 4 Light Cog eny Oyster Creek Nuclear Generating Stattert Docket #50 219 Forked Rivur. New Jersey 08731
Subject:
Abnorinal Occurrence Report No. 50-21p/74/ 10 The following is a proliminary report being subanitted in coinpliance with the Technical Spect fications paragraph 6.6.2.
Preliminary Approval:
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2211/74 J. T. Carrol),.[r.
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OY R CRE2K HUCt. EAR GnN2 RATING STr" pH ORKED RIVER, N!W JERS2Y C8731 /
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Abnerunat.Ocourrence
' Report No, 50-219/74/ E IDEDfr1PICATION Violation of the Technical Specifications, paragraph
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OP OCCUR.%ENCE:
low Pressure Main Steam Line Pressure Switches RE25A, C, and D were found to trip at jpressures g less,.themlMb required '
value of N60 paig.
This event is considered to be an abnormal occurrence as de-fined in the Toshnical spe ci fiest i ons, paragraph 1.15A CONDITIONS PRTOR TO OCCURRENCB 4 X
4teady State Power Routina Shutdown Hot Standby Ope ration Cold Shutdown Load Osanges During stefueling Shutdown Routine Power Operation Routino Startup Other (Spec.Lfy) operation The maj or plant puhtssoters nt the time of the occurrence worcs Powers Haector, 1908 left Elect ric, 672 MWe Flows Hacirc., 60.2 x 10' Ab/h r Peed., 7.13 x 10' Ib/hr Roastor Pressured 1020 psig Stack Ges 28,357 uC1/sec DESCRIPT1ON i
OF OCCURAnNCn a on Friday, February 8, 1974, at 1030, while performing a sur-vaillance tout on the four Main Mteam Line Low Prosauro SwltcJien, it was discovered that RB23A, C, and D trippod at 850, 856 and usa ps3.g, respoctively.
Those valuem are below the minimum ro-quired trip point of 860 psig which j a derived by rdding to the i
l Technion1 Specifi cation Il mi t of 850 psig n 10 paig head correc-tion factor.
(see Attachment 1 for test results.)
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- PPAHENT.CAUSE X [ haign Pre fure A
~ UnL /21 Corvico Condit1on CP CCCUnqu6HCR4
%denufcct u re Installation /
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Const ruction Component Pallure Othe r. (8pe ct fy)
Operato r Sensor dri ft fa a recognised prwbtem and work to in progreen to formusste a final mo1ution. The steps required to achieve No.
this end were delineated in Abnonnel Occurrenec Report 78-30 and restated in Abnorma! Occurrenco Report No. 74-D.
ANAINNIN OF An indicated in the bauen of the Te chnical Spe ci fi catt en, + "the OCCumahMCMs low pressure isolation of the Main Stesa 1.ines at 850 paig was fast reactor depressurisation provided to give protection against and the resultant rapid cooldown of the vennel.
Advantage was taker. of the scram feature which occurs when the Main Steam lao-tation Valves are closed to provide for rea'ctor shutdown so that hi$ power oporation at low reactor pressure does not o c cu r, l
thus providing protection for the fuel cladding integrity safety 4
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The adverso consequences of reactor isolation occurring at reactor pressure approximat ely 10 pois below the epocified mini-saum va1ue of mau psig is 11taited to thoso offects attendant t.o l
The fuel cl adding n Arent.er t han nossal reactor cooldown rate.
integrity safety limit only comes into offect for power oporo-i l
tion at reactor pressures l os e t h an 600 pe i g o r fo r pow er ope ra.
tion greator than 354 MWt with loss then 10% recirculation h ow.
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'thorofore, the consequences of" u 3 0 pu i s T ower th en normal reactor t
inul ation and scram motpoint has no threatening effect whatso-i J
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cver( l tho fuel cladding intcgrity.
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The effects of a too rapid coold wwn duo e the lower iso,1eti on i
pressure oro inconsequential sinco there la appront mately n 1
1* P dA ttorence between the asturation tegorature for $60 psig j
und #50 psig.
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CORRTCI VR Continuing corrective actions being t aken at this time are as ACTAuNs stated in Abnormaal occurrence R* Port No. 74-9 and as restated
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Investigation is being conducted into the bania for the steam lino low proseure aceting of 550 pe12 Deve3opment of a Todinical 8pecifi cation chenge to lower the setpoint wila foss ow it resuats of t ransient analysom indi ent o thi s ponsthility (sos. Abnormal Occurrence Report No. 73-30).
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Vendor recosessendations to possihiy reduce or eliminate the nennur netpuant de t (t. proh t est wait be evaluated as soon as they are available (letter to Mr. A. Ciambusso from Mr. D.
A.
Hoss, dated Liecember 24, 1973).
PAILURD DATD:
Munut'acturer data pertinent to these switches are as follows:
l Molotron Corp. (subsidiary of Barkedale) the Angelop, Cali fomi a j
Prces n u rre Actuat ed Nwitch Model 372 Catalop # 372-6SS4DA-293 Hanke 20-1400 psig P roo f Ps i. 1750 C 4
F-The ao fswid switwh esttings wsrst Trt _he?ulf-j RE25A 850 psig RE23B 860 psig RB23C 856 psis Rt.2 3D.
456 ps13 The presaure Awltches were then reco11brated and checked to actuate as folienes s Test Results RB23A 860 psis RB23C-860 pnla M22n sno psig c
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l Jersey Central Power & Light Company (i!mln 1
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MADISON AVENUE AT PUNCH BOWL ROAD
- MORRISTOWN, N.J. 07960
- 201-539-6111 mamass e en
,.}. { Public Utilities Corporation Genered araram February 7, 1974 6}
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Qj~ 7 Mr. Dennis L. Ziemann, Chief i
FEt 25 h.M
- D Operating Reactors Branch #2 50-219 E9!
Directorate of Licensing United States Atomic Energy Commission JL atouic nmi kb& w$,"[$f,'lf Washington, D. C.
20545 p
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Dear Mr. Ziemann:
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Subject:
Electromatic Relief Valve Operation Summary This letter serves as an addendum to my previous letter addressed to you dated January 18, 1974.
Its purpose is to report additional electromatic relief valve' operations not accounted for in the above referenced letter.
Since formal records of relief valve operations have not been maintained in
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the past, we relied upon operating charts, reports, and log books to deter-mine valve'actuations.
'Ihis now completes our response to your request regarding electromatic relief valve operation at our Oyster Creek Nuclear Generating Station.
Very truly yours, l
Ml.'/
ikshI' Ivan R. Fir, frock', Jr.
Vice President i
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LRecords Used in Determining the
. Electromatic Relief Valve Operations -
A compilation of scram reports was used to determine-the 'date of those' transients which would be severe enough to' cause the steam. pressure to exceed the setpoint of the Electromatic Relief Valves.
The charts which record the. downcommer temperature were' then employed to verify the sus-
-pected operation of the valves.on the determined dates.
Due to the
~ difficulty in reading this ~ particular. chart and a. time period of down-commer temperature recorder inoperability, a cross-check was made with the steam pressure _ chart, in which case it was assumed that if the steam pressure reached or. exceeded the setpoint of the electromatics, the valves were automatically opened.
The Shift Foreman and Control Room log books were also. checked on these particular dates, but no
-consistent record of valve operation could be found in these. logs.
Automatic hepressurization surveillance records were used to determine those. valve operations which occurred during surveillance testing of
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the valve.
These tests are included in the summary.
In order to in-clude other. tests which might not be included in the surveillance records, the Control Room log' book was examined during all periods of reactor startup and reactor shutdown operation, which is a time when manually initiated relief valve operations' are most ' expected due to lower reactor pressure.
The operations summaries of the six-month reports were also. examined, f
-and one valve operation was found in this record; it is included in the summary.
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' Summary of Additional Electromatic Relief Valve Operation -
January 1,1971 to December 31, 1971 Date of Operation:- September 18, 1971 Purpose of Operation: Valve operability test.
- Mode of-Initiation: Manual-Reactor Conditions Prior to Operation: 'Ihe reactor was suberitical with
- the reactor pressure at 600 psig.
Comnents : During a reactor shutdown, the Electromatic Relief Valves were manually tested at a pressure of 600 psig.
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Summary of Additional Electromatic Relief Valve Operation January 1,1973-to December 31. 1973'
'l Date of Operation: April _13,1973 Purpose of Operation:
Valve Operability Test
' Mode ^ of Initiation: Manual
. Reactor Conditions Prior to Operation:
The reactor was suberitical with the reactor pressure at 230 psig and coolant temperature at 400*F.
Comments:
Following a scram, the Electromatic Relief Valves were manually i
tested at the above conditions.
. Date of Operation: November 25, 1973 Purpose of Operation:
Primary coolant system depressurization.
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Reactor Conditions Prior to Operation:
Steam Flow 6.6 x 106 lbm/hr Reactor Pressure 1020 psig Electrical Output 629 MW. (e)
Comments: The. reactor scrammed due to a high neutron flux caused by a pressure spike which collapsed voids in the core.
The pressure increased to the setpoint of the Electromatic Relief Valves of 1070 psig, causing them to open.
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