ML20090D860
| ML20090D860 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/29/1974 |
| From: | Carroll J JERSEY CENTRAL POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| AO-50-219-74-56, NUDOCS 8303030432 | |
| Download: ML20090D860 (6) | |
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To: ' James P. O'Reilly .
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' ' Directorate of Regulatory Operations - -
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-631 Park Avenue .ll' King of Prussia, Pennsylvania 19406 .
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; J :. .m Prom: Jersey Central Power & Light %Cc::pany .- ,,
"0yster Crcok Nuclear Generating Station .
' Docket #50-219 Forked River, New. Jersey 08731' j l .
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Subject:
Abnormal Occurrence Report No.-'50-219/71/56 . 1he following .is a preliminary report being submitted in compliance with the Technical .Specificatioits, . t paragraph 6.6.2. , 7 '
' Preliminary Approval:
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. T .'.l PDR ADOCK 05000219
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Initial Tel 3 N.D5t of ,,
. .. h Report Date: 10/25/74 -
' Occurrence:pr :#10/25/74 w- . . . .
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C Initial Written *
' Time of < .
Report Date: 10/29/74~~P~'" ^""^ _2dccurrence:" + - 1320 4 OYS'ER CREEK hTCIIAR GENERATING STATION PORKED RIVER, NEW JERSEY. 08731 Abnor=11 Occurrence Report No. 50-219/74/ 56 "*'*F " "*" -" + ^ ~ - IDE?rrIFICATION Violation of'the Technical Specifications, paragraph 2.3.7, OP OCCURRENCE: . Main Steam Line Low Pressure Switches RB23A, B, C, and D were found to trip at pressures less than the minimum required . value of- 860 psig.
. This event is. considered to be an abnormal occurrence as de-fined.in the Technical Specifications, paragraph 1.15A.
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CONDITIONS PRIOR x Steady State Power Routino Shutdown 1D OCCURREKE:. 150t Standby Operation Cold shutdown- Load Changes During-Refueling Shutdown Routine-Power. Operation Routino Startup 0ther (Specify) Operation _ _ _ Power: Reactor, 1912 left Electric, 66212fe Plow: Recirc., 59.9 X.106 lb/hr- *
. Feed., 7.15 X 106 lb/hr-Stack Gas: .17,259 pCi/sec '
DESCRIPTION On Friday, October 25,1974', at 1320, while perfoming a OF. OCCURRENCE: routino surveillance test on the four Main Steam Line low c Pressure Switches, it was discovered that switches RB23A, B,
., C and D tripped at 850, 855, 854 and 857 psig, respectively.
'1hese values are below the minimum required trippoint of 860 psig, which is derived by adding to the Technical Specification
.' limit of 850 psig a 10 psig head correction factor.
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.,' , 'the "as: found" and ."as' left" switch,. settings were:.
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"As Found" Settingsz .
"As- 1, eft" Settings _
~ 850 psig- ,
860' p.sig -
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851:.psig.
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" :RE23B E55 psig.
854.psig.
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RE23DJ 857.. psig '. 862:psigi j 0 .s
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APPARENT CAUSE '
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APPA5 hT.CAUSE-Design _ N odedure , . lSnufacture , Unusual Service Condition i 0F OCCl"lRENCE: Inc.; Environmental.; j Installation / ' Construction .;, . , Component Failure > 1
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- Operator > x" Othor.(Specify)
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e, . ~ . :::. . . . . . . . . ... _ , . . d.The cause o'f this: occurrer.co'. is s..w. itchTrcpeatability which 'is - 1
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- v ANALYSIS OF Four; pressure switches in tho' reactor protection ~ "' system.(RPS) '
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OCCURRENCE . . ~
- " .are.provided to isolate the reactofin'the event of low main- -
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m . i:s$eamlinepressure. Two of.those' switches (RB23A'and RE23C) 7 '
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. are. in~ RPS. Channel.1, and th'e other..tyo. switches (RE23B and. t g
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' Low.: pressure, signals'.:from two
. cc,7 a . . 2'P.E23D):.are in RPS' Channel 2.
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. , , .ip2pssure switches >, one in each' RPSichannel, are required to .
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,,f.effect r.ain steam isolation, valve', closure.. A review of the- t
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."asifound"' switch. settings indicates that reactor.1sblation i
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,. .would have occurred at a pressure of.854 psigshadYazin steam
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. "line low pressure condition existedi..
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' As indicated in the bases of.the Technica1' Specifications, u.,;
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"The' low pressure isolation of the Main ~ Steam I,ines .at'850
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. depressurization and the resultant rapid' cooldown.of!the . ,: .
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vessel. Advantage was taken of.:the.scrr.a. feature which occurs when the Hain. Steam Isolation. Valves .are closed to e . y.
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.',. provide for reactor shutdown so that:high power' operation at
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low. reactor pressure does not; occur, .thus providing protec-
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tien for the fuel.cledding. integrity. safety 11mi.t';n.. .. .
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ne cdverse.consequ::nces of'rcactor isolation occurring at.. a reactor pressure approximately 6 psig below the.specified
. ...', minis:um value of 850 psigis limitedSto those effects atten-
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, fuel. cladding integrity safety. limit' only cones into effect
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_ '.,. or for power operation greater. than 354 Wt withVless.than 10F: recirculation flow. Werefore, the consequences of.a
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CORRECTI'B :ESteam line pressure. variations during daily stop valve testing ' ACTION: -
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4.. make it i: practical ~.to include in-thd switch setpoint.the normal 1 ( ".Ia,.%l'
? . trippoint variations to provido a sufficient margin.above the
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The plant has received from. General Electric,,'Coepany informa - . tion to enable us to. submit. a. Technical Specification Change Request which will enco= pass changing the present 850 psig
". J.setpoint of the Main Steam Line. Low Pressure Switches' to a
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notiyet been fully evaluated bythe plant staff;. A' Technical
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be submitted pending the
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... . ,s . .n PAILURE DATA:'.-
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. v. ,. x; reports involving. these'. switches. . . .
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- e. j.+ Mlf,",, f.ii.iLotter to Mr.- A. Giarbusso $os
. ,:. - .. ..Mr . D Al Ross[dat .
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December 24, 1973.
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cr data portinent to these ches are.,'t.s follows: Manuf
..', . Hele' tron Corp. (subsidiary of Barksdaley -
los Angeles, California .' . ). <
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Pressure Actuated Switch -
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Catalog No. 372-6SS49A-293" ,3 s - :,.. -
, Range 20-1400 psig , . .
.,3 6 Prcof psi,1750"GJ
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