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hT UNITED STATES ENVIRON' MENTAL PROTECTION AGENCY WASHINGTON, D.C.
20460 18 MAR 1974 0FFICE Or THE pW~
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Mr. A. Giambusso 50-219
_ g!, y Deputy Director for Reactor Projects 6-MAR 2 2 D745 Directorate of Licensing U.S. Atomic Energy Commission (9
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Dear Mr. Giambusso:
b Thank you for your letter of February 20, 1974, concerning
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the oyster Creek Nuclear Generating Station and its effects on the Oyster Creek Marina.
With regard to your request for information concerning the "...present EPA position on the acceptability of the proposed New Jersey water quality criteria...", I asked Jack Anderson of my staff to see to it that some assistance was provided.
He arranged for your staff to be contacted' by Mr. Paul Arbesman or Mr. Harry Allen of EPA's Region II. office.. I understand this has been accomplished and I trust they have satisfied your needs.
Should any further problems or questions arise in this area, please feel free to contact me.
Sincerely yours,
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y Sheldon Meyers Director Office of Federal Activities C
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To:
James P. O'Reilly
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Directorate of Regulatory Operations
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From:
Jersey Central Power 6 Light Company Oyster C, reek Nuclear Generating Station Docket #50-219 Forked River,.New Jersey 08731
Subject:
Abnormal Occurrence Report No. 50-219/74/ 23 9
The following is a preliminary report being submitted in c.ompliance with the Technical Specifications paragraph 6.6.2.
j Prelimina'ry Approval:
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3/18/74
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Date cc: Mr. A. Giambusso 6 'h C
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T Report Datu:
3/16/74 Occurrence:
/15/74 i
Initial l'lritt en Time of Occurrence:
1852 Report Date:-
3/18/74 OYSTER CP.EEK S"C'. EAR GE':ERATING STATION FORKED RIVER, NEW JERSEY 0S731
-Abnormal Occurrence s
Report.No. 50-319/74/ 23 IDENTIFICATION Violation of the Technical Specifications, paragraph 3.l. A.3, 0F OCCURRENCE:
the high flow isolation setpoint for the Isclation Condenser condensate line break sensors were found to actuate at differ-ential pressures in excess of those as stated in Technical Specification table 3.1.1.H.2 (<27 inches AP H O).
2 This event is censidered to be an abnormal occurrence as de-fined in. the Technical Specifications, paragraph 1.15A CONDITIONS PRIOR TO OCCURRENCE:
X Steady Stato Power Routine Shutdown 4
j Hot Standby Operation Cold Shu-down Load Cnanges During Refueling shutdown Routine Power Operation Routine Startup Other (Specify)
Operation Power:
Reactor, 1902 MWt' Elec., 661 MWe Flow:
Recirc.,15.3 x 10" gpm i
Feed., 7.10 x 10 lb/hr 6
Reactor Pressure:
1020 psig Stack Gas:
40,600 pCi/sec l
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. DESCRIPTION On Friday, Farch 15,1974, at 1852, while performing routine OF OCCURRENCE:
surveillance testing on the Isolation Condenser condensate i
high flow line break sensors, it was observed that two of the four sensors (located two each on the A and B Isolation Con-densers) actuated at setpoints above the-Technical Spec.iication limit of 27 inches 110.
The two sensors, IB11A2 and IB11B2, 2
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Abno25a1 Occurrence Report No. 50-219/74/23 Page 2 were both found to actuate at 29 inches of H2O differential pressure. The complete condensate line break sensor surveil-lance results were as follows:
Isolation Condenser A Trip Reset Sensor (inches H2 )
(inches H2O)
O 1B11A1 26.5' 23
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1B11A'
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~25 Isolation Condenser B Trip Reset Sensor (inches H2 )
(inches H2O) i O
1B11B1 27 25.5 1B11B2 29
'26.5 The IB11A2 and 1811B2 sensors were recalibrated and were surveilled to function in the proper manner. The surveillance retest results were as follows :
Isolation Condenser A T}.Q';',h': \\ ' ' )Ri, '" l'l * ;!k.'.; ', '
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f 1B11A2 27 23 Isolation Condenser B Trip Reset Sensor (inches H O)
(inches 110) 2 2
1B11B2 26.5-24.5 4
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Abnortp1 Occurrence Report No. 50-219/74/23 Page 3 4
APPARENT CAUsE Design Procedure 0F OCCURRENCE:
!!anufacture Unusual Service Condition Inst allation/
Inc. Environmental Construction
' Component Failure Operator Other (Specify) 1 The cause of the occurrence has been attributed to sensor i
.dri ft.
i ANALYSIS OF The safety significance of this event lies in the loss of OCCURRENCE:
system redundancy. Had a condition occurred whereby the condensers would have been required to isolate, the redundant sensors, IB11A1 and 1B11B1, would have performed the isolation function in the proper manner.
CORRECTIVE Corrective action will be taken, as appropriate, pending Plant ACTION:
Operations Review Coc.tittee review of this ' occurrence.-
FAILURE DATA:
Type:
Barton Differential Pressure Switch Range:
0-60 inches H 0 Pressure Rating:
1500 psig Serial Nos.:
1D11A2 - 27S-965 i
s 1B11B2.- 278-967.
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To James P..-O'Reilly Directorate of Regulatory Operations Region I j
631 Park Avenue Xing of Pnt8sla, Pennsyly'ania 19406 j
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From:
Jersey Central Power 4 f.lght Company i
Oyster Creek Nucioar Generating Station Docket #$0-219 ;
Forked River, New Jersey 08731 1
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Subject:
Abnormal Occurronco Report No. 50 219/74/ 22 i
The following is a prellatinary report being subhitted in compliance with the Technical Specification $
I paragraph'6.6.2.
Preliminary Approval!
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cc: Mr. A. Gianbur.no C
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0-3/18/74 Occurrence:
1550 _
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I OYSTER CREEK NUCLEAR GENDRATING STATION I
PORKEli RIVER, NEK.1DR5EY 08731 I
Abnormal Occurrence Report No. 50-219/74/22 I
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! C$1FICATION Violation of the Technical specifications, paragraph 2.3.7,
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ACCURRENCE:
Low Pressuro Main Stcom Line Pressure Switch, P123D, was g
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found to trip at a pressure less than the minimtm reqbired l
vnlue of 860 psix.
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This event is considered to be an abnormal occurrence as de-
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fined in the Technical $pecifications, paragraph 1.15A
(; *-dlT10NS PRIOR T* ICCURRENCE:
X Steady State Power Routine Shutdown j
Hot Standby 0peration Cold Shutdown Load Changes tharing I
Refueling Shutdown Routine Power Operation Routine Startup
_ Other (Specify)
Operation i
Power:
Roactor,1902 Wt Uloc., 661 We l
Plow; Recire.,15.3 x 10" gpm 6
Feod., 7.10 x 10 lb/hr Reactor Pressure:
1020 psig i
Stack Gas:
40,600 FCi/sec I
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IC.'d.RIPTION On Friday, F4rch 15,1974, at 1550, while performing n routine
- 0. ICURRENui:
surveillance test on t.he four Main Steam Line Low Pressurc t
Switches, it was discovered that RD23D tripped at 850 psig.
l This value is below the minimum required trip point of 860 1
psig which is derived by adding to the Technical Speelfication s
l Jimit of 850 psig a 10 psig head correction factor.
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Page 2 pportNo. 50 219/74/32
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(i ne "as found" and "As left" switch settings werea f
"As Found" Settings "As Left" Settings Rl!23A 865 psig 861 psig i
RE238 864 'psig 864 psig i
M23C 865 psig 865 psig E23D 850 psig 860 psig Pressure switch Rli23D was immediately recalibrated and rechecked l
to octuato at 860 psig.
I dPARENT CML40.
X Design Proceduro Hanufacture Umtsual Serviec Condition y occuRPJE E Installotion/
Inc !!nvironmental Construction Component Failure l
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_ Operator Other (Specify)
Switch repeatability is a recognized problem and work f r. in progr ss to formulate a floal solution, e
hALYSISOF As indicated in the besos of the Technical Specifications "he
}CCURRENCE:
low pressure isolation of the Main Steam Lines at 850 psig was l
l provided to give protection against fast reactor depressurir.u-
- t. ion and the resultant rapid cooldcun of the vessel.
Advantage was token of the scram feature which occurs when the Hain $ team itsolution Valves are closed to provide for reactor shutdown so
- t. hat high power operation at low reactor pressure does not.
occur, thus providing protection for the fuel cladding integrity L
snfety limit,"
The adverse consequences of reactor isolation occurring at
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reactor pressure approximately 10 paig below the specified alni-num value of 860 psig is limited to those effects attendant to s
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L n greater than normal reactor cooldown rate. '!he futti cl adding integrity safety limit only comes into effect for power opera-tion at reactor pressures less than 600 psig or for pwer opera-j tion greater than 354 *t with less than 10% recirculation flow.
.'fherefore, the consequences of a 10 psig lower than normal l
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reactor isolation and scram setpoint has no threatening offect i
whatsoever on the fuel cladding integrity, I
The effects of a too rapid cooldown due to the lower isolation f
j pnosure are incen.;cquential ainee there is less than 2 F dif-j ference between the saturation temperature for 860 psig and 8$0 psig.
CORRELT3 Vi!
Continuinr. corrective actions being taken at this time are as (TION:
stated in Abnormal Occurrence Report Nos. 74-9, 74-10, and 74-12, 4,
and na restated herein:
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Investip,ation is being con' ducted into the basis for the l
steam line low preanum setting of BSD pnig.
Development of a Technical Specification chango t.o lower the setpoint will follow if results of transient annlyses indicate this l
possibility.
(See Abnormal Occurrence Report No, 73 30,)
l 3.
Recolendations to posolbly reduce or eliminate the sensor actpoint change problem have been received.
It was reported that' General D1cetric tests on a pulsating line to simulate plant conditions show that pre-cycled Barksdale switches show
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improvenent but that the switches still do not moct M re-l postability. General Diectric, therefore, recommended an 1
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ppm ws. wj-mwynycu v
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f Ashcroft switch as it 18 more accurate. The Ashcroft catalog I
raud>er is 61 S 6080 BN20-OhL-1028.
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As a result, one switch of each typo (pro-cyclod Barksdalo and Ashcroft) has been purchtsed for test and evaluation at l'
Oyster Creek. An Ashcroft switch is currently on hand and undergoing evaluation.
i Mll,URE DATA!
hiufacturer dAth p6rtlnent to thoS6 sWitCho5 aro D5 follow 5; 4i Heletron Corp. (subsidiary of Barksdale) i 1,o.6 Angeles, Qs11fornia i
'j Pressure Actuaf.ed Switch Hodel 372 j
j Catalog #372-6SS49A-293 J
Rango 20-1400 psig i
Proof Pol.1750 U I
j Previous Abontmal Occurrence Reports involving these switches 1
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are:
1 1
Letter to Mr. A. Giatusso from Mr. D. A. Roso, dated l
Deced or 24, 1973.
i 2,
Abnormal Occurrence kopon No. 74-1.
i 3.
Abnorma) Occurrence Report No. 74-9.
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Abnormal Occurrence Report No. 74-10.
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Abnormal Occurrence Report No. 7412 t
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pared by:
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Date:
3/18/74__
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