ML20031C330
| ML20031C330 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/15/1974 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| AO-5-74, NUDOCS 8110070060 | |
| Download: ML20031C330 (3) | |
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April 15, 1974
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Mr. John F. O' Leary, Director
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- Re: Docket 50-155 Directorate of Licensing License DPR-6 US Atomic Energy Co==ission A0-5-74 Washington, DC 205h5
Dear Mr. O' Leary:
A Attached is a copy of an Abnormal Occurrence Report for the Big Rock Point Plant.
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RBS/ cap Ralph B. Sewell
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CC: JGKeppler, USA::0 Nuclear Licensing Administrator l
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- ABNORMAL OCCURRENC'E' REPORT
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Report: AD-5-74, Ideket 50-15"
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Date: April 15, 197h "q
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Occurrence Date: April h, 1974 j;
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Facility: Big Rock Point Plant D
5 Identification: Core R :c; ; rat Exchanger Tube Leakage Surveillance 6.
Conditions Prior to Occurrence: All plant operating conditions j
since February of 1971.
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Description of Occurrence: Failure to check core spray beat i
exchanger integrity at frequent intervals as described in See-tion 5, Item 4, of Amend:ent 10 to the FESR following design modification in 1970.
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- 8. & 9 Designation of Cause/ Analysis of occurrence: Plant modifications for the backup core spray system vere made during the refueling antage of Ms ch 1"70 and a chech valve vas c.dded in 'vLe 4" 11ue
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which penetrates containment to meet updated containment isolation criteria. The addition of this check valve made it i=possible to perfom the frequent checks for tube leakage as cutlined in Amendment 10 of the FHSR. This require =ent in Amend =ent 10 reads as follows:
"The tube bundle of the core spray heat exchanger vill be checked for leckage during routine operator invec-
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tions, which occur at frequent intervals oy opening a 3/4 inch drain valve on the shell sidat.
Th. tube bundle vill be under p essure at all times from the fire system."
The pressure require =ent is descriptive and aside frcm the fact that it provides the basis for the surveillance check, it is not l
intended to be a safety-related requirenent of itself.
The core spray beat exchanger leakage test since 1971 has been done as a special test, T365-07, on an annual basis with no failures noted. The tube bundle had been replaced in February of 1971 fol-loving corrosion type failures of the original bundle. Based on the satisfactory results of the annual tests perforced in 1972, 1973 and j
197h, it is dec=cd that no undue safety harards existed at the fa-cility with reference to this ites.
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Corrective Action: The Special Annual Leak Test (T365-07) vas con-ducted satisfactorily on April 10, 1974 and procedural ctances are being cade to conduct a leakage inspection at renthly intervals.
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J e FACILITY:
CATFCORY: REPORT t_u L
m_q e /55 07 DATE*M7 4 03 DATE:/J 74-TYPE:
SOURCE: DOCRET f:
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M 49 74 75
- DESCRIPTION OF $ENT:
O' MOJ C rJF C U C CV L
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80 7~89 m
es cm*ce (Ato -s-74) 7 89
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'STSTDt No.:
PROSIMATE COMPONENT CAUSE CODE:
A-FDSONNEL ERROR D-PROCEDURES DEFFCTIVE NUMBER:
B-DESIGN ERROR E-COMPONENT FAILURE C-MTF1tMAL cat'tr F-0TUF1t 12 13 DESCRIPTIO[0F CAUSH (A ?W % h c w (<
ADbCP F C IdE Ck.
Os 30 7
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89 80 STATUS OF
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METHOD A-OFERATIOSAL DDiT REACTOR CODE:
8-PRECPERAT10NAL. INITIAL ROUTINE POWER OPERATION OF B-ROUTINE TEST /1RSFff STARTUP AND POWER ASCEMS10N G-SHUTDOWit (HOT OR COLD.
DISCOV11T C-SPECIAL TEST /INSPFC TESTS E1* EFT REftELLINC)
D-FITF7 MAL SATRCE (DISC *}I C ROUTINE STARIUP OPERATION H-REFUELLING D-ROUT!hT. SHL*1 TING DOWN OPERATION 1-0THER.1%CLUDING f ?ECIAL E-STEADT STATE OPEIATION At _1 TESTS (DESCRIBE)
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STATUS:
1 POWD:
0;dE1 STATUS:
DISC.:
DESCRIPTIUN:
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10 12 IJ 44 4 46 7 ~ 8l-FORM OF
.: LIQJIL COTTENT Na hotLE R.S r
' ACnVITT S: SOLID OF 1: HAIDCE" RELEASED:
C: CAS RELEASE:
Pt PARTirttATE AMOUNT OF ACTIVITY:
LOCATION OF RELEASE:
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10 11 44 45 FERSONKEL EIPOSURES t k
NUMBER:
DESCRIPTION:
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8 9 11 12 PERSC WEL INJURIES:
L NUMBER:
DESCRIPTION:
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OFFSITEbONSEhENCES:
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'DAMACE TO FACIL11T:
16 60 7
8 9PUBLICITa*:
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REY. 8/21/73
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