ML20084U695
| ML20084U695 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 01/10/1975 |
| From: | Kalivianakis N COMMONWEALTH EDISON CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20084U697 | List: |
| References | |
| NJK-75-23, NUDOCS 8306290185 | |
| Download: ML20084U695 (3) | |
Text
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i Conunomssaltt>Emeon 3
Quad-Cities Noctest Power Station l
PostOmcaBox 216
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Cordova.litmors 61242 Telephone 309/654 224r I
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Teslecopy-Region-f il, Attention:
Mr. C. FeIerabend i
J-Janua ry - 10, 1975-l J.. Xeppler, Regional Director l
Directorate of Regulatory Operations Region. t il 3:
U. S. Atomic Energy Commission 799 Roosevelt Road j
G1ca: Ellyn, IIlinois 60337'
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e Reference r Quad-Cities Nuclear Power Station, Unit 1 Docket No. 50-25%, DPR-20 Appendix. A. Sections 1.0. A.5. and 6.6,a.11 a.
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Dear Mr. Keppler:
The purpose-of this letter is to provide you.with notification of an Ah-normal Occurrence as required, by Technical Spect fication. 6.6.8~.1.a within:.
i 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the occurrence.
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WIthiquad-C1 ties Unit 1 in, the ColdsShutdown Condition-, weld. examinations l
were conducted on the reactor recirculation discharge bypass lines. Two j
weld-cracks were identified, at the Junction of each. of' the discharge.by-pass valve. (M0-1-0202.~7 A&B) four-inch downstreme sections and the 28-:
j inch discharge h4ader.- Two indications have been~ found at the junction i
of the upstream four-inch; section and the 28 inch: line.
Final.amelyses 6
and, plans are not complete: at this time..
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This occurrence was discussed by" telephone with. Mr. Feierabend of your office on January-10, 1975 Fur:ther infonnation wl1-1 be provided by Ah-l normal. Occurrence Report AO 50-254/75-3 which.will be..submi tted within.
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- 10. days of the date of this occurrence.
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Very-truly yours, I
COMMONWEALTH' EDISON COMPANY j
QUAD-ClTlES. NUCLEAR POWER STATION:
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J. Kalivianakis[
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Station Superintendent i
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Directorate.of Licensing l
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DIRECTORATE OF REGULATORY OPERATIONS REGION III
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R0 Inspection Report No.
i-Transmittal Date 4
Distribution:
Distribution:
R0 Chief, FS&EB R0 Chief, FS&EB
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RO:HQ (4)
DR Central Files L:D/D for Fuels & Materials s
Regulatory Standards (3)
DR Central Files
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Licensing (13)
RO Files i
R0 Files e
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RO Inquiry Report No.
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Transmittal Date
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Distribution:
Distribution:
R0 Chief, FS&EB R0 Chief, FS&EB
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RO:HQ (5)
RO:HQ J
DR Central Files DR Central Files 7
Regulatory Standards (3)
R0 Files Licensing (13) i R0 Files C.
Incident Notification From: Commonwealth Edison Co., Docket No. 50-254 5
(Licensee & Docket No. (or License No.)
bN Transmittal Date a
Distribution:
Distribution:
RO Chief,_FS&EB_
R0 Chief, FS&EB g
RO:HQ (4)
RO:HQ (4) 4 Licensing (4)
L:D/D for Fuels & Materials i
DR Central Files DR Central Files A
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T Honorable Joshua Eilberg J
House of Representatives s
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Dear Mr. E11 berg.,
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l The following'181in reply to your letter of October 10,,1974, to.
Mr. Robert D., Ofjfeill'regarding cracks identified in auxiliary piping of three bo.ilin.g water r. eac' tor facilities.;
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Aftercrackbwerefoundinmid-Septecher1974infour,relativelysmall-y (4-inch diameter),bypans' links.,in r.e. act
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vater reactors in Illinois ~and a third,or..c. o.olant' systems'at.two boi. ling in Connecticut, the AEC on e.-
g-Septe$ber 19 ' notified 'alfftiliti%h'aYin(one or.cora operhting. boiling' '^
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water reactors 'to czanine" these. bypass lines for evidence of cracks f within 60 days. AEC's notification covered _a total of 21 boiling water ~.
j reactors with AEC licenses authorizing their_ operation..,
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Fifteen of the facilities, including the three whero cracks.were found '
initially, have similar bypass piping systems. As of October 18,'tvelva O
of theso had coupleted detailed examinations of their bypass piping V
systems. No additional cracks have been, identified in the 4-inch bypass b
lines.
The utility operator of one of.the facilities in this category,. c -
reported to AEC that examination of their piping system had been conducted ?
I in December 1973, and the plant had not yet commenced power operation.c.~ -
AEC has not required reexamination of this facility.3Theiremaining two
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I facilities plan' examinations of their piping systems by.mid-Novemberj
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Six additional' operating boiling'. water. reactors of e,arlier' design eitheru....
do not hive' the bypass" piping syste:s ofjoncern'or~haveja' markedly dif-2
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forent piping configuration (generally ' smaller) from those where cracks have been identified.. AEC is,not rcquiring an' examination of the piping.
systems of these facilities 'at this' time.n The utility operators of four.
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of these plants h' ve, however, notified the.AEC of plans to examine at a
least portion's of their' piping ' systems'. ~
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'G The AEC Regulatory staff has been informed by' its licensecs, assisted by the Ceneral Electric Company and AEC's Argonne National Laboratory [] f{ h.[
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that preliminary findings indicate stress-assisted corrosion, caused, V _
the cracks identified in mid-September. However, the sources of the i d - -
g stress and corrosion have not yet been determined.'L% ' U.
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