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., w A. Gimabusso, Deputy Director for Reactor Projects Directorate of Licensing NOISE AND IIIGH FREQUENCY VIBRATION IN QUAD CITIES, IRIIT 1 Counnonwealth Edison Company letter dated February 16, 1973 re-ports a situation in which noise was heard and high frequency vibrations were observed in piping of one recirculation loop.
Members of the Committee would like to discuss the cause and safety significance of this event and would like the Regulatory Staff to present any additional information available beyond that contained in the cmith 1stter, to discuss how the Staff arrived at the assessmaat that there is no insipient safety problem (since the plant has been allowed to continue to operate), the basis for that assessment, and to discuss plans for further investigation and action.
Please advise the ACRS office of when you will be prepared to j
discuss this matter with the Comatittee.
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John C. McKinley 8
Senior 8taff Assistant cc:
M. Rosen J. Hendrie V. Moore D. Skovholt P. Morris R. Engelken bec:
R. F. Fraley M. W. Libarkin ACRS Members
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Form Atc-3:s (nev.8.ss) Arcu c24o
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l UNITED STATES I
D ATOMIC ENERGY COMMISSION I
WASHINGTON, D.C.
20545 No.
P-444 FOR 15NEDIATE RELEASE
Contact:
Clare Miles (Monday. December 18, 1972)
Tel.
301/973-7771 AEC ISSUES FULL TERM LICENSES FOR NUCLEAR POWER STATION NEAR CORDOVA, ILLINOIS The Atomic Energy Commission has issued full term licenses to Commonwealth Edison Company and Iowa-Illinois Gas and Electric Company for full power operation of Units 1 and 2 of the Ou d rit_.
'l; clear Power Station near Cordova, Illinois.
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The full term licenses will expire 40 years from February 15, 1967 -- the date the AEC construction permits were issued.
At full power each unit will produce approxi-mately 809,000 electrical kilowatts.
Since August 15, 1972, the companies have been authori:ed to operate both units at 90 percent of full power under interim operating licenses issued by th'e Commission pending completion of the final environmental statement required by the AEC's regulations implementing the National Environmental Policy Act.
Issuance of the full term licenses follows completion of the environmental review and modification of the tech-nical specifications for operation of the facilities.
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4 EXCERPTS I'?.0M S1':'.ARY OF 152nd ACR$ MEETING DECEMBER 7-9, 1972 I
3 2.1.2 Report on Flooding of Turbine Building (As Occurred at Ouad Citic s) on the Capabili t y for Lonn-Term Dec,ay Heat Removal Mr. J. I. Riesland, DL, reviewed the turbine building flooding incident at the Ouad Cities Station (See Section 2.2.2, Summary Report of 147th ACRS Meeting) and informed the Conmittee that if the incident had occurred during power operation, the system could be depicssurized, and time (at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) and procedures vould be availnole to permit removal of residual heat. The Conuittee was also informed that:
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There are other Category 2 systems whose failure e
could cause failure of Category 1 systems in the Ouad Cities and other plants.
i Letters have been sent to licensees of other plants e
to request an evaluation and report to REG on these matters.
An earthquake could cause the same type of incident.
e Tbc mm eptibility of the Browns Perry plant to this e
type of oc cu r re n c e is thour,ht to be similar, but the D ro. s Terry evaluation is not complete.
e The pie P, as pre':ently conceived, would not bc endan:, red by n oo:11ng loss of critical el uipmant,
l but a 1.; a e rupture of the type that occurred at the Guad Ci cins pl:x could have caused sinking. This will be corrected, i
The P i A. tory Scaf f will report back to the Committee o
(1) results of ongoing evaluations and (2) criteria on bear: derc]oped to evaluate the adequacy of preventive / pro-
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'!j EXCEP. PTS r?.0M SI::"*ARY OF 152nd ACRS MEETING DECEMBER 7-9, 1972 4
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!> r e::he i v :lves were foand to be one d och or raere f n, :t 1o'1,/ clo;; a p -cition, even though the tha vd ces to be c30:ed, uas describcd po,'tJo, i n.il: aors fel t h.
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,lu a re nLtributc6 principally to y c nl. w e r, t of vaJsc operating c;.t mri,c fritt.on cnd e
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- I r ' '; t c ' s The ; elx, uc re overhr 01 cd 1.0 ensure positier indicator limit witches were por. J 1.
clonn.u, an j repir"cd ui; b unit.s m-a;, lese hysteresis.
Th e Cc.: ',!iu "e e.v, info 3:
that. ris !!ngu t+. tory St a f f is (1) p re-m p a cir. ' n t p c.ric ype ' ei t.:r t o h ". n t t o all cu ers of plants with vocoeu b.
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,;c c leaLage 2.1. 5, 1 ned Cies Unit 2 - Ti:e ' n a C : ',1 < Tm Mr. ib m.Jiu t i n form d tb. Cm 'it1 that the Ju]y 16,1972, fires occur.< ; in t,:' e'.ble trc3r of Qan Cities Station during
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I st a rt-xp tes t ioc wrc th< retult of poor (high resistance)
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merbanical splicing of. sculuctorr.
Investigation showed the need for resplicing reiy 011ginai connections of a similar type.
.ent obs.:ved thcr th dclay (tuo hours) in fire li r.
det ect ion / location u s a rant.t er of concern and that measures should be tchen by rec to ensare that full advantr.ge is taken of current technology for fire detection in nuclear plants.
Dr. Rosen agrued to raahe note of t his, and Mr. Eill indicated that this subject would be c::plored by the ACRS Ad lloc Working i
Group on Fire Protection.
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'llt 152nd ACRS MEETING.
DECEMBER 7-9, 1972 e
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of t < h r.v! - point dri f t espm lence at '
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va rious pl.ints ntni not..' that incident reportr. had not been accomulni ed prior h, t air fear bec.tuse thic pas not previously recop.nined a. c~ieporte.bic occurrence. Jiu i n fo rr.ed t he Committee that:
a Darhndalc switchen cpper.r to be r.ot.coptible to drift difj.icu1 Lies and CE has Jup.ter.iented a progra.n uith the vendor t.o solve the problem.
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\\'e ry f<.u d ri f t incidents have been reported for PWR's.
One-reason may be that L.h e recalibration procedure for
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L=j' PUlt's does net include the pressure sensing element.
F (nol a syst em enlibration).
f; j RCG in establishing a progtam to revict and evaluate e
'e drift incident reports.
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'8 EXCEEPTS TP.0M St."'."4RY OF 152nd ACRS MEETING J
DECEMBER 7-9, 1972 2.1.5.9 g rA citics - RCIC Valve Ma1 fonctions Mr.
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G. Eiserbut, DL, described for the Cor.mittee the RCIC valve i"1c;3mu. en incident (duz in/, vnive operability surveillance te n t i n;-) o f S e pt.<. o'.;c t 3, 197?.
Soue valvec failed to close and othei. faiJtJ to '>;)e n. The failurer were dueribed as due to (1) owi-t orqueinl, on closure (f ailure of torque limit switch) wi th renultant jatair'a and (2) fcilure of a 250-V de breaker openin;; contactor.
Following corrective action, no operating abnormalities wre obrar ved.
Mr. Eisenhut noted that; o Six euch fai) urea had been reported since July 1972.
over-torque jerning of valves has occurred in many o
plants.
e The incident would have no adverse safety consequences cince the valves are part n of redundant systemn which are required to met the single-active-failure criterion.
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Most of the failures are though t to be random, although a ccwnon-mode failure mechanicm may be inferred for some.
i o Encouragement for industry attention to valve prob 1 cms a
was'given at a recent meeting of REG with valve manu-facturers.
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