ML19269C232

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Forwards Request for Addl Info Re EI/NNI-77-7 Radwaste Volume Reduction Sys. Requests Schedule for Newport News Industries Responses.Info Sought Concerns in-place Testing Criteria,Design Criteria & off-gas Treatment Sys
ML19269C232
Person / Time
Issue date: 01/18/1979
From: Baer R
Office of Nuclear Reactor Regulation
To: May J
NEWPORT NEWS INDUSTRIAL CORP. (SUBS. OF NEWPORT NEWS
References
NUDOCS 7901300142
Download: ML19269C232 (3)


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UNITED STATES

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34 NUCLE AR REGULATORY COMMISslON

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Mr. J. R. May Newport News Industrial Corporation 230 41st Street Newport News, Virginia 23607

Dear Mr. May:

SUBJECT:

ADDITIONAL REQUESTS ON "RADWASTE VOLUME REDUCTION SYSTEM,"

TOPICAL REPORT EI/NNI-77-7

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Enclosed is a request for additional information on subject topical report. These questions rcsulted from our continuing review of the topical report and of you responses to our previous request for additional infonnation.

If you request that we withhold from public disclosure any of the in-formation you provide in response to this request, you should do the following:

1.

Provide a supporting affidavit that contains a full state-ment of the reasons on the basis of which it is claimed that the information should be withheld from public dis-closure.

2.

A clear identification of the specific information that you s-consider proprietary. This can be most conveniently accom-plished by preparing separate proprietary and non-proprietary versions of the information you are providing.

Please notify me, within two weeks of receipt of this letter, of your schedule for submittin.g the information requested in the Enclosure.

Sincerely,

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Robert L. Baer, Chief Light Water Reactors Branch No. 2

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Division of Froject Management

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Enclosure:

Request for Additional Infonnation 9

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.. i.w.gy' 2 REQUEST FOR ADDITIO!;AL II;FORI*.ATION q

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Report L'u'ber:

E1/l;Th!:1-77-7 h.

RWR-1 Radwaste Volume Reduction System ~ June 24, 1977

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Report

Title:

Originating Organization: Energy Incorporated /l;ewport flews Industrial Corporation 1.

On Pasa 1 of the rep;rt you state that the residue from the fluidized-ted incir.2reter/calcinar is ceipatible wii.h existing solidification agents as well as r.tr.y agents currer.tly under study.

Provide operating data or lat:ratory t?st results te sutstar.tiate this statement.

3 ste cc.bustion of 1

2.

Ccn;ur.in; cranic ccr.ticinar.ts fr;r. th3 ir::

organic feed mi erials (resins, plastics, rt.iber etc.), provide a discussion as to the effects of these contam.ir. ants on the components of the off-gas treatment system and cechanisms or procedures designed to preclude or tinimize the effects of these contaminants.

3.

In your response to Question-2 dated January 1978 you presented a dis-Cussion of the desien crit 2ria and function of the radioactivity monitor iri the RWR-lTH system offgas c>.haust line to the plant stack. You should discuss in more d2 tail the type of e'.nitor that will b2 used and the.

capability of this instrurint to continueusly monitor both radioactive particulates and iodine-131 Also describe in detail how the radiation vonitor initiates recirculation in the off-gas system.

4.

In your response to question 10 dated January 1978, you did not address -

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in-place testing criteria for components of the off-gas system. You

.should commit to the in-place testing criteria of position C.5 of Regu-5 latory Guide 1.140 for the off-gas system.

In addition, you should provide the expected lifetime of the iodinc adsorber,

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What is the recomended change-out frequency for the ac.;uruer? What tests can be performed on representative adsorber samples to determine iodine removal efficiencies and at what frequency should test samples be taken for installed systems at comercial nuclear power plants? Pro-vide justification for your responses with experimental or research data, t

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Pages 52-53. What prevents the possibility of backup of combustion products or combustion of shredded waste in the feed system if the l

off-gas blower shuts down. Does the feed system isolation valve-shut on loss.of off-gas-blower?

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6.

Page 56, Subsection 3.3.4.

Table 1 from BTP ETSB 11-1 (now Regulatory

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Guide 1.143) is presented in Table 3-2 on Page 71 of the technical

' report, however, there is no indication how the equipment codes are applied to each component of the Radwaste Reduction System. Table 3-3 k

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(Fage 72) should list the equip;ent codes used for each component iDf h.

the F.ed.aste F. eduction System.. Table 3-3 should also provide ths. Wgm desien ti ;1ratures in addition to'the operating temperatures proy(dedN;S 7.

What piens are previded to detect and monitor radioactive contamination cf the cocling water provided for the scrub liquor cocler and off-gas.

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clean up syster coidenser?

8.

Fic.,re 2-5, Shiet 2, d:.cs not indicate the relative positions of the scrut, liquor tank and scrub liqvcr pw;s.

Tecvida justification that sufficient I;PSH exists for the scrub liqu r pamps.

9.

Eis ess everprtssuri:Eti:ns or precsur? t.s it ts within the calciner/

v :t 2 rat:r vesssi c;rinc c;criticn ar.d ;;stify that the r.niTuT.

.n;$: tid re:siirt is uiti.in the d2si;n pressure of tiie vessel. Also, discuss the propagation of the vessel pressure transient on the other cor.,onents of the Radt:aste Reduction System and justify their capability to withstand these tracsients.

10. As an interface with the plant furnished product container, describe the :pecial design requirements, if any, e.g., fill opsning size and 5:-al curface require.nents, for the centainer which receives the calcined i

natarial/ ash frca the dry cyclcne, taking into ac;ount the specific activity, temperature, and corrosivensss of the waste product.

11.

Justify your' statement that the maximum credible accident is the gross i

failure of the product container by discussing radiological consequences and likelihood of other postulated accidents such as gross incinerator failure, or failure of piping between incinerator and dry cyclone.

For the maximum credible accident you have assumed, justify your assumption....

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.af 10% release of powdered ash to the environment.

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The operation of incinerators in the past has resulted in a significant 12.

number of explosions.

Discuss the probability of an explosion in your incinerator, measures taken (by design or administrative procedures) to prevent explosion and the radiological consequences of an explosion.

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