ML20037B173
| ML20037B173 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/02/1978 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Reed C COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009080548 | |
| Download: ML20037B173 (6) | |
Text
}
(~
e
(
s 4
Cocket No. 50-10 Conenonwealth Edison Company
~
ATTH: Mr. Cordell Reed
[
Assistant Vice Prcsident
[,[,[ Mgy}2 1g1, _,,_
' ~ " ~ '
~
Post Office Box 767 Chicago, Illinois 60690 Gentlemen:
[_,,, _,,
We are currently reviewing you'r August 23,'1 977 submittal, " Technical Study for the Chanical Cleaning of Dresderi ~ I" and 'io'ur "Dresden '
~
Unit - 1 Chemical Cleaning Licensing Update" subnitted by your February 17, 1978 letter. Enclosures 1 and '2. ldescritie ladditio'nal
~
information and docu:nentation needed to camp.lete our review. To maintain a review schedule cons,1. stent with pur stafV's_ most _re. cent estimated date for cleaning, _pl, ease,subsit_ the, requested, information by May 10,1978.
Sincerely, si?,6GineaE7 De85VfU.mme.nnZiemann, Chief
[
Operating Reactors Branch f2,
[
~
Division of Operating Reactors, t
l.
DISTRIBUTION b
Enclosures:
As stated
.. -.. Doc ket i
NRC PDR i
cc w/ enclosures:
....... Local PDR-l See next page-
. ORB #2 Reading VStello BGrimes OELD OI&E (3)
DLZiemann HSmith DEisenhut TBAbernathy JRBuchanan ACRS (16)
~. -
s
~
M n,
gr DOR:0RB #2
- D0R:0RB j.2_
l
..ne.
l P)!O' Gonn.or.: a h DL Zi.ema nn...
VN/Z8._._
6/ 2 l78...
our,.
I NRC FOR.M 318 (9 76) NRCM 0240 W u. s. oovr=wuswv reiwtime owners sore - ono.eu
(-
~
..,a M
2-0 2 7975 Comonwealth Edison Company cc w/ enclosures:
Mr. John W. Rowe Ishar., Lincolh & Beale Counselors at Law 35 One 'irst National Plaza, 42nd Floor
~~
Chicago, Illinois 60603 Mr. B. B. Stephenson
=
Plant Superintendent H==
Dresden Nuclear Power Station Rural. Route #1
=
Morris, Illinois 60450 5(.
Morris Public Library 604 Liberty Street Morris, Illinois 60451
..c Department of Public Health ATTN:
Chief, Division of
~
==
Nuclear Safety l
535 West Jefferson Springfield, Illinois 62761
- _=
i 9 h O
O 4
4 I
O SU 7".
s=
O y
v vwg 7
1 w..
y
--m-
&,ev.
- -. - +,%-
+
-ggy
.---m a
9g y-g,wi
g e
y --.
-eap
--.e*mwv.9
- w - -.
o El? CLOSURE 1 REQUEST FOR ADDITIO!iAL IfiFORiiATIO'i RADIOJ.0GICAL SAFETY C0t;CERi1S RELATED TO DEC0!!TAMIiATIOil DRESDEt; STATI0t Utili f;0. 1 DOCKET t;0. 50-10 The following questions relate to open items and documentation of CECO's responses to questions p3sec by fiRC representatives during our December 15, 1977 meeting at Dresden Station.
1.
Either provide adequate assurance that the decontamination solution will contain less than 10 nanocuries/gm of transuranic nuclides or commit to measure the transuranic content of the Dresden i decon-tamination waste prior to waste shipping.
2.
Provide the staff with a description of the radioactive waste facility's ventilation system.
Identify all paths for the release of gaseous radioactive effluents and identify the location and type of the filters present.
3.
Document your response that the solidified waste is not flammable.
Provide assurance that fires involving the flammable binder used in your waste solidification process cannot cause the release of radioactive material.
4.
Describe the filtration of the nitrogen cover gas that is vented following the decontamination.
5.
Document the basis for your estimate that approximately 1 ;:Ci of
~
I-129 will be generated by the decontamination.
6.
Document your conclusion that failure of the liquid waste storage tanks would not result in the release of radioactive liquid waste from the waste facility.
7.
During.the meeting CECO's representatives mentioned approximately 100 operations which had been evaluated in detail to determine their potential radiation doses.
Provide the doses estimated for these operations.
8.
Describe the procedures to be used for handling, processing, solidifying and shipping the radioactive waste.
Provide your dose estimates for these operations.
.o a
...Z'..'
e
- - 2 b
I 9.
Provide es'tinates of the curie amounts of Fe-55, tii-63, and any other non-gamma emitters of significant quantities (s>10 curies) f that may te encountered in the decontamination process.
Provide i7' assurance that all liquid releases to the environment from the
_~
Dresden i reactor, including Dresden 2/3 if liquids from Dresden 1 are transferred to Dresden 2/3, will be analyzed for the ' isotopes determined above while decontamination and subsequent waste processing operations are in progress or until the expected
==
releases of these isotopes decrease to less than 10 mei/yr.
..=
==i Analysis should consist of at least a monthly analysis of a composite smaple of all the liquid releases over the-past month.
".'J."..'.*j
. '. ~. '
A h
)
9 I
+
4 O
e
':l: 'l E.
4
i f
ENCLOSURE 2 REQUEST FOR ADDITIONAL INFORMATION h
MATERIAL TESTING CONCERf!S RELATED.T0 DECONTAMINATION DP.ESDEN STATION UNIT NO. 1 DOCKET tt0. 50-10 The following questions relate to open items and documentation of CECO's responses to ' questions posed by NRC representatives during the January 17, 1978 meeting at Dow Chemical Company in Midland, 1
.^ l];-
1.
Document the limits to be placed on the chloride, lead, sulfide, total halogen content, and chelating capacity of the decontami-nation solution prepared for use at Dresden 1.
2.
Verify that conformance to these limits will assure that your test results are valid for the full scale application of the NS-1
- solvent, y
-3 Document the method for controlling pH, dissolved iron < 1200 ppm,
)
j and solvent (chelating) capacity of the cleaning solution.
==
4.
You stated that no check will be made on inhibitor contents during the cleaning because tests indicated no excessive attack i
by the selvent on reactor materials even in the absence of the I
i inhibitor.
Explain why the inhibitor is added ~ to the solvent if its absence does not result in unacceptable corrosion rates.
5.
Identify, by reference, the data base to support each of the conclusions on pages 206,and 207 of Volume:II.
6.
Identify the resolution of each of the 11. items that your consultant, 4~
Dr. Staehle, identified in his October 25,1974, " Evaluation of Stuides by Dow to Qualify Decontamination of Dresden 1", 'as needing careful consideration.
=
'7.
Provide an updated schedule for the Dresden 1 chemical cleaning.
8.
Describe the.results of the irradiated material testing program identified in.Section IV C _ of Appendix XVI.
Provide a schedule i
for completing any portions of this program that have not been compl eted.
'k.
i
9.
Review thf ASTM Specifications which apply to the materials used in Dresden 1.
Determine whether changes in these ASTM Specifi-cations since the late 1950's may have an impact on the validity of your test data.
10.
Provide a listing of the major components that will be in contact with the NS-1 solvent.
Identify the materials in each component that will be contacted by the solvent and provide a page reference for the relevant test data, 11.
Identify the metallurgical condition and uses of type 410 stainless-steel that will be contacted by the NS-1 solvent and state whether the alloy is used as a pressure boundary.
12.
What was the metallurgical condition of the samples of the type 410 alloy used in the materials test program?
13.
You have indicated that nitrided surfaces and thrust bearings will not be tested for materials compatibility because they will be inspected after decontamination and replaced if damaged.
Determine whether failure of components which contain nitrided surfaces during the decontamination process could involve an unreviewed safety question.
Prepere a contingency plan for draining and flushing the primary coolant system that is independent of these components if an unreviewed safety question is identified.
14.
Address the pick-up and subsequent redistribution of copper throughout the primary coolant system.
15.
Provide a step-by-step summary of the intended sequence of operations involved in the decontamination.
G e
5