2CAN028313, Forwards Procedures Re Resins Involved in High Integrity Container Exothermic Reaction,Per 830204 Telecopy Request: Difference between revisions

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ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 [5011371-4000 February 25, 1983 5
ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 [5011371-4000 February 25, 1983
                                                            ?r-~-@- WIi\V/F.%'.
?r-~-@- WIi\\V/F.%'.
2CAN028313 bd l
5 bd MAR - 21983 2CAN028313 l
MAR - 21983     :-
L {J l
L   {J                   l Mr. W. C. Seidle, Chief Reactor Project Branch #2 U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
Mr. W. C. Seidle, Chief Reactor Project Branch #2 U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011


==SUBJECT:==
==SUBJECT:==
Line 31: Line 31:
I.D - Resin quantity The quantity of resin contained in the High Integrity Container (HIC) was 103 cubic feet.
I.D - Resin quantity The quantity of resin contained in the High Integrity Container (HIC) was 103 cubic feet.
I.E. - Resin age, exposure to temperature and radiation It is difficult to determine the precise age of the resin; however, it is felt that some resin may have been as much as 3-4 years old.
I.E. - Resin age, exposure to temperature and radiation It is difficult to determine the precise age of the resin; however, it is felt that some resin may have been as much as 3-4 years old.
8303290222 830225 PDR ADOCK 05000368 P                   PDR MEMBEFI MIDOLE SOUTH UTiuTIES SYSTEM
8303290222 830225 PDR ADOCK 05000368 P
PDR MEMBEFI MIDOLE SOUTH UTiuTIES SYSTEM


Mr. W. C. Saidle                                     February 25, 1983
Mr. W. C. Saidle February 25, 1983
  - The temperature of resin during the exothermic reaction was determined to be approximately 365*F along the center line of the HIC. Radiation levels were found to be about 400 mr/hr at the top opening of the HIC.
- The temperature of resin during the exothermic reaction was determined to be approximately 365*F along the center line of the HIC.
Radiation levels were found to be about 400 mr/hr at the top opening of the HIC.
I.F. - Physical condition of the resins beads Resin samples taken near the center line of the HIC were found to be quite dark (shiny black) in appearance, while those resin beads away from the center line showed less darkening and normal coloration.
I.F. - Physical condition of the resins beads Resin samples taken near the center line of the HIC were found to be quite dark (shiny black) in appearance, while those resin beads away from the center line showed less darkening and normal coloration.
II.A - Service use of the resin bed materials The resins in question were used for a variety of purposes. The resins had been transferred to the HIC from the ANO-2 Resin Storage Tank (2T-13) which serves as a holding tank for spent resins from several ANO-2 radwaste systems. Therefore, it is difficult to state specifically the service use of the resins.
II.A - Service use of the resin bed materials The resins in question were used for a variety of purposes.
II.B - Inlet stream chemistry / periodic sampling Waste inlet streams are sampled periodically with the frequency dependent upon operational considerations. Since the resin came from a holding tank, the inlet stream chemistry is dependent on_a number of inputs.
The resins had been transferred to the HIC from the ANO-2 Resin Storage Tank (2T-13) which serves as a holding tank for spent resins from several ANO-2 radwaste systems.
II.C - Unusual operating conditions. Past experience with similar resins.
Therefore, it is difficult to state specifically the service use of the resins.
II.B - Inlet stream chemistry / periodic sampling Waste inlet streams are sampled periodically with the frequency dependent upon operational considerations.
Since the resin came from a holding tank, the inlet stream chemistry is dependent on_a number of inputs.
II.C - Unusual operating conditions.
Past experience with similar resins.
Incidents with nitrates a7d other oxidizing chemicals.
Incidents with nitrates a7d other oxidizing chemicals.
Similar resins have been routinely transferred from tank 2T-13 to HIC's with no problems having been experienced.
Similar resins have been routinely transferred from tank 2T-13 to HIC's with no problems having been experienced.
During ANO-2 service water chemical cleaning in November 1982, a cleaning system hose leak occured which resulted in spillage of 'a quantity of water containing sodium nitrite (used as a passivation agent in the cleaning process). It is presumed a small portion of this leakage was routed to and processed by the ANO-2 Radwaste System.
During ANO-2 service water chemical cleaning in November 1982, a cleaning system hose leak occured which resulted in spillage of 'a quantity of water containing sodium nitrite (used as a passivation agent in the cleaning process).
It is presumed a small portion of this leakage was routed to and processed by the ANO-2 Radwaste System.
II.D - Changes in resin parameters with time Unknown.
II.D - Changes in resin parameters with time Unknown.
II.E - Resin sluicing procedures Resin transfer was accomplished using a resin-water slurry in accordance with approved procedures. These standard procedures are routinely used and no problems have been experienced with previous resin transfers.
II.E - Resin sluicing procedures Resin transfer was accomplished using a resin-water slurry in accordance with approved procedures. These standard procedures are routinely used and no problems have been experienced with previous resin transfers.
Information copies of these procedures are attached.
Information copies of these procedures are attached.
III.A,B - HIC type, size, material, and vendor The high integrity container used was a Chem-Nuclear type 8-120. Details of its size and material of construction are proprietary and cannot be released without authorization from Chem-Nuclear. Should you still need this information, we will pursue a release from Chem-Nuclear.
III.A,B - HIC type, size, material, and vendor The high integrity container used was a Chem-Nuclear type 8-120.
Details of its size and material of construction are proprietary and cannot be released without authorization from Chem-Nuclear.
Should you still need this information, we will pursue a release from Chem-Nuclear.
(
(


Mr. W. C. Saidle-                                     February 25, 1983-
Mr. W. C. Saidle-February 25, 1983-
'III.C - Resin dewatering procedures
'III.C - Resin dewatering procedures
' Resin was dewatered in accordance with Chem-Nuclear approved dewatering
' Resin was dewatered in accordance with Chem-Nuclear approved dewatering
. procedures. These procedures are proprietary'and cannot be released without authorization from Chem-Nuclear. Should you~still need these procedures, we   '
. procedures. These procedures are proprietary'and cannot be released without authorization from Chem-Nuclear.
will pursue a release from_ Chem-Nuclear.
Should you~still need these procedures, we will pursue a release from_ Chem-Nuclear.
III.D - Interaction between the HIC and the waste-There has been no apparent interaction between the resin and the HIC.
III.D - Interaction between the HIC and the waste-There has been no apparent interaction between the resin and the HIC.
III.E - Effect of the exothermic reaction on the HIC There tis no apparent damage to the HIC or internal dewatering system; however, Chem-Nuclear intends to confirm this through destructive testing.
III.E - Effect of the exothermic reaction on the HIC There tis no apparent damage to the HIC or internal dewatering system; however, Chem-Nuclear intends to confirm this through destructive testing.
IV.A - Assay results and chemistry analysis results of testing None to report at this time. AP&L expects to receive results of tests it has contracted for about March 1, 1983.
IV.A - Assay results and chemistry analysis results of testing None to report at this time.
AP&L expects to receive results of tests it has contracted for about March 1, 1983.
IV.B - Tests to be performed and by whom AP&L has contracted with Battelle Northwest Laboratories (BNL) to perform the following tests:
IV.B - Tests to be performed and by whom AP&L has contracted with Battelle Northwest Laboratories (BNL) to perform the following tests:
: 1)   Analysis of resins for oxidizing agents
1)
: 2)   Analysis of resins for " Free Organics"
Analysis of resins for oxidizing agents 2)
: 3)   Acid-Base titration of resin
Analysis of resins for " Free Organics" 3)
: 4)   Heat-Chemical reactions
Acid-Base titration of resin 4)
: 5)   Cation analysis
Heat-Chemical reactions 5)
: 6)   Analysis of resins for peroxides
Cation analysis 6)
: 7)   Resin identification IV.C - Status of Chem-Nuclear and Dow Chemical testing efforts-Chem-Nuclear and Dow have not performed any chemical analysis at this time that we are aware of. The only action known to us' is that AP&L contracted with Chem-Nuclear to transport twelve samples of the affected resin to BNL on February 9,1983.
Analysis of resins for peroxides 7)
Resin identification IV.C - Status of Chem-Nuclear and Dow Chemical testing efforts-Chem-Nuclear and Dow have not performed any chemical analysis at this time that we are aware of. The only action known to us' is that AP&L contracted with Chem-Nuclear to transport twelve samples of the affected resin to BNL on February 9,1983.
IV.D - Sample availability for independent NRC testing Samples of resin are available to the NRC at ANO until arrangements for final disposal are made.
IV.D - Sample availability for independent NRC testing Samples of resin are available to the NRC at ANO until arrangements for final disposal are made.
V.A - Quality. assurance of the HIC to assure safe transportation Resins which have_ experienced an' exothermic reaction will be transferred to another' container for final transport and disposal. At this time it appears the HIC had no bearing on the exothermic reaction and further it appears that no damage has occurred to the HIC.
V.A - Quality. assurance of the HIC to assure safe transportation Resins which have_ experienced an' exothermic reaction will be transferred to another' container for final transport and disposal.
At this time it appears the HIC had no bearing on the exothermic reaction and further it appears that no damage has occurred to the HIC.


Mr. W. C. Seidle                                                                                         February 2:5, 1983 b
Mr. W. C. Seidle February 2:5, 1983 b
V.B - Routine storage of HIC's.                                           Shipment of resins in the involved lirer.                                           ,
V.B - Routine storage of HIC's.
Shipment of resins in the involved lirer.
HIC's are normally stored for a period of 30 days or less inside a shield cask and away from direct sunlight.
HIC's are normally stored for a period of 30 days or less inside a shield cask and away from direct sunlight.
:                    .The resins in question will not be shipped in the same liner.                                                         Chem-Nuclear has requested that the affected HIC be returned to Chem-Nuclear for destructive testing.
.The resins in question will not be shipped in the same liner.
Chem-Nuclear has requested that the affected HIC be returned to Chem-Nuclear for destructive testing.
V.C - Past experience with resins-from the same source No previous problems have occurred.
V.C - Past experience with resins-from the same source No previous problems have occurred.
V.D - Solidification procedure for resin disposal Preparation for disposal will be based on results: from chemical analysis and recommendations from vendors. Therefore, the disposal procedures are not
V.D - Solidification procedure for resin disposal Preparation for disposal will be based on results: from chemical analysis and recommendations from vendors.
                    -known at this time.
Therefore, the disposal procedures are not
Very.truly yours, i                                                                                                                 John R. Marshall
-known at this time.
                                                                                                                - Manager, Licensing JRM: RR:sl i'
Very.truly yours, i
John R. Marshall
- Manager, Licensing JRM: RR:sl i
4 l--
4 l--
.i i
.i i
f 1
f 1
                                                                                                                                                                                  ,,}}
_}}

Latest revision as of 05:13, 15 December 2024

Forwards Procedures Re Resins Involved in High Integrity Container Exothermic Reaction,Per 830204 Telecopy Request
ML20072G969
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 02/25/1983
From: John Marshall
ARKANSAS POWER & LIGHT CO.
To: Seidle W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20072G971 List:
References
2CAN028313, 2CAN28313, NUDOCS 8303290222
Download: ML20072G969 (4)
v • d • e


Text

!

ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 LITTLE ROCK, ARKANSAS 72203 [5011371-4000 February 25, 1983

?r-~-@- WIi\\V/F.%'.

5 bd MAR - 21983 2CAN028313 l

L {J l

Mr. W. C. Seidle, Chief Reactor Project Branch #2 U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

SUBJECT:

Arkansas Nuclear One - Unit 2 Docket No. 50-368 License No. NPF-6 Data on Resins Involved in the High Integrity Container (HIC)

Exothermic Reaction Gentlemen:

The following information is provided in response to your telecopy request dated February 4,1983, and titled " Data Needed on Resins." We have repeated each request and provided a response for each item.

I.A,B,C - Resin manufacturer, type and form The affected resin was manufactured by either Rohm-Haas, IRN 150 LC, 50/50 mixture; or Diamond Shamrock ARA 9371 Anion, ARA 9358 Cation, typically a 50/50 mixture.

I.D - Resin quantity The quantity of resin contained in the High Integrity Container (HIC) was 103 cubic feet.

I.E. - Resin age, exposure to temperature and radiation It is difficult to determine the precise age of the resin; however, it is felt that some resin may have been as much as 3-4 years old.

8303290222 830225 PDR ADOCK 05000368 P

PDR MEMBEFI MIDOLE SOUTH UTiuTIES SYSTEM

Mr. W. C. Saidle February 25, 1983

- The temperature of resin during the exothermic reaction was determined to be approximately 365*F along the center line of the HIC.

Radiation levels were found to be about 400 mr/hr at the top opening of the HIC.

I.F. - Physical condition of the resins beads Resin samples taken near the center line of the HIC were found to be quite dark (shiny black) in appearance, while those resin beads away from the center line showed less darkening and normal coloration.

II.A - Service use of the resin bed materials The resins in question were used for a variety of purposes.

The resins had been transferred to the HIC from the ANO-2 Resin Storage Tank (2T-13) which serves as a holding tank for spent resins from several ANO-2 radwaste systems.

Therefore, it is difficult to state specifically the service use of the resins.

II.B - Inlet stream chemistry / periodic sampling Waste inlet streams are sampled periodically with the frequency dependent upon operational considerations.

Since the resin came from a holding tank, the inlet stream chemistry is dependent on_a number of inputs.

II.C - Unusual operating conditions.

Past experience with similar resins.

Incidents with nitrates a7d other oxidizing chemicals.

Similar resins have been routinely transferred from tank 2T-13 to HIC's with no problems having been experienced.

During ANO-2 service water chemical cleaning in November 1982, a cleaning system hose leak occured which resulted in spillage of 'a quantity of water containing sodium nitrite (used as a passivation agent in the cleaning process).

It is presumed a small portion of this leakage was routed to and processed by the ANO-2 Radwaste System.

II.D - Changes in resin parameters with time Unknown.

II.E - Resin sluicing procedures Resin transfer was accomplished using a resin-water slurry in accordance with approved procedures. These standard procedures are routinely used and no problems have been experienced with previous resin transfers.

Information copies of these procedures are attached.

III.A,B - HIC type, size, material, and vendor The high integrity container used was a Chem-Nuclear type 8-120.

Details of its size and material of construction are proprietary and cannot be released without authorization from Chem-Nuclear.

Should you still need this information, we will pursue a release from Chem-Nuclear.

(

Mr. W. C. Saidle-February 25, 1983-

'III.C - Resin dewatering procedures

' Resin was dewatered in accordance with Chem-Nuclear approved dewatering

. procedures. These procedures are proprietary'and cannot be released without authorization from Chem-Nuclear.

Should you~still need these procedures, we will pursue a release from_ Chem-Nuclear.

III.D - Interaction between the HIC and the waste-There has been no apparent interaction between the resin and the HIC.

III.E - Effect of the exothermic reaction on the HIC There tis no apparent damage to the HIC or internal dewatering system; however, Chem-Nuclear intends to confirm this through destructive testing.

IV.A - Assay results and chemistry analysis results of testing None to report at this time.

AP&L expects to receive results of tests it has contracted for about March 1, 1983.

IV.B - Tests to be performed and by whom AP&L has contracted with Battelle Northwest Laboratories (BNL) to perform the following tests:

1)

Analysis of resins for oxidizing agents 2)

Analysis of resins for " Free Organics" 3)

Acid-Base titration of resin 4)

Heat-Chemical reactions 5)

Cation analysis 6)

Analysis of resins for peroxides 7)

Resin identification IV.C - Status of Chem-Nuclear and Dow Chemical testing efforts-Chem-Nuclear and Dow have not performed any chemical analysis at this time that we are aware of. The only action known to us' is that AP&L contracted with Chem-Nuclear to transport twelve samples of the affected resin to BNL on February 9,1983.

IV.D - Sample availability for independent NRC testing Samples of resin are available to the NRC at ANO until arrangements for final disposal are made.

V.A - Quality. assurance of the HIC to assure safe transportation Resins which have_ experienced an' exothermic reaction will be transferred to another' container for final transport and disposal.

At this time it appears the HIC had no bearing on the exothermic reaction and further it appears that no damage has occurred to the HIC.

Mr. W. C. Seidle February 2:5, 1983 b

V.B - Routine storage of HIC's.

Shipment of resins in the involved lirer.

HIC's are normally stored for a period of 30 days or less inside a shield cask and away from direct sunlight.

.The resins in question will not be shipped in the same liner.

Chem-Nuclear has requested that the affected HIC be returned to Chem-Nuclear for destructive testing.

V.C - Past experience with resins-from the same source No previous problems have occurred.

V.D - Solidification procedure for resin disposal Preparation for disposal will be based on results: from chemical analysis and recommendations from vendors.

Therefore, the disposal procedures are not

-known at this time.

Very.truly yours, i

John R. Marshall

- Manager, Licensing JRM: RR:sl i

4 l--

.i i

f 1

_

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