ML20126H618
| ML20126H618 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/03/1985 |
| From: | Whittier G Maine Yankee |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20126H622 | List: |
| References | |
| GDW-85-159, MN-85-105, NUDOCS 8506100370 | |
| Download: ML20126H618 (1) | |
Text
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y E IS N RIVE MAME HARHEE ATOMICPOWERCOMPARUe AUGUSTA, MAINE 04336 g1 (200 623 3 21 June 3, 1985 O
MN-85-105 GDW-85-159 Region I United States Nuclear Regulatory Commission Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Dr. Thomas E. Murley, Regional Administrator Attention:
References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) MYAPCo Letter to U$bRC dated April 30, 1985 (MN-85-82)
Subject:
Inspection 85 Radioactive Materials Transport Program Gentlemen:
This letter provides additional information regarding our response to the subject inspection report as requested by Mr. P. Clemons of your staff.
Attachment A provides a copy of our letter to USNRC describing Maine A copy of this Yankee's program for implementation of 10 CFR 61 requirements.
letter was inadvertently omitted from our earlier response, Reference (b).
A copy of PCR's84-520 through 84-524 and a copy of Procedure 1-18-4 are also attached as Attachments B and C respectively, at the request of Mr. Clemons.
These documents were referenced in Reference (b) in our response to Notice These documents should be considered as additional of Violation 8.
information since they apparently were not brought to Mr. Clemens' attention during the inspection.
Please feel free to contact me if you should have any additional question in tnis matter.
Very truly yours, MAINE YANKEE ATOMIC POWER COM'ANY 8506100370 850603 f
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G. D. Whittier, Manager Nuclear Engineering & Licensing GDW/bjp
Attachment:
cc: Mr. James R. Miller Mr. Cornelius F. Holden
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December 22, 1983 MN-83-268 GDW-83-149 g ;&
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m0PONSIBILITY l
Director of Nuclear Reactor Regulation NE United States Nuclear Regulatory Commission F.ESPOND BY Washington, D. C.
20555 NRC DUE DATE Attention:
Mr. James R. Miller, Chief Operating Reactors Branch No. 3 l
Division of Licensing
References:
(a) License No. DPR-36 (Docket No. 50-309)
Subject:
Request for Review of 10 CFR 61 Implementation Program l
Gentlemen:
l Maine Yankee Atomic Power Company has developed a program for l
implementation of the 10 CFR 61 requirements on waste form and waste l (_
classification, effective December 27, 1983. This program is being submitted for your review and concurrence as an adequate means of implementing these requirements.
l It is anticipated that most process wastes to be shipped from our facility l
will not exceed the concentration limits listed in 10 CFR 61.55 for Class A wastes.
It is our position that wastes solidified in accordance with our i
program, or placed within a certified high integrity container, are sufficiently stable such that they will not affect overall disposal site stability, and need not be segregated upon disposal, irrespective of E
classification.
All operations described in this program will be conducted in accordance with fully approved plant procedures. The waste solidification system, supplied by Hittman Nuclear, will be operated in full conformance with their process control program.
Very truly yours, i
MAItE YANKEE 6TOMIC PDWER COWANY d [' M l
G. D. Whittier Licensing Section Head GDW/bjp
Enclosure:
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cc: Dr. Thomas E. Murley l
Mr. Corneluis F. Holden 38 m
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MA1NE YANKEE 10 CFR 61 I W LEMENTATION PROGRAM A.
WASTE STREAMS 1.
Evaporator Concentrates 2.-
Exhausted Resins 3.
Cartridge Filters 4.
Compactible and Non-Compactible Dry Active Wastes (DAWs)
B.
WASTE FORMS 1.
Stable Wastes In order to preclude trench subsidance after disposal, wastes must have structural stability. Such waste must generally maintain its physical dimensions under expected disposal conditions. Stability can be assured by either the waste form itself or the waste container.
Two options are available to assure stability:
a.
Currently, a Hittman Nuclear portable cement system is utilized to solidify evaporator bottoms in accordance with approved
' procedures and Process Control Program (PCP).
b.
Exhausted resins can either be processed by the above cement system or loaded into approved High Integrity Containers (HICs),
s Cartridge filters are stabilized in concrete in either drums or c.
liners or placed in HICs.
2.
Other Wastes DAW is low in activity and generally will be classified as " Class A JHM waste" requiring segregation upon disposal. These wastes will be packaged within " strong, tight containers".
(49 CFR 173.24)
Compactible wastes will be processed with a hydr.aulic box compactor to reduce volume and increase density to the maximum extent practicable. All waste processing and packaging will be in compliance with approved plant procedures.
C.
WASTE CLASSIFICATION 1.
As a minimum, all radionuclides required by 10 CFR 20.311 and 10 CFR 61.55 will be reported.
2.
A sample of each processed waste batch (concentrates, resin, filter) will be analyzed for gamma emitters. The quantity of all major contributors will be reported for each container. The isotopic
(
distribution contained in DAW will be based on the evaporator concentrates.
3.
Gamma emitters not detected in (2) above, but required to be reported, will be reported as "below the lower limit of detection" (LLD). LLD values-for radionuclides will be reported as required.
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m MAINE YANKEE 10 CFR 61 I W LEMENTATION PROGRAM
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(continued) 4.
Non-gamma emitters required to be reported will be reported using scaling factors, where applicable. These scaling factors are currently based upon a data base developed under a cooperative
. program with the NRC and SAI and modified as the data base expands.
5.
Radioisotopes requiring reporting, which are not easily me.asured or correlatable, will be reported based upon the methods described in
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-the AIF ESP Report, " Methodologies for Classification of LLW From Nuclear Power Plants", November 1983.
6.
One sample, typical of each waste stream, will be fully analyzed annually until it is demonstrated to be unnecessary, to ensure the validity of the factors being utilized.
7.
Gross changes in waste stream radionuclide concentrations or ratios will require a reevaluation of the classification methods and will be addressed as the situation arises.
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