IR 05000309/1988023
| ML20246B927 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 06/28/1989 |
| From: | Ronald Bellamy NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Frizzle C Maine Yankee |
| References | |
| NUDOCS 8907100176 | |
| Download: ML20246B927 (2) | |
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JUN : 8 1999
i Docket No. 50-309 Maine Yankee Atomic Power Company ATTN:
Mr. Charles 0. Frizzle President 83 Edison Drive Augusta, Maine 04336 Gentlemen:
Subject:
Inspection No. 50-309/88-23 This refers to your letter dated June dated January 24, 1989.
14, 1989, in response to our letter Thank you for informing us of the corrective and preventive actions dcc in your letter.
your licensed program.These actions will be examined during a future inspection of umented Your cooperation with us is appreciated.
Sincerely, en;,nal Signed Dy:
- < wid R. DeFmy Ronald R. Bellamy, Chief Facilities Radiological Safety and Safeguards Branch Division of Radiation Safety and Safeguards cc w/ encl
J. Randazza, Assistant Chairman of the Board
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i J. H. Garrity, Vice President, Engineering and Licensing E. T. Bou'ette, Vice Presideat, Operations / Plant Manager P. L. Anderson, Project Manager J. D. Firth, Vice President, Public and Governmental Affairs J. A. Ritsber, Attorney (Ropes and Gray)G. D. Whittie, Manage P. Ahrens, Esquire U. Vanags, Maine State Planning Office Public Document Room (PDR)
Local Public Document Room (LPDR)
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Nuclear Safety Information Center (NSIC)
NRC Resident Inspector State of Maine
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0FFICIAL RECORD COPY RL MY 88-23 - 0001.0.0
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8907100176 890628 PDR
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Naine Yankee Atomic
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Power Company JUN 2 8 1999 bec w/ enc 1:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
L. Tripp, DRP D. Limroth, DRP J.Macdonald,(NRR RI - Yankee P. Sears, LPM, PA0 SALP Reports Only 17 J. Wiggins, DRP J. Dyer, EDO
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/tI/89 0FFIC L RECORD COPY RL MY 88-23 - 0002.0.0 06/26/89 i
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MaineYankee
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RELIAEtLE ELEC% CITY FOR MAINE $1NCE 1972 EDISON DRIVE.. AUGUSTA, MAINE 04330 *(207) 622-4868 t
June 14, 1989 MN-89-81 GDH-89-210 Region I i
. UNITED STATES NUCLEAR REGULATORY COMMISSION-475 Allendale Road King of Prussia, Pennsylvania 19406 Attention: Mr. William T. Russell, Regional Administrator References:
(a) License No. DPR-36 (Docket No. 50-309)
(b) Maine ' Yankee letter to USNRC dated February 23,19S9 (MN-89-21), Response to Notice of Violation (c) USNRC letter to HYAPCo dated January 24, 1989 - Inspection
. Report No. 50-309/88-23 Subject:
Response to Notice of Violation - Inspection Report 50-309/88-23 Gentlemen:
In Reference (b), Maine Yankee responded to the Notice of Violation contained in Reference (c).
In Reference (b), we stated:
A review of all 1988 radioactive waste shipments was made to check for other calculational errors and none were found.
The statement should be revised to read:
A review of all 1958 radioactive waste shipments was made to check for other calculational errors. There were no errors made that l
resulted in a violation of burial site criteria or transportation
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regulations.
The attachment to this letter details the minor errors fcund in 6 of the 17 shipments that were checked.
This ammended response is being submitted to more accurately report the results of our review of the 1988 waste shipment records.
Should you have any questions on this matter, please contact me.
Very truly yours, j
L,9 4 g,,
MAINE YANKEE
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G. D. Whittier, anager Nuclear Engineering and Licensing c: Mr. Richard H. Wessman Mr. Patrick M. Sears Mr. Cornelius F. Holden L--__---___-------------------
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ATTACHMENT
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Shipment No. 0488-215
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On the " Haste Classification Worksheet" the Co-60 activity of 13.60 uCi/cc l
divided by 700 uCi/cc (Class A limit) was reported as 1.94E-4 rather than
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1.94E-2.
The waste was still properly classified as Class B due to Ni-63, l
Sr-90 and Cs-137 specific activities exceeding the Class A limits..The l
total activity for Co-60 on the Raoicactive Shipment Record (RSR) was L
prcperly reported.
Shipment No. 0488-216 Nuclide activities were originally calculated by " Rad.un".
The hand calculation to verify results calculated 2.89Ci more tlan "Radman" but there were no differences in waste classification or transportation requirements. This sort of discrepancy between hand calculations and
"Radman" is typical and expected.
Shipment No. 0888-226 Rounding of volume and mass values resulted in slightly different values for the nuclides listed on the RSR.
For example, the Co-60 activity
. propagated through the calculations as 1.38 uCi/cc versus a rounded value of 1.4 uC1/cc.
The activity difference in drum 5 due to this rounding was less than 4% and the total shipment activity difference was less than 1%.
There were no differences ir, waste classification or transportation requirements.
Shipment No. 0888-192 Ag-110m activity was not added to shipment total. The activity of Ag-110m was less than 1% of the tota' activity.
By regulation and procedure, this amount of activity does not have to be included in the RSR. There w:#d have been no change in the waste classification or transportatica requirements if it had been added.
i Shipment Nr. 0888,276 The Cm-244 activity on the RSR was isted as 2.3 E-1 UCi when it was actually 2.3E-2 uC1. This reduced the total activity of the shipment from 16,779.662 mci to 16,779.452 mC1. This change was much less than 1% of the total activity.
It did not affect the waste classification or transportation requirements as they were based on the correct value of 2.3E-2 uCi.
Shipment No. 0588-159 The curie value of drum HH-57 was originally calculated by improperly applying contact dose rate conversion factors to a three-foot dose rate reading. Subsequently, the activity of the drum was recalculated using the proper conversion factors. After scaling the non-gamma nuclides, the total drum activity was determined to be 5 Ci versus the 1 Ci reported.
The waste class changed from A to B due to higher values of scaled nuclides but this had no effect on burial site criteria as tha drum in question was packed in a HIC with a class C drum.
There was no change in transportation requirements as the waste still met LSA requirements.
l Ol721-RCC
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