ML14184A596
| ML14184A596 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 04/20/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Utley E CAROLINA POWER & LIGHT CO. |
| Shared Package | |
| ML14184A597 | List: |
| References | |
| NUDOCS 8405160375 | |
| Download: ML14184A596 (2) | |
Text
I BUT ION Docket No.
50-261 April 20, 1934 Gray File NRC PDR L PDR OELD Mr. E. E. Utley, Executive Vice President CParrish Power Supply an dEngineering & Construction ACRS (10)
Carolina Power and Light Company EJordan Post Office Box 1551 JNGrace Raleigh, North Carolina 27602 Deisenhut GRequa
Dear Mr. Utley:
SUBJECT:
IMPLEMENTATION OF 10 CFR 61 FOR H. B. ROBINSON UNIT 2 By letter dated February 2, 1984 you submitted your intended methods for obtaiing scaling factors to be used in implementation of 10 CFR 61 for H. B. Robinson Steam Electric Plant Unit No. 2 and Brunswick Steam Electric Plant Units Nos. 1 and 2. In your letter you indicated that oil and irradiated component waste streams continue to present a problem.
During subsequent discussions with your staff, you requested our early comments with regard to oil at H. B. Robinson Unit No. 2 since storage space is at a premium during the steam generator outage.
We have completed our evaluation of the method you intend to use to obtain scaling factors for the waste oil presently solidfied and stored at the Robinson plant.
We find the proposed method for obtaining scaling factors to be acceptable for the waste oil presently solidified and stored in drums at the Robinson plant. During discussion with your staff, CP&L proposed that all radionuclides be scaled to Co-60, whereas, it was proposed in your February 2, 1984 letter, that activation products be scaled to Co-60 and other radionclides be scaled to Cs-137. We find your proposal to scale all radionuclides to Co-60 acceptable.
Please note that this evaluation is only for the oil waste presenty solidified and stored in drums of the Robinson plant. The remaining items of your submittal will be addressed in a future evaluation.
Our safety evaluation is enclosed.
Steven A.
Vasp Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing
Enclosure:
As stated cc: See next page
- See other white for coourrences ORB#1:DL
- DL METB*
METB*
GRequa;ps qSVaa CNichol WGammill 4/ /84 4
4/20/84 4/20/84 8405160375 940420 PDR ADOCK 05000261 P
-PDR
Docket No. 50-261 Mr. E. E. Utley, Executive Vice President Power Supply an dEngineering & Construction Carolina Power and Light Company Post Office Box 1551 Raleigh, North Carolina 27602
Dear Mr. Utley:
SUBJECT:
IMPLEMENTATION OF 10 CFR 61 FOR H. B. ROBINSON 'NIT 2 By letter dated February 2, 1984 you submitted your i ended methods for obtaiing scaling factor to be used in implementation of 10 CFR 61 for H. B. Robinson Steam Electric Plant Unit No. 2 and/ runswick Steam Electric Plant Units Nos. 1 and 2. In your letter you in cated that oil and irradiate component waste streams continue to p sent a problem.
During subsequent discussions with your stap, you requested our early comments with regard to oil at H. B. Robi n Unit No. 2 since storage space is at a premium during the steam erator outage.
We have completed our evaluation of, method you intend to use to obtain scaling factors for the waste oil pr sently solidfied and stored at the Robinson plant.
We find the proposed method fo obtaining scaling factors to be acceptable for the waste oil presently s idified and stored in drums at the Robinson plant. During discussion w" h your staff, CP&L proposed that all radionuclides be scaled t o-60, whereas, it was proposed in your February 2, 1984 letter, that activat on products be scaled to Co-60 and other radimnclides be scaled o Cs-137. We find your proposas to scale all radimuclides to C-60 acceptable.
Please note that t s evaluation is only for the oil waste presently solidified and st/red in drums of the Robinson plant. The remaining item of your submitt' will be contained in a future evaluation.
Our safety e luation is enclosed.
Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing nclosure:
s stated cc: See next page ORB#1:bj
- 1:DL METB GRequ dYpP'fi a
CNichol W
1 4/,/84 4 /84 4/uj84 4
4