ML17255A592
| ML17255A592 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/27/1983 |
| From: | Maier J ROCHESTER GAS & ELECTRIC CORP. |
| To: | Crutchfield D Office of Nuclear Reactor Regulation |
| References | |
| PROC-831227, NUDOCS 8401040513 | |
| Download: ML17255A592 (18) | |
Text
REGULATQR+NRORMATION DISTRIBUTION SOfEM(RIDS)
ACCESSION NBR:8401040513 DOC>>DATE: 83/12/27 NOTARIZED:: NO DOCKET ¹ FACIL'.50 244 Robert Emmet Ginna Nuclear Planti Unit ii Rochester G
05000244
'UTH,'AME AUTHOR AFFILIATION Roc;hester Gas S Electr)c Corp>>
MAIERiJ ~ E>>
Rochester Gas 8 Electric Corp.
RKCIP ~ NAME RECIPIENT AFFILIATION CRUTCHF IKLDt D ~
Operating Reactors Branch 5'UBJECT:
"Rev 0 to "Process Control Program,"
I'l/831227 ltd DISTRIBUTION CODEX'001S COPIES RECEIYED:LTR ENCL
'IZE:,.
'ITLE:
OR Submittal:
General Distr ibution NOTES:NRR/DL/SKP icy, 05000?44 RECIPIENT ID CODE/NAME NRA ORBS BC 01 INTERNALS ELD/HDS4 NRR/DL DIR NR TB F ILE 04 COPIES LTTR ENCL 7
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1 RKC IP IENT ID CODE/NAME NRR/DE/MTKB NRR/DL/ORAB NRR/DS I/RAB RGN1 COPIES LTTR ENCL 1
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EXTERNAL! ACRS NRC PDR NTI' NOTES'9 02 6
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.TOTAL NUMBER OF COPIES REQUIRED>>
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- surveyed, serialized and stored in one of the drum storage areas.
Prior to shipment the drums are cleaned, resurveyed, and smeared.
Low Specific Activity (LSA) labels are affixed to the drums prior to shipment to a burial facility in accordance vith the RD-18 series procedures.
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III. Cemented Ultrafiltration Slud e
AD General Description The ultrafiltration unit removes suspended solids from the Waste stream and concentrates this material to a liquid sludge.
'This material is periodically drummed.
Procedures S-4.1.23 and S-4.1.24 control the operation,and drumming of -the ultrafiltration system.
This process in general is the same as described for cemented waste evaporator bottoms.
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S ent Bead Resin A.
General Description Bead resin is used to remove chemical impurities and radioactive contamination from the reactor coolant, the chemical and volume control system, the spent fuel pool, and the liquid waste processing system.
Nhen the resin is exhausted or reaches a radiation limit, the spent resin is sluiced to one of two 158 cubic foot spent resin storage tanks.
After sufficient resin has been collected in one of the storage tanks,'
QA order.
is initiated for use of a transport cask certified by the NRC for transporting greater than Type A quantities of radioactive material.
Upon arrival on site, the transport cask is inspected using a Quality Control Xnspection Procedure (QCXP) specific for each type of cask to ensure the cask meets all the requirements of the Certificate of Compliance and 18 CFR 71.
A steel liner, which contains internal piping to completely dewater the resin, is installed in the cask.
The cask is handled, loaded and unloaded using an H-18 series procedure specific for the model cask used.
Piping is, run from the drumming station to the manway in the top of the liner.
Using procedure S-4.4, spent resin is then slurried from the spent resin storage into the liner with water used for sparging and mixing the resin and nitrogen gas pressure used. to move the resin.
A repre-sentative sample of the resin is obtained and the concentration of each radioisotope is calculated.
After the resin is dewatered or cemented, the liner is capped and sealed and the top is put back on the cask.
The cask is surveyed for radiation and contamination and properly label'ed and marked as specified in a RD-18 series procedure for packaging shipment of radioactive materials.
The RD-18 series includes instructions on any special requirements of the burial site to which the shipment is being sent.
A radioactive shipment record is prepared and all necessary shipping papers and instructions are given t,o the carrier.
The vehicle is placarded, the cask sealed with security seals, and the Quality Control inspection is complete.
The resin is then transported to the burial site.
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1 V. Pilters Nhen filters become saturated or have a high dose rate, they are dewatered and then replaced.
The spent filters are placed in a FIigh Integrity Container-or solidified in an approved media and shipped in accordance with 18CFR71, 18CPR61 and burial site licenses.
The maximum dose rate allowed depends on the cask chosen to ship the materials into.
They are shipped per M-18.6 series procedures.
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/'~~iliiEI"lir~~iu~w ZZ.,
$1AIE ROCHESTER GAS AND ELECTRIC CORPORATION
~ 89 EAST AVENUE, ROCHESTER, N.Y. 14649 JOHN E. MAIER Vice President
'Tc LEP H0 N K Anc* cooc vie 546-2700 December 27, 1983 Director of Nuclear Reactor Regulation Attention:
Mr. Dennis M. Crutchfield, Chief Operating Reactors Branch No.
5 U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Process Control Program R ~ ',E'inna Nuclear Power Plant Docket No.
50-244
Dear Mr. Crutchfield:
Xn accordance with our 1'etter dated September 23,
- 1983, enclosed are three copies of the Ginna Process Control Program.
Very truly yours, John E. Maier Enclosures goal
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