GO2-96-180, Provides 1995 Dose Assessment Exposure Info Requested by NRC in
| ML17292A451 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/10/1996 |
| From: | Galen Smith WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GO2-96-180, NUDOCS 9609180188 | |
| Download: ML17292A451 (4) | |
Text
CATEGORY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDE)
F ACCESSION NBR:9609180188 DOC.DATE: 96/09/10 NOTARIZED:
NO DOCKET I FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION SMITH,G.O.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides 1995 Dose Assessment exposure info requested by NRC in 960815 ltr.
DISTRIBUTION CODE:
ZESSD COPIES RECEIVED:LTR
(
ENCL I
SIZE:
TITLE: 20.407 Annual Personnel Monitoring Rpt/Annual Rad Exposure Rpt NOTES:
A by Fun T
RECIPIENT ID CODE/NAME PD4-2 PD INTERNAL: ACNW NMSS/SSSS T 8F5 RES/RPHEB COPIES LTTR ENCL 1
0 6
6 1
1 1
1 RECIPIENT ID CODE/NAME COLBURN,T ILE CENTER NR FERB/B RGN4 01 COPIES LTTR ENCL 1
1 1
1 1
1 1
1 EXTERNAL: LITCO BRYCE,J H
NRC PDR 1
1 NOAC 1
1 1
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NOTE TO ALL NRIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK/
ROOM OWFN SD-5(EXT ~ 435-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL 15
WASHINGTON PUBLIC POWER SUPPLY SYSTEM PO. Box 968
~ 3000 George Washington Way
~ Richland, Washington 993S2-0968
~ (S09) 372-SOOO September 10, 1996 G02-96-180 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:
Subject:
WNP-2, OPERATING LICENSE NPF-21 1995 DOSE ASSESSMENT INFORMATION
Reference:
Letter dated August 15, 1996, TG Colburn (NRC) to JV Parrish (SS), "1995 Dose Assessment Information For The Washington Public Power Supply System (WPPSS) Nuclear Project No. 2" In the referenced letter the staff requested that the Supply System provide exposure information for 1995.
Attached is the requested information. If the staff will continue to require this information on an annual basis as it has in the past, we request the NRC evaluate Codifying this
- need, as it has other routine periodic information needs, as a reporting requirement.
Should you have any questions or desire additional information regarding this matter, please contact L. C. Fernandez (509) 377-4147.
F Sincerely, G.O. Smith Plant General Manager Mail Drop 927M Attachment DAS/bk CC:
LJ Callan - NRC RIV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office NS Reynolds - Winston & Strawn TG Colburn - NRR DL Williams - BPA/399 (w/o)
NRC Sr. Resident Inspector - 927N 9609i80i88 9609i0 PDR ADQCK 05000397 P
ATTACHMENT 1.
1995 Refueling Outage Days - 49 2.
3.
4, 1995 Refueling Outage Exposure - 297 man-rem 1996 projected exposure (as of 8/29/96) - 368 man-rem ALARAFeatures Implemented a.
By flooding the undervessel sub-pile floor and sumps with at least 2 ft. of water above the plane of the Floor Drains Radioactive (FDR) sump, the dose rate gradient between the carousel and the shoot-out steel was increased.
Dose rates in the squating position were a factor of 1.8 to 2.0.lower than at head level.
Where possible, work was performed low on the carousel.
b.
Flushing of hotspots on the Reactor Water Cleanup (RWCU), Reactor Feedwater (RFW), and Residual Heat Removal (RHR) systems was successful.
The RHR sensor line was reduced from 300 Rem/hr to background (400 mrem/hr) from Reactor Recirculation (RRC) "A" suction line. RWCU-V-101/103 was reduced from 60 Rem/hr to 7 Rem/hr and the RFW low point drains were reduced from 20 Rem/hr to (
1 Rem/hr.
C.
Permanent shielding installation around the RRC "B" loop on 501'nd the RRC 512'isers in the drywell was completed.
Similar work was performed on RRC loop "A" during R-11 (1996).
Once installed, this shielding mitigates the need to install and remove temporary shielding on the 501* and 512'levations each outage. This equates to more than half the total temporary shielding normally installed in the drywell.
d.
Work Matrix Planning was used in sequencing and interfacing drywell work during the initial planning/scheduling phase for R-10.
This method of plannjng allows a visual overview of the drywell outage scope and indicates where work interferences and conflicts are probable, where detail in planning needs to be increased, where redundant work can be eliminated, and where scheduling considerations need improving.
e.
The undervessel shoot-out steel was removed selectively for the first time in R-10.
f.
Use of remote readout dosimetry (WRM) and video cameras were used to monitor work in High-High Radiation areas.
This saved HP exposure throughout the outage.
ATI'ACHMENT Page 2 of 2 g.
Surgeons gloves are being used for detailed instrument and controls and electrical work. By increasing dexterity for connector replacements and splicing of wire, an estimated time reduction of 15% was achieved.
h.
Whenever possible, insulation removed for support of drywell work is stored in canvas bags near the work location. This reduces the transit time for transporting the insulation to a central storage location.
Also, insulation damage is reduced.
A new index tool for the NA-250 LPRM dry-tube assembly now mitigates the need for removing shoot-out steel for positioning the cruciform assembly between the fuel assemblies.
AllLPRM indexing can be performed from just above the plane of the shoot-out steel.
This saved an estimated 4 Rem in total exposure.
The following is a list ofjobs resulting in ) 10 man-rem exposure in R10 (1995)
Reactor Disassembly Reactor Reassembly Drywell Shielding Installation/Removal RWCU Chemical Decontamination Main Steam Relief Valve Removal/Replacement Inservice Inspection/Errosion-Corrosion 10.25 man-rem 14.25 man-rem 29.95 man-rem 20.59 man-rem 14.83 man-rem 19.49 man-rem