GO2-91-012, Provides Actions Planned for Improving Performance of Reactor Bldg post-accident Grab Sampling Sys (REA-SR-48),per Insp Rept 50-397/90-29.State-of-art in-line post-accident Monitoring Sys to Be Installed in Elevated Release Duct
| ML17286B097 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 10/18/1991 |
| From: | Bouchey G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM GO2-91-012, GO2-91-12, GO2-91-193, NUDOCS 9110230034 | |
| Download: ML17286B097 (6) | |
Text
FORD 1
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
J CCESSION NBR:9110230034 DOC.DATE: 91/10/18 NOTARIZED: NO ACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION BOUCHEY,G.D.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
DOCKET 05000397
SUBJECT:
Provides actions planned for improving performance of reactor bldg post-accident grab sampling sys (REA-SR-48),per insp rept 50-397/90-29.State-of-art in-line post-accident monitoring sys to be installed in elevated release duct.
DISTRIBUTION CODE:
IEOZD COPIES RECEIVED:LTR Q ENCL2 SIZE:
TITLE: General (50 Dkt)-Insp Rept/Notice of Violation Response NOTES:
RECIPIENT ID CODE/NAME PD5 PD INTERNAL: ACRS AEOD/DEIIB DEDRO NRR MORISSEAUFD NRR/DLPQ/LPEB10 NRR/DREP/PEPB9H NRR/PMAS/ILRB12 OE DIR REGNI-'liE 2
'EXTERNAL: EG&G/BRYCEFJ.H.
NSIC COPIES LTTR ENCL RECIPIENT ID CODE/NAME ENG,P.L.
AEOD AEOD/DSP/TPAB NRR HARBUCKI C.
NRR SHANKMAN,S NRR/DOEA/OEAB NRR/DST/DIR 8E2 NUDOCS-ABSTRACT OGC/HDS1 RGN5 FILE 01 NRC PDR COPIES LTTR ENCL S,
C, TOTAL NUMBER OF COPIES REQUIRED:
LTTR 24 ENCL
i j
1
ti WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968
~ 3000 George Washington Way
~ Richland, Washington 99352 October 18, 1991 G02-91-193 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Hail Station Pl-137 Washington, D.C.
Gentlemen:
Subject:
NUCLEAR PLANT NO. 2, LICENSE NO. NPF-21 NRC INSPECTION REPORTS 85-20 AND 90-29 REACTOR BUILDING POST-LOCA GRAB SAHPLER (REA-SR-48)
Reference:
- Letter, G02-91-012, GD Bouchey (SS) to NRC "NRC Inspection Report 90-29
- Response to Notice of Violation", Appendix B, dated January 23, 1991 The purpose of this letter is to provide the actions planned for improving the performance of the Reactor Building Post-Accident Grab Sampling System (REA-SR-48).
In Inspection Report 90-29, the NRC followed up on a previous concern (Inspection Report 85-20) pertaining to the ability of REA-SR-48 to quantify post-accident radioiodine concentrations in effluents."'n Appendix B to the referenced letter, the Supply System agreed that improve-ments in system performance was advisable for the long term, and that an evaluation was in progress to determine the best option for improvement with regard to the requirement of NUREG-0737.
Table II.F.1, Attachment 2, of the NUREG requires the ability to representatively sample and quantify the effluent release rate for gaseous/particulate radioiodine under accident conditions.
t As a result of the Engineering evaluation, the decision has been made to install a state-of-the-art, in-line post accident monitoring system (with gamma spectroscopy capability) in the elevated release duct.
The new in-line system will be capable of identifying and quantifying any of the reactor building effluents, including noble gases and gases particulate radioiodine, during normal and post-accident conditions.
The current schedule is to have the system installed and operational by the end of the 1993 maintenahce and refueling outage (June, 1993).
qiio 30034 9iiois PDFl ADOCH, 05000397 6
)1I
Page Two NRC INSPECTION REPORTS 85-20 AND 90-29 REACTOR BUILDING POST-LOCA GRAB SAMPLER (REA-SR-48)
In addition, as stated in our response to Inspection Report 90-29 (Appendix B to the referenced letter) the use of the correcti'on factor is considered to be a
valid, near-term compensation for considering the operability of Sample Rack REA-SR-48 until'uch time that the new monitoring system is installed.
Very truly yours, G.
D. Bouchey, Dire tor Licensing and Assurance JDA/bk cc:
JB Hartin -
NRC RV GP Yuhas NRC RV NS Reynolds
- Winston/Stawn PL Eng -
NRR DL Williams - BPA/399 NRC Site Inspector
- 901A