ML20008E391
| ML20008E391 | |
| Person / Time | |
|---|---|
| Issue date: | 09/30/1980 |
| From: | Pappas H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8010270512 | |
| Download: ML20008E391 (2) | |
Text
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,:. E REGION 111 799 ROOSEVELT ROAD O
GLEN ELLYN, ILLINOIS 60137
,o P3D State of Illinois Department of Public Health ATTN:
Mr. Gary N. Wright, Chief Division of Nuclear Safety 535 West Jefferson Street Springfield, IL 62761 Gentlemen:
The enclosed IE Information Notice No. 80-34 titled " Boron Dilution of Reactor Coolant During Steam Generator Decontamination" was sent to the following licensees on September 25, 1980 for information:
American Electric Power Company D. C. Cook (50-315, 50-316)
Commonwealth Edison Company Zion 1, 2 (50-295, 50 304)
Consumers Power Company Palisades (50-255)
Northern States Power Company Prairie Island 1, 2 (50-282, 50-306)
Toledo Edison Company Davis-Besse 1 (50-346)
Wisconsin Electric Power Company Point Beach 1, 2 (50-266, 50-301) 8010270512
t State of Illinois Wisconsin Public Service Corporation Kewaunee (50-305)
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elen Papp
, Chief Administrative Branch
/
Enclosure:
IE Information Notice No. 80-34 cc w/ encl:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b AEOD Resident inspector, RIII Local PDR NSIC TIC 4
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SSINS No.:
6835 glQ yE Accession No.:
8008220239 IEIN 80-34 UNITED STATES HUCLEAR REGULATORY COMMISSION OFF':CE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 September 26, 1980 IE Information Notice No. 80-34:
BORON DILUTION OF REACTOR COOLANT DURING STEAM GENERATOR DECONTAMINATION Description of Circumstances:
Recently two instances of boron dilution of the reactor coolant system have occurred.
Both cases were a result of high pressure washing of the steam generator tube sheets for decontamination to reduce the radiation levels during eddy current testing and related steam generator work.
On May 29, 1980, Trojan Nuclear Plant miscalculated the excess boric acid equired to offset the demineralized water used in washing the tube sheets.
ibis resulted in the boron concentration of the primary coolant being reduced to less than the minimum required by the Technical Specifications.
The dilu-tion was, however, expected since the wash water was allowed to enter the reactor vessel through the nozzles.
On July 5, 1980, San Onofre Unit 1 inadvertently diluted the reactor coolant boron concentration.when the high pressure demineralized flushing water leaked by a dislodged nozzle seal. The inflatable seals had been installed to prevent the non-barated water from entering the reactor.
The resulting boron concentra-tion was greater than required for shutdown margin, but the positive reactivity added was in excess of that allowed by the Technical Specifications.
This Information Notice is provided to identify potential problem areas involved with decontaminating specific areas of steam generators.
It is expected that recipents will review the potential hazards involved and consider increased monitoring of 1) inflatable seal performance, 2) vessel level, and 3) boron concentration.
Increasing the boron concentration of the primary system prior to performing any decontamination activities or using borated water for washing should also be considered.
It is expected that recipients will review this information for possible applicability to their facilities.
No specific action or response is requested at this time.
If you have any questions regarding this matter, please contact the Director of the appropriate Regional Office.
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IN 80-34 September 26, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 80-33 Determination of Teletherapy 9/15/80 All teletherapy Timer Accuracy (G3) licensees 80-32 Clarification of certain 8/12/80 All NRC and agreement requirements for Exclu-state licensees sive-use shipments of radioactive materials 80-31 Maloperation of Gould-8/27/80 All light water reactor Brown Boveri Type 480 facilities holding OLs volt type K-6005 and or cps K-DON 6005 circuit breakers 80-30 Potential for unaccept-8/19/80 All boiling water reactor able interaction between facilities holding power the control rod drive scran reactor OLs or cps.
function and non-essential control air at certain GE BWR facilities 80-29 Broken studs on Terry 8/7/80 All light water reactor turbine steam inlet facilities holding flange power reactor OLs or cps
- Supplement to Notification of 7/29/80 All holders of reactor 80-06 significant events at and near-term OL operating power reactor applicants facilities 80-28 Prompt reporting of 6/13/80 All applicants for and required information holders of nuclear power to NRC reactor cps 80-27 Degradation of reactor 6/11/80 All pressurized water coolant pump studs reactor facilities holding power reactor OLs or cps 80-26 Evaluation of contractor 6/10/80 All Part 50 licensees QA programs
- Operating Licenses or Construction Permits