ML20032B883
| ML20032B883 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek, Cooper, Arkansas Nuclear, River Bend, Waterford, South Texas, Comanche Peak, Fort Calhoun, Fort Saint Vrain  |
| Issue date: | 07/10/1981 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | ARKANSAS POWER & LIGHT CO., GULF STATES UTILITIES CO., HOUSTON LIGHTING & POWER CO., KANSAS GAS & ELECTRIC CO., LOUISIANA POWER & LIGHT CO., NEBRASKA PUBLIC POWER DISTRICT, OMAHA PUBLIC POWER DISTRICT, PUBLIC SERVICE CO. OF COLORADO, TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| References | |
| NUDOCS 8111060480 | |
| Download: ML20032B883 (3) | |
Text
,Y "o
UNITED STATES E\\
NUCLEAR REGULATORY COMMISSION
" :: g
,, f
. REGION IV
.p 3-Q sta GY AN PLAZA D;lVE, SulTE 1000
'g, o'.\\
,e ARLINGTON, TEXAS 76011 July' 10, 1981, i
Gentlemen:
The enclosed IE Circular is forwa-ded for your action.
No written response to this IE Circular is required.
If you have any questions related to this matter please contact this office.
Sincerely,
'h/:
"t/ a.V/ vMLw Karl V. Seyfrit Director
Enclosures:
1.
IE Circular No. 81-09 2.
List of Recently Issued IE Circulars
&h s
i{
g!A2e88S$89$?
f /-d
. = _ -_.
IE CIRCULAR 81-09 Licensee Facility / Docket Number _
i Arkansas Power and Light Conpany Arkansas Nuclear One,' Unit 1 & 2 Little Rock, Arkansas 50-313; 50-368 Nebraska Public Power District Cooper Nuclear Station Columbus, Nebraska 50-298 Omaha Public Power District Fort Calhoun Station Omaha, Nebraska 50-285 Public Service Company of Colorado Fort St. Vrain Senerating Station Denver, Colorado 50-267 Gulf States Utilities River Bend Beaumor.t, Texas 50-458; 50-459 t
Houston Lighting & Power Company South Texas Project Houston, Texas 50-498; 50-499 Kansas Gas & Electric Company Wolf Creek Wichita, Kansas STN 50-482 Louisiana Power & Light Company Waterford-3 New Orleans, Louisiar'.
50-382 Texas Utilities Generating Company Comanche Peak Steam Electric; Station Dallas, Texas 50-445; 50-446 e,3.'.:
"'9qq
~.u
/
< y 'y 1
Y8** *
\\ 05Wd i
In 7
%ngc8 63/
7 s
I
/
7/d
psecoq
[ j )", ( jo,,
4 UNIT 5
s rsUCLEAR REGUL RY COMMISSION g
REGION IV
-l 811 RYAN PLAZA DRIVE. SUITE 1000
$,^'
s
,d*
ARLINGTON. TEXAS 76011 o..=
July 10','1981 Gentlemen:
The enc.losed IE Circular is forwarded for your information.
Your review of this matter and correction of any identified problems is expected before licensing of your plant.
If you have any questions related to this matter please contact e
this office.
i Sincerely,
' $ d&J,'-
i Karl V. Seyfrit Director
Enclosures:
1.
IE Circular No. 81-09 2.
List of Recently Issued IE Circulars l
s l
P
SSIN No.:
6830 Access No.:
810330373 IEC 81-09 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Circular No. 81-09 July 10, 1981 Page 1 of 2 CONTAINMENT EFFLUENT WATER THAT BYPASSES RADI0 ACTIVITY MONITOR Description of Circumstances:
At Indian Point Units 2 and 3 and at H. B. Robinson Unit 2, licensee reviews of service water systems have identified unmonitored effluent paths from contain-ment.
Although containment cooler water effluent is monitored, containment cooler fan motor cooling water bypasses the monitors by joining the containment cooler water effluent downstream of the radiation monitoring equipment.
This represents a potential unmonitored release path if the containment is at design pressure due to a design basis accident (DBA) and if leaks are present in the fan motor cooler system.
Similar designs may exist at other plants.
Appropriate monitoring of direct discharges (from containment to the environment following a DBA) having the potential to exceed the limits specified in 10 CFR Part 20 is required.
Recommended Actions:
1.
All water system effluents that are not automatically isolated by a high-containment pressure containment isolation signal and that flow directly to the environment from containment should be reviewed to determine whether or not a pathway exists for "significant" unmonitored discharge.
A "signif-icant" discharge, for purposes of this circular, is a discharge where projected concentrations in unrestricted areas are likely to exceed the concentrations listed in 10 CFR Part 20, Appendix B, Table II, column 2, with the containment at design pressure due to a design basis accident and with maximum credible leakage, such as a single completely severed cooler tube, assumed to be present in the water system inside containment.
You may take credit for design pressure in the water system being higher than containment design pressure only for cases where neither single failures, nor operation in degraded modes as permitted by Technical
IE Circular 81-09 Page 2 of 2 Specifications under a limiting condition of operation (LCO), are likely to result in operation of the water system at water pressures lower than the containment design pressure.
2.
All water system effluents that are not automatically isolated by a high-containment pressure containment isolation signal and that flow directly to the environment from containment should be reviewed to determine whether or not any "significant" radioactive discharge can be isolated once it is detected.
The review should include evaluation of the capability of the system to be isolated without interruption of any safety-related functions.
Isolation of the system's inlet as well as its discharge may be required to prevent radioactive discharge through the inlet piping to the inlet piping of a parallel system and/or to ',he environment.
3.
Corrective actions to install detection and isolation methods that provide performance consistent with Technical Specification requirements should be initiated for any "significa n" unmonitored anc/or unisolable discharge pathways.
Although no written response to this circular is requested, a report and cor-rective actions may be required by applicable Technical Specifications in the event an unmonitored and/or unisolable effluent pathway is identified.
If you desire additional information regarding this matter, clease contact the appro-priate IE Regional Office.
~
IE Circular No. 81-09 July 10, 1981.
RECENTLY ISSUED IE CIRCULARS Circular Subject Date Issued To No.
Issued 81-03 Inoperable Seismic 3/2/81 All power reactor facilities Monitoring Instru-
'(reasearch and test) with an mentation Operating License (OL) or Construction Permit (CP) 81-05 Self-Aligning Rod End 3/31/81 All power reactor facilities Bushings for Pipe with an Operating Licenses Supports (0L) or Construction Permit (CP) 81-06 Potential Deficiency 4/14/81 All power reactor facilities Affecting Certain with an Operating License Foxboro 10 to 50 (OL) or Construction Permit Milliampere Transmitters (CP) 81-04 The Role of Shift Tech-4/30/81 All power reactor facilities nical Advisors and Impor-with an Operating Licenses (OL) tance if Licensee Event or near-term Operating Licenses (OL)
Reports 81-07 Control of Radioactively 5/14/81 All power reactor Contaminated Material facilities with an Operating License (OL) or Construction Permit (CP).
81-08 Foundation Materials 5/29/81 All power recctor facilities with an Operating License (0L) or Construction Permit (CP) 81-10 Steam Voiding in the 7/2/81 All power reactor facilities Reactor Coolant System with an Operating License (0L) during Decay Heat Removal or Construction Permit (CP)
Cooldown Enclosure