ML19344E216
| ML19344E216 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/03/1980 |
| From: | Counsil W CONNECTICUT YANKEE ATOMIC POWER CO. |
| To: | Galen Smith NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML19344E215 | List: |
| References | |
| NUDOCS 8008280112 | |
| Download: ML19344E216 (3) | |
Text
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e mb CONNECTICUT YANKEE ATOMIC POWER COMPANY BERLIN. CO N N ECTIC UT P. O. BOX 270 M ARTFORD. CONNECTICUT 06101 Tatsewoes 203-666-6911 July 3, 1980 CYH 80-105 DOCKET NO. 50-213 U. S. Nuclear Regulatory Commission Region.I Office of Inspection and Enforcement 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention:
Mr. George Smith Chief, Fuel Materials and Materials Safety Branch
Reference:
Letter, G. H. Smith to W. G. Counsil, dated June 9, 1980 Inspection 50-213/80-09 Gentlemen:
The following information concerning the item of non-compliance described in the above reference is submitted to your office pursuant to the provisions of Section 2.20] of the Nuclear Regulatory Commissions " Rules of Practice", Part 20 Tltle 10, Code of Federal Regulations.
1.
Technical Specification 2.4.3, " Specification for Gaseous Waste Effluents", states in Section 2.4.3.1, "(1) The release rate limit of noble gases from the site shall be:
Qiv 94 l
+ 460 5
<1 i
g v
i where (
= release rate from all roof and unit vents in Ci/sec (ground release)
.80082801/2 N
i
= the ith individual nuclide
= the average gamma energy per disintegration for Eg nuclide i
= the average beta energy per disintegration for Egg nuclide i Contrary to the above, on May 4, 1980, at about 7:55 a.m.
and 9:00 a.m.,
the release rate limit of noble gases exceeded the Technical Specification limit by a factor of 1.66 and 2.78, respectively, for a period of four minutes each.
Response
The following corrective actions have been taken to minimize the probability of recurrence of unplanned gas releases during slurrying of ion exchangers.
1.
The procedure for slurrying reactor coolant letdown ion exchangers has been modified to require a 45 day hold period after an ion exchanger is removed from service.
This will allow more than sufficient decay time.
If an ion exchanger must be slurried in less than the 45 day holdup period the ion exchanger will be flushed with demineralized water to the Primary Drain Tank (PDT) which will subsequently process the gases through the waste gas system.
Once this flushing is completed the slurrying operation will proceed as normally performed.
2.
Communications between the Control Room and the ion exchanger area were reviewed for their adequacy.
Two bull horn speakers have been installed in the ion exchange area to insure that auxiliary operators are in near constant communications with the control room.
l Additional Preventive Measures
[
l l
To further decrease the potential for unplanned releases, a review of i
the operational and design features of the volume control tank and l
waste gas system was conducted.
l f
The following changes are a result of this review.
1.
An Engineering study of the Volume Control Tank vent design and the waste gas holdup system has been initiated.
The VCT vent will be redesigned to limit flow to the waste gas l
holdup system.
After appropriate reviews are completed the redesigned vent system will be installed.
2.
The waste gas surge tank air operated relief valve setpoint will be increased pending appropriate reviews.
3.
Use of the Volume Control Tank (VCT) vent will be minimized until such time as the redesigned vent is installed.
In addition to those corrective and preventive measures described above, we are concurrently preparing a technical specification change request that hopefully will provide relief from what we consider to be an excessively conservative (gaseous release rate) specification limit.
Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY h(/)'
W. G. Counsil Senior Vice President
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