ML18024B448
| ML18024B448 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/04/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML18024B447 | List: |
| References | |
| NUDOCS 8004020249 | |
| Download: ML18024B448 (6) | |
Text
TENNESSEE VALLEYAUTHORlTY CHATTANOOGA. TENNESSEE +7)gt t>l'>KG i(L6s 400 Chestnut Street Tower~MT>'..
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February 4, 1980 I
t Mr. James P. O'Reilly, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Enclosed is our response to R.
C. Lewis'anuary 10, 1980, letter, RII:HLW 50-259/79-38, 50-260/79-38, and 50-296/79-38, concerning activities at Browns Ferry Nuclear Plant which appeared to be in noncompliance with NRC requirements.
We have reviewed the above inspection report and find no proprietary information in it. If you have any questions, please call Jim Domer at FTS 854-2014.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Man ger Nuclear Regulation and Safety Enclosure aoo4oie>94 An Equal Opportunity Employer
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ENCLOSURE
RESPONSE
TO NRC-OIE LETTER FROM R.
C.
LEWIS TO H. G.
PARRIS DATED JANUARY 10, 1980
(
REFERENCE:
RII:HLW 50-259/79-38, 50-260/79-38R 50-296/79-38)
This report responds to the following Notice of Violation described in Appendix A of OIE inspection report RII:HLW 50-259/79-38, 50-260/79-38, and 50-296/79-38.
This is the final report on this noncompliance.
Noncom liance Item (Infraction 79-38-03 As required by Technical Specification 4.7.A.2, integrated leak rate tests shall be performed to verify primary containment integrity.
Criteria for such tests are specified in Appendix J to 10 CFR 50.
Section II.E of Appendix J defines overall integrated leakage rate (Type A test) as the summation of leakage through all potential leakage paths including containment welds, valves, fittings, and components which penetrate containment.
Contrary to the above, during the Type A test on November 23-25,
- 1979, the normal hatch cover for the control rod drive penetration was not used.
The CRD hatch temporary cover used during the Type A test does not provide a
summation of all potential leakage paths through components which penetrate the containment.
This is an infraction.
~Res oese Corr'ective Ste s Which Have Been Taken. and Results Achieved The results of the local leak rate test performed on the normal hatch cover for the control rod drive penetration I-6 following the CILRT was added to the CILRT results.
This summation of leakage satisfied Technical Specifi-cation requirements for containment leakage.
Corrective Ste s Taken to Avoid Further Noncom liance The unit 1 CILRT, scheduled to be conducted in February 1980, will be conducted with the normal X-6 penetration hatch cover installed.
This hatch cover, which will be installed in accordance with the same maintenance instruction used for the installation of the unit 3 hatch cover,'ill be closely inspected for possible leakage during the CILRT.
Assuming that no leakage is detected during this inspection, we will conclude that the
0
unit 3 penetration hatch cover is satisfactory and does in no way compromise the integrity of the unit's containment.
We will regard this as a satisfactory solution to the infraction issued against unit 3.
Date Full Com lienee Will be Achieved These actions will be completed by February 29, 1980.
I V