ML18030B022
| ML18030B022 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/06/1986 |
| From: | Domer J TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8601270026 | |
| Download: ML18030B022 (6) | |
Text
PÃ/a TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place 0 J)',!I I4 P
I '6 January 6,
1986 U.S. Nuclear Regulatory Commission Region II ATTN:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Dr. Grace:
BROWNS FERRY NU PLANT UNITS 1, 2
AND 3 NRC-OIE REGION II INSPECTION REPORT 50-259/85-53 50-260/85-53, 50-296/85-53
RESPONSE
TO VIOLATION Enclosed is our response to D.
M. Verrelli's December 4, 1985 letter transmitting IE Inspection Report Nos. 50-259/85-53, 50-260/85-53, and 50-296/85-53 for our Browns Ferry Nuclear Plant which cited TVA with one Severity Level V Violation.
H If you have any questions, please get in'touch with R.
E. Alsup at FTS 858-2725.
t To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, TENNESSEE VALLEY AUTHORITY
~
~
~
~
A. Domer, Chief Nuclear Licensing Branch Enclosure cc:
Mr. James Taylor, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 601+70026
~000P59 860106 pDR ADOCI 0
@DR 8
An Fquel Opportunity Employer X&Cl
RESPONSE
NRC INSPECTION REPORT NOS.
50-259/85-53, 50-260/85-53, AND 50-296/85-53 D. M. VERRELLI'S LETTER TO H.
G., PARRIS DATED DECEMBER 4, 1985 Item 1 Technical Specification 4.1.A requires that ins'trumentation systems shall be functionally tested and calibrated as indicated in Tables 4.1.A and 4.1.B respectively.
Table 4.1.B, Reactor Protection System (Scram) Instrument Calibration, requires that the Main'Steam Line High Radiation Instrument Channel be calibrated using a radiation source each refueling outage.
Contrary to the above, the Main Steam Line High Radiaiton Instruments were not calibrated using a radiation source during the End-of-Cycle (EOC) 5 refueling of Unit 1 (April 16, 1983 to January 2, 1984), the EOC-4 refueling outage of Unit 2 (July 30, 1982 to March 18, 1983),
and the EOC-5 refueling outage of Unit 3 (September 6,
1983 to December 1, 1984).
Due to a deficiency in the plant instruction used to comply with the Technical Specification (Surveillance Instruction, SI 4.1.B-10, Main Steam Line Radiation Monitoring System Calibration), the requirements of an instrument calibration were not satisfied.
Technical Specification 1.V.1 defines an instrument calibration as an adjustment of an instrument signal output so that it corresponds within an acceptable range and accuracy to a known value of the parameter which the instrument monitors.
Although SI 4.1.B-10 was performed on these instruments and it required the use of a radiation source, it did not contain an acceptable range and accuracy and no adjustment of the signal output was required.
No evaluation was performed to determine the acceptability 'of instrument output signals ranging from 25 mrem/hour to 200 mrem/hour for the same radiation source strength input to the radiation monitors.
This is a Severity Level V violation (Supplement I) and is applicable to all three units.
1.
Admission or Denial of the Alle ed Violation TVA admits the violati.on.
2.
Reasons for the Violation The steam line monitors are utilized to measure gross radiation as compared to a high background radiation'rate.
The procedure being utilized was basically a source response check and did not contain acceptance criteria.
Page 2
Item 1 continued 3.
Corrective Ste s Which Have Been Taken and Results Achieved Acceptable calibration methods are currently being assessed.
4.
Corrective Ste s Which Will be Taken to Avoid Further Violations Surveillance Instrument 4;1.B-10 will-be revised to include acceptable calibration provisions.
A description of the new calibration procedure will be provided in a supplemental response by March 17, 1986.
5.
Date When Full Co lienee Will Be Achieved The procedure will be revised before the startup of any unit.
~ ~~.l