ML18031A679
| ML18031A679 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/30/1986 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8608110443 | |
| Download: ML18031A679 (5) | |
Text
Qt~ 8 TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place JUL 50 $86 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 NUCLEAR PLANT UNITS 1, 2, AND 3 NRC-OIE REGION II INSPECTION REPORT 50-259/86-16,
-260/86-16,
-296/86-1
RESPONSE
TO VIOLATION Enclosed is our response to S.
P. Weise's June 26, 1986 letter to S.
A. White txansmitting IE Inspection Report Nos. 50-259/86-16,
-260/86-16, and
-296/86-16 fox oux Browns Ferry Nuclear Plant which cited TVA with one Severity Level V Violation.
A one-week extension for submittal of this report was discussed with S.
P. Weise on July 28, 1986.
If you have any questions, please get in touch with M. J.
May at (205) 729-3566.
To the best of my knowledge, I declare the statements contained herein are complete and true.
Vexy truly yours, TENNESSEE VALLEY AUTHORITY R. Gxidley, Di ector Nuclear Safet and Licensing Enclosure cc:
Mx. James Taylox', Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatox'y Commission Washington, D.C.
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Sb08110443 Sb0730 PDR ADOCK 05000259 8
PDR An Equal Opportunity Employer
ENCLOSURE
RESPONSE
TO NRC INSPECTION REPORT NOS. 50-259/86-16, 50-260/86-16, AND 50-296/86-16 STEPHEN P.
NEISE'S LETTER TO S.
A. NHITE DATED JUNE 26, 1986 Item 1
10 CFR 50, Appendix B, Criterion VI requires that documents, such as instructions, procedures, and drawings, including changes thereto are reviewed for adequacy and approved for release by authorized personnel.
Contrary to the above, changes were made to the TVA Natural Resource Operations, Field Operations, Quality Assurance Procedure No.
NR-FO-NRE-62.2, Calibration of ORNL Radiation Monitors, Browns Ferry Nuclear Plant only without review and approval by authorized personnel.
The Airflow Calibration section of Procedure NR-FO-NRE-62.2 became inadequate following a modification to the equipment in the spring of 1985.
Since the modification was completed, an unofficial substitute calibration procedure, which itself contained pen-and-ink changes to the typed document, had been used.
The substitute calibration procedure and changes for this procedure had not been reviewed and approved by authorized personnel as of May 21, 1986.
This is a Severity Level V Violation (Supplement I) and is applicable to all three units.
l.
Admission or Denial of the Alle ed Violation TVA admits to the violation.
Procedure NR OPS-FO-NRE-62.2, Rev.
0 was out of date and had several pen-and-ink changes.
Procedure S&F OPS-FO-NRE-062.2, Rev.
1 had not been reviewed and approved by authorized personnel.
The licensee representative had an uncontrolled version of revision l.
2.
Reason for the Violation The following are the root causes that resulted in the violation:
a)
Inadequate control and review of procedures within the Division of Services and Field Operations (S&F OPS) which is in the Office of Natural Resources and Economic Development (ONRED)
~
b)
Inadequate training of the field and service personnel in S&F OPS.
c)
Inadequate oversight of S&F OPS radiological support programs by the Office of Nuclear Power, Radiological Control (Rad Con).
3.
Corrective Ste s Nhich Have Been Taken and Results Achieved a)
S&F OPS reviewed,
- revised, approved, and issued S&F OPS-FO-NRE-62.2, Rev.
1 on June 24, 1986.
There were no technical inadequacies involved.
only procedural changes.
Rad Con personnel approved the procedure before issuance.
b)
Because of the potential generic implications, similar procedures for Sequoyah and Watts Bar Nuclear Plants and a procedure on "Servicing and Preventive Maintenance of Radiation Monitors" have also been revised and
'reissued by SKF OPS.
c)
A SEF OPS review of all SE F OPS'adiological support procedures supporting Browns Ferry,
- Sequoyah, and Watts Bar Nuclear sites has been performed.
4.
Corrective Ste s Which Will Be Taken To Avoid Further Violations a)
SE F OPS radiological support procedures for all TVA nuclear plants identified as needing revising in the recent revie~ (3c above) will be revised by November 1,
1986.
b)
Training of S&F OPS field. and service personnel supporting all TVA nuclear plants in QA program requirements and in the use of procedures will be completed by November 1,
1986.
c)
Existing SKF OPS radiological support procedures wi 11 be reviewed and approved by Rad Con by November 1,
1986.
All future changes to existing and issuance of new SKF OPS radiological support procedures will receive Rad Con review and approval before implementation.
d)
Rad Con personnel will periodically perform field assessments of SKF OPS radiological support activities to confirm technical adequacy and effective performance.
e)
Although not cited as a violati'on, the "Report Details" discuss simiTar procedural problems.
These problems were the subject of violation 50-259/86-18, 50-260/86-18, 50-296/86-18.
Rad Con's predecessor, Radiological Hygiene Branch, is defined in Appendix B Section 5 of the Browns Ferry technical specifications as the organization responsible for environmental radiological monitoring.
In an effort to address this generic
- problem, Rad Con will review the environmental radiological monitoring program.
Rad Con's review will include ONRED radiological support programs and training for performance and effectiveness.
It will be completed by December 1,
- 1986, and will be performed annually thereafter.
5.
Date When Full Com liance Will be Achieved TVA wi 11 be in full compliance by December 1,
1986.
The one-month period after.completion of training is needed to perform QA checks of training effectiveness and adherence to procedures.