IR 05000259/1980033
| ML19338F723 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Sequoyah  |
| Issue date: | 09/11/1980 |
| From: | Brownlee V, Conlon T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19338F719 | List: |
| References | |
| 50-259-80-33, 50-260-80-26, 50-296-80-27, 50-327-80-32, NUDOCS 8010270107 | |
| Download: ML19338F723 (3) | |
Text
,m (v)
pa arrug
UNITED STATES
h, NUCLEAR REGULATORY COMMUSION
$
.E REGION 11
,
b[
Q 101 MARIETTA ST., N.W., SUITE 3100
%
o ATLANTA, GEORGIA 30303 Report Nos. 50-259/80-33, 50-260/80-26, 50-296/80-27 and 50-327/80-32
'
Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name:
Browns Ferry 1, 2, 3 and Sequoyah I c
Docket Nos. 50-259, 50-260, 50-296 and 50-327 License Nos. DPR-33, DPR-52, DPR-68 and DPR-77 Inspection at TVA Offices, Chattanooga, Tennessee, Sequoyah Nuclear Plant near Soddy-Daisy, T aness e and Erowns Ferry 1, 2, 3 Nuclear Plants near Athens, Alabama Inspector: l [mq 1/T4 9 - //- 90 V.~L.$rownlee Late Signed Approved by:
//m-f - // -80
'
TM. Conlon, Section' Chief, RCES Branch Date Signed
~
SUMMARY Inspection on August 11-13, 1980 Areas Inspected This routine, unannounced inspection involved 14 inspector-hours onsite in the areas of followup on items of noncompliance relative to 10 CFR Part 21 procedures and procedure implementation.
Results The previously identified items of noncompliance 50-259/79-25-01, 50-260/ 79-25-01, 50-296/79-25-01 and Inspector Followup item 50-259/79-25-02 remain open.
8 o 10 2'r0/o 7
.
...
.
.
DETAILS 1.
Persons Contacted Licensee Employees
- J. L. Harness, Assistant Plant Manager (Browns Ferry)
- R. T. Smith, QA Supervisor (Browns Ferry)
W. E. Andrewr Chief, QA Staff (Chattanooga)
J. E. Law, Suj.ervisor Quality Program Section (Chattanooga)
J. Taylor, QA Staff (Chattanooga)
J. R. Bynum, Assistant Plant Manager (Sequoyah)
T. L. Howard, Site QA Staff (Sequoyah)
L. H. Coots, Site Compliance Staff (Sequoyah)
C. R. Stutz, QA Staff (Sequoyah)
NRC Resident Inspectors R. Sullivan, Browns Ferry B. Cottle, Sequoyah
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on August 13, 1980 with those persons indicated in Paragraph I above.
3.
License Action on Previous Inspection Findings (0 pen) Infraction 259, 260, 296/79-25-01, "Part 21 Procedures and Procedure Implementation".
The inspector reviewed TVA's letter of response dated October 29, 1979; held discussions with responsible Chatt anooga office QA, plant management and Plant QA personnel; and reviewed the following procedures:
N77A14,10 CFR 21 Evaluation & Reporting Requirements a.
b.
N74A8, Nuclear Plant Reportable occurences c.
N72A14, Procurement d.
N74A8, Nuclear Plant Reportable Occurrences e.
SQA 84, Reportavle Occurences f.
SQA 49, Posting g.
SQA 94,10 CFR 21 Evaluation and Reporting Requirements h.
SQA 45, QC of Material, Parts, and Services i.
AI 13, Handling Nonconforming Items J.
AI 11, Receipt Inspection k.
AI 12, Adverse Conditions and Corrective Actions 1.
AI 18, Plant Reporting Requirements BF 16.5, Nonconforming Material Components and Spare Parts m.
n.
' BF 15,10 CFR 21 Evaluation and Reports (DRAFT)
..
.
_
.-
.
_ _-
... _. __
.
-2-
.
Based on review of procedures and discussions with divisional, Sequoyah site and Browns Ferry site personnel the inspector concluded:
Responsible divisional personnel were knowledgeable of Part 21 require-a.
ments.
b.
Divisional procedures N77A14 and N72A14 required revision.
It could not be determined where, within the TVA scope, the TVA part c.
21 or other programs provide the mechanism to assure that the generic aspects of defects will be examined.
d.
Responsible Sequoyah site personnel were knowledgeable of Part 21 requirements.
e.
Sequoyah site procedures provide sufficient control measures and guidance for Part 21 implementation ~and are considered acceptable.
f.
Responsible Brown's Ferry site personnel are not sufficiently know-ledgeable of Part 21 requirements.
g.
Browns Ferry site Part 21 procedures are inadequate.
Responsible divisional and site management personnel concurred with the inspector's conclusions and committed to further review of the contral system and procedural changes where required to properly implement a Part 21 management control program.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Inspector Followup Item 50-259/79-25-02, " Corporate Policy Statements and the Nuclear Safety Review Board Procedure 4.2 Regarding Responsibility for Evaluation - Inconsistances". This matter was not discussed during this inspection. This matter remains open.
.