ML20210K596
| ML20210K596 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/22/1986 |
| From: | Taylor J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | White S TENNESSEE VALLEY AUTHORITY |
| Shared Package | |
| ML20210K600 | List: |
| References | |
| NUDOCS 8604280394 | |
| Download: ML20210K596 (6) | |
See also: IR 05000327/1986027
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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April 22,1986
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Mr. S. A. White
Manager of Nuclear Power
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Tennessee Valley Authority
6N, 38A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
Dear Mr. White:
SUBJECT: REPORT NOS. 50-327/86-27 AFD 50-328/86-27
On February 12 - March 14, 1986, the NRC staff conducted a specisi inspection
to examine design control practices for the Sequoyah Nuclear Power Plant.
The main focus of the inspection was to review the implementation and findings
of the Gilbert / Commonwealth technical review of Sequoyah Engineering Change
Notices (ECNs) for the main and auxiliary feedwater system and the TVA Office
of Engineering (OE) review of unimplemented or partially implemented ECNs at
Sequoyah. Reports for both these reviews were issued on March 4, 1986. The
NRC also conducted additional independent reviews.
The Gilbert / Commonwealth review was considered to be thorough and appropriate
in technical depth within the selected review scope. Specific Gilbert / Common-
wealth findings of significance included a failure to assess generic impli-
cations of concrete cracking near embedded plates due to inadequate edge
distance, and potential cable tray overloading caused by a failure to track
abandoned cables left in the trays. Gilbert / Commonwealth identified lack of
engineering evaluation, lack of documentation of evaluation, lack of detail in
design output, and lack of identification of design input and design bases as
root causes of the findings in their report. The technical and generic issues
identified by Gilbert / Commonwealth appear valid.
The OE "3 system review" was considered to be adequately implemented for the
purpose of determining the need to evaluate all incomplete ECNs. The TVA team
recommendation that all incomplete ECNs be evaluated appears appropriate. In
addition, the review recommended several corrective actions relating to the
control of plant configuration, with which the NRC team agrees.
The NRC team also independently examined the technical adequacy of several
design modifications to better assess the adequacy of the Gilbert and TVA
reviews. The NRC findings substantiate the need for comprehensive corrective
action and further evaluation as indicated by the two reviews. The NRC intends
to closely follow your activities relating to the assurance of adequacy of the
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8604280394 e60422
ADOCK 05000327
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Mr. S. A. White
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April- 22,1986
design control process.
In the review of the additional design areas examined
by the NRC, the following concerns were identified by the NRC team during the
inspection.
In several cases standard industry codes and practices were not followed
in the samples of original design work examined by the NRC-staff in
conjunction with the review of the Gilbert / Commonwealth effort.
There is a lack of available-calculations' supporting the original design
in some disciplines. For example, calculations do not exist to support
the sizing of the station batteries, vital inverters, and battery chargers.
Temporary alteration procedures have been used for permanent design;
management controls did not provide timely engineering review and
closure.
Seismic requirements were not being adequately handled as design input
in some instances nor were they translated into design output documents,
as evidenced by lack of specification of these requirements in purchase
documents and vendor data sheets.
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Five cases were identified where design modifications violate the assump-
tions or the statements contained in unreviewed safety question
determinations.
The concerns and findings of the NRC inspection have been classified as defi-
ciencies, unresolved items, and observations. Deficiencies are errors, procedural
violations or inconsistencies with respect to NRC regulatory requirements or.
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licensing commitments. Unresolved items have been identified where more infor-
mation is needed to reach a conclusion. Other. observations have been described
where it was considered appropriate to call your attention to matters which are
nat deficiencies or unresolved items, but which are recommended for your
consideration.
You should respond in writing to the deficiencies and unresolved items within
30 days after receipt of this letter.
In your assessment of individual defi .
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ciencies identified in the inspection report, you are requested to address the
cause, the extent to which the condition may be reflected in the unreviewed
portion of the design, action to correct the existing condition, the action
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taken to prevent recurrence, and any other information you consider relevant.
For unresolved items, the response should provide information needed to reach-
conclusions concerning acceptability of the specific feature or practice involved.
Comments on observations may be included in your response in addition to'the
requested information but they are not required. Several of the items identified
by the team may be considered Potential Enforcement Findings. Formal enforcement
action, including any further action required, will be identified after receipt
and evaluation of your response.
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Mr. S. A. White
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April 22,1986
.In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosures
will be placed in the NRC Public Document Room.
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Should you have any questions concerning this inspection, please contact me or
Mr. Ted Ankrum (301-492-4774) of this office.
Sincerely,
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s M. Tay1
, Director
fice of Inspection and Enforcement
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Enclosure:
Inspection Report 50-327/86-27 and 50-328/86-27
cc w/ enclosures: See next page
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Mr. S. A. White
Sequoyah Nuclear Power Plant
Tennessee Valley Authority
cc:
Herbert S. Sanger, Jr., Esq.
Tennessee Department of Public Health
,
General Counsel
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ATTN: Director, Bureau of Environmental
Tennessee Valley Authority
Health Services
400 West Summit Hill Drive, E 118 33
Cordell Hull Building
Knoxville, TN 37902
Nashville, TN 37219
Mr. K. W. Whitt
Mr. Michael H. Mobley, Director
Tennessee Valley Authority
Division of Radiological Health
400 West Summit Hill Drive, E3A8
T.E.R.R.A. Building
Knoxville, TN 37902
150 9th Avenue North
Nashville, TN 37203
Mr. Bob Faas
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Westinghouse Electric Corp.
County Judge
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P.O. Box 355
Hamilton County Courthouse
Pittsburgh, PA 15230
Chattanooga, TN 37402
Mr. Jerry Wills
Tennessee Valley Authority
SN 133 Lookout Place
Chattanooga, TN 37402-2801
Mr. Donald L. Williams, Jr.
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Tennessee Valley Authority
400 West Summit Hill Drive, W10B85
Knoxville, TN 37902
,
Resident Inspector /Sequoyah NPS
c/o U.S. Nuclear Regulatory Commission
2600 Igou Ferry Road
Soddy Daisy, TN 37379
Regional Administrator, Region II
U.S. Nuclear Regulatory Commission
101 Marietta Street, N.W., Suite 2900
Atlanta, GA 30323
Mr. Everett Whitaker
Tennessee Valley Authority
SN 128B Lookout Place
Chattanooga, TN 37402-2801
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Mr. S. A. White
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LIST OF ABBREVIATIONS
American Concrete Institute
American Institute of Steel Construction
American Society of Mechanical Engineers
ANSI
American National Standards Institute
American Society for Testing and Materials
CEB
Civil Engineering Branch
CFR
Code of Federal Regulations
Chemical and Volume Control System
Engineering Change Notice
Essential Raw Cooling Water
'
Engineered Safety Features
Final Safety Analysis Report
G/C
Gilbert / Commonwealth
Heating, Ventilation and Air Conditioning
IEEE
Institute of Electrical and Electronics EnginesFs
Loss of Coolant Accident
NRC
U.S. Nuclear Regulatory Commission
Nuclear Steam Supply System
Office of Engineering
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Piping and Instrumentation Diagram
TACF
Temporary Alteration Control Form
Tennessee Valley Authority _
Unreviewed Safety Question
USQD
Unreviewed Safety Question Determination
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