ML18029A692
| ML18029A692 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/23/1985 |
| From: | Mccloud D TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8507180153 | |
| Download: ML18029A692 (7) | |
Text
e TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II May -23, 1985 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 50-259/85-21, 50-260/85-21, 50-296/85-21
RESPONSE
TO VIOLATION Enclosed is our response to D. M. Verrelli's April 26, 1985 letter to H.
G. Parris transmitting IE Inspection Report Nos. 50-259/85-21, 50-260/85-21, and 50-296/85-21 for our Browns Ferry Nuclear Plant which cited TVA with one Severity Level V Violation.
If you have any questions, please get in touch with R.
E. Alsup at FTS 858-2725.
To the best of my knowledge, I declare the statements contained herein are complete and true.
Very truly yours, D. E. McCloud Nuclear Engineer Enclosure cc:
Mr. James Taylor, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
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ENCLOSURE
RESPONSE
NRC INSPECTION REPORT NOS.
50-259/85-21, 50-260/85>>21, AND 50-296/85-21 DAVID M. VERRELLI'S LETTER"TO H. G.
PARRIS DATED APRIL 26, 1985 Enclosur e 1
Item 1
10 CFR 50, Appendix B, Criterion III requires that measures to assure design control shall include provisions to assure that appropriate quality standards are specified and included in design documents; the design control measures shall provide for verifying or checking the adequacy of design.
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TVA Engineering Procedure 3.03, Design Calculations, paragraph 2.3, requires that all design calculations shall be checked for adequacy by a qualified person.
The checker must be able to provide independent review.
Paragraph 4.5 requires that any configuration change given by an as-constructed drawing must be reconciled with the associated calculations.
The preparers must ensure that each sheet is identifiable with the document, that the status of each sheet is clear, and that the document has continuity.
Contrary to the above, a system required to mitigate the consequences of a-postulated accident was not being designed to an appropriate quality standard in that a review of design calculations for pipe support HPCI R-86, R2, revealed various discrepancies identified below:
a ~
Calculation Sheet 2 specified 1" plate, the as-built plate was l-l/2" thick.
The 5/16" fillet weld which was subject to 12,000 pound load was simply evaluated by engineering judgement.
No weld calculations were included.
b.
Calculation Sheet 3 specified a 3/4" plate for qualification, actual calculation was based on 1-1/2" thick.
Cross-sectional area of the plate was shown as 8 square inches, actual plate cross-sectional area should be 12 squar e inches.
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Sheet 5 showed two structural members (one vertical and one sloped),
these two members had been removed.
There were no notes to indicate that these members were either voided or super seded.
No weld calculations were found for the two attachment plates (l-l/2"x8"x8")
shown on the as-built drawing.
d.
Sheet 6 specified a plate size of 1-1/2"x12"xl'-2" with 3/4" diameter bolts.
There were no notes to indicate that the plate had been revised to 1-1/2"xl5"xl'-3", and bolt size had been changed to l-l/4" diameter.
The as-built drawing showed a weld connection between strut assembly and the steel beam.
No weld calculations were found.
Page 2
e.
Sheets 10 thru 13 showed support No. R-90 and support detail assembly.
There were no notes to indicate that the R-90 and the support assembly were voided or superseded.
This is a Severity Level V violation (Supplement I).
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Page 3
l.
Admission or Denial of the Alle ed Violation TVA admits the violation occurred as stated.
2.
Reasons For the Violation For items a
& b, the final plate stress calculation incorporated the 1-1/2" plate thickness, but portions of the previous plate property statements were not changed,to reflect the as-designed and as-built conditions.
This was an oversight by both the designer and checker in making the plate calculations consistent.
For item c, both the designer and checker forgot to note in the calculations that portions of the existing steel were to be removed, as documented on the support drawing and reflected in the as-built condition.
For item d, similarly to items a 5 b, the final plate and anchor design calculation reflects the as-built condition, but the previous property statements were not changed to reflect the as-built condition.
This was an apparent oversight by both the designer and checker in not making the plate and anchor calculations consistent.
As for the weld connection between the strut assembly and the steel
- beam, both the designer and checker may have decided by engineering judgment that this weld is adequate but failed to document this judgment.
For item e, sheets 10 through 13 are 79-14 inspection data sheets which should have been marked in a manner'to indicate their use for information only.
Both the designer and checker failed to document and identify superseded or voided information.
3.
Corrective Ste s Which Have Been Taken and Results Achieved The procedural deficiencies as they relate to the failure to follow TVA Engineering Procedure (EP) 3.03 did not result in an unacceptable support.
The calculations will be rechecked and revised in accordance with EP 3.03.
Corrective Ste s Which Will Be Taken to Avoid Further Violations The present designers and checkers responsible for the pipe support have been reminded of the requirements.
Also, a documented training session will be held on EP 3.03 to ensure all personnel are fully informed.
5.
Date When Full Com liance Will Be Achieved Full compliance will be achieved by June 28, l985.
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