ML20132D440: Difference between revisions

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II cn June 13, 1985                     c_.
TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II cn June 13, 1985 c_.
BLRD-50-438/84-36                                                         E BLRD-50-439/84-33                                                         2 U.S. Nuclear Regulatory Comission                                           a Region II                                                                 FG Attn: Dr. J. Nelson Grace, Regional Administrator                           -
BLRD-50-438/84-36 E
101 Marietta Street, NW, Suite 2900                                       c.o Atlanta, Georgia 30323                                                   w
BLRD-50-439/84-33 2
U.S. Nuclear Regulatory Comission a
Region II FG Attn:
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 c.o Atlanta, Georgia 30323 w


==Dear Dr. Grace:==
==Dear Dr. Grace:==
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - FAILURE TO IMPACT TEST SUPPORT MATERIALS - BLRD-50-438/84-36, BLRD-50-439/84 FINAL REPORT The subject deficiency was initially reported to NRC-OIE Inspector P. E. Fredrickson on May 9,1984 in accordance with 10 CFR 50.55(e) as NCR BLN CEB 8407. Our first interim report was submitted on June 4,1984.
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - FAILURE TO IMPACT TEST SUPPORT MATERIALS - BLRD-50-438/84-36, BLRD-50-439/84 FINAL REPORT The subject deficiency was initially reported to NRC-OIE Inspector P. E. Fredrickson on May 9,1984 in accordance with 10 CFR 50.55(e) as NCR BLN CEB 8407. Our first interim report was submitted on June 4,1984.
Enclosed is our final report indicating that no nonconforming condition exists and that this matter is no longer considered reportable under the provisions of 10 CFR 50.55(e).
Enclosed is our final report indicating that no nonconforming condition exists and that this matter is no longer considered reportable under the provisions of 10 CFR 50.55(e).
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY J . 4. A f,rJ. W. Hufham, Manager Licensing and Regulations Enclosure cc: Mr. James Taylor, Director (Enclosure)
Very truly yours, TENNESSEE VALLEY AUTHORITY J. 4. A f,rJ. W. Hufham, Manager Licensing and Regulations Enclosure cc:
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Records Center (Enclosure)
Mr. James Taylor, Director (Enclosure)
Institute of Nuclear Power Operations 1100 Qircle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 9500010024 850613                                                       -
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
gDR    ADOCK O          8                                      %m -IM . '~;c W An Equal Opportunity Employer
20555 Records Center (Enclosure)
[     )
Institute of Nuclear Power Operations 1100 Qircle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 9500010024 850613
%m -IM. '~;c W gDR ADOCK O 8
An Equal Opportunity Employer
[
)


        'e ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2
'e ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 FAILURE TO IMPACT TEST SUPPORT MATERIALS BLRD-50-438/84-36, BLRD-50-439/84-33 NCR BLN CEB 8407 10 CFR 50.55(e)
'                            FAILURE TO IMPACT TEST SUPPORT MATERIALS BLRD-50-438/84-36, BLRD-50-439/84-33 NCR BLN CEB 8407 10 CFR 50.55(e)
FINAL REPORT Description of Deficiency Bellefonte Nuclear Plant (BLN) pipe support material impact test requirements are specified by the ASME B&PV Code Section III, subsection NF-5211, and BLN Design Specification BLNP-DS-1915-2992-01. From these sources, ASME safety classes 1, 2, and 3 seismic pipe supports located in areas where the ambient service temperature can fall below 400F are required to be constructed from materials meeting impact test requirements.
FINAL REPORT Description of Deficiency Bellefonte Nuclear Plant (BLN) pipe support material impact test requirements are specified by the ASME B&PV Code Section III, subsection NF-5211, and BLN Design Specification BLNP-DS-1915-2992-01. From these sources, ASME safety classes 1, 2, and 3 seismic pipe supports located in areas where the ambient
Due to misinterpretation of the BLN design specification, various pipe suports in such areas were constructed from materials which had not been qualified to impact test requirements.
;        service temperature can fall below 400F are required to be constructed from materials meeting impact test requirements.     Due to misinterpretation of the BLN design specification, various pipe suports in such areas were constructed from materials which had not been qualified to impact test requirements.
Safety Implications 1
Safety Implications 1
TVA identified all the pipe support materials subject to impact test requirements and either tested the materials in a TVA test facility or requested ITT-Grinnell to do so. All of the tested matelais were accepted for use "as is" based on the test results. In addition, a fracture mechanics evaluation was performed which confirmed the test results.
TVA identified all the pipe support materials subject to impact test requirements and either tested the materials in a TVA test facility or requested ITT-Grinnell to do so.
,          Consequently, TVA han determined that no nonconforming condition exists, and therefore, this conditior is no longer considered reportable under the provisions of 10 CFR 50.55(e).
All of the tested matelais were accepted for use "as is" based on the test results. In addition, a fracture mechanics evaluation was performed which confirmed the test results.
Consequently, TVA han determined that no nonconforming condition exists, and therefore, this conditior is no longer considered reportable under the provisions of 10 CFR 50.55(e).
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Latest revision as of 10:00, 12 December 2024

Final Deficiency Rept Re Failure to Impact Test Support Matls.Initially Reported on 840509.All Tested Matls Accepted for Use Based on Test Results.Condition Not Reportable Per 10CFR50.55(e)
ML20132D440
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 06/13/1985
From: Hufham J
TENNESSEE VALLEY AUTHORITY
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8508010024
Download: ML20132D440 (2)


Text

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TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II cn June 13, 1985 c_.

BLRD-50-438/84-36 E

BLRD-50-439/84-33 2

U.S. Nuclear Regulatory Comission a

Region II FG Attn:

Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 c.o Atlanta, Georgia 30323 w

Dear Dr. Grace:

BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 - FAILURE TO IMPACT TEST SUPPORT MATERIALS - BLRD-50-438/84-36, BLRD-50-439/84 FINAL REPORT The subject deficiency was initially reported to NRC-OIE Inspector P. E. Fredrickson on May 9,1984 in accordance with 10 CFR 50.55(e) as NCR BLN CEB 8407. Our first interim report was submitted on June 4,1984.

Enclosed is our final report indicating that no nonconforming condition exists and that this matter is no longer considered reportable under the provisions of 10 CFR 50.55(e).

If you have any questions, please get in touch with R. H. Shell at FTS 858-2688.

Very truly yours, TENNESSEE VALLEY AUTHORITY J. 4. A f,rJ. W. Hufham, Manager Licensing and Regulations Enclosure cc:

Mr. James Taylor, Director (Enclosure)

Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555 Records Center (Enclosure)

Institute of Nuclear Power Operations 1100 Qircle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 9500010024 850613

%m -IM. '~;c W gDR ADOCK O 8

An Equal Opportunity Employer

[

)

'e ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 FAILURE TO IMPACT TEST SUPPORT MATERIALS BLRD-50-438/84-36, BLRD-50-439/84-33 NCR BLN CEB 8407 10 CFR 50.55(e)

FINAL REPORT Description of Deficiency Bellefonte Nuclear Plant (BLN) pipe support material impact test requirements are specified by the ASME B&PV Code Section III, subsection NF-5211, and BLN Design Specification BLNP-DS-1915-2992-01. From these sources, ASME safety classes 1, 2, and 3 seismic pipe supports located in areas where the ambient service temperature can fall below 400F are required to be constructed from materials meeting impact test requirements.

Due to misinterpretation of the BLN design specification, various pipe suports in such areas were constructed from materials which had not been qualified to impact test requirements.

Safety Implications 1

TVA identified all the pipe support materials subject to impact test requirements and either tested the materials in a TVA test facility or requested ITT-Grinnell to do so.

All of the tested matelais were accepted for use "as is" based on the test results. In addition, a fracture mechanics evaluation was performed which confirmed the test results.

Consequently, TVA han determined that no nonconforming condition exists, and therefore, this conditior is no longer considered reportable under the provisions of 10 CFR 50.55(e).

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