ML20133P014: Difference between revisions

From kanterella
Jump to navigation Jump to search
StriderTol Bot insert
 
StriderTol Bot change
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:* .
{{#Wiki_filter:*
e .
e TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 1630 Chestnut Street Tower II July 10, 1985 BLRD-50-438/84-39 BLRD-50-439/84-36 U.S. Nuclear Regulatory Commissicn Region II Attn:
TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 1630 Chestnut Street Tower II July 10, 1985 BLRD-50-438/84-39 BLRD-50-439/84-36 U.S. Nuclear Regulatory Commissicn Region II Attn:   Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia     30323
Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323


==Dear Dr. Grace:==
==Dear Dr. Grace:==
 
BELLEFONTE NUCLEAR PLANTS UNITS 1 AND 2 - OMISSION OF WATER WEIGHT IN VALVES IN PIPING ANALYSIS BY TELEDYNE - BLRD-50-438/84-39, BLRD-50-439/84 SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-OIE Inspector c,
BELLEFONTE NUCLEAR PLANTS UNITS 1 AND 2 - OMISSION OF WATER WEIGHT IN VALVES IN PIPING ANALYSIS BY TELEDYNE - BLRD-50-438/84-39, BLRD-50-439/84 SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-OIE Inspector                       c, P. E. Fredrickson on June 7, 1984 in accordance with 10 CFR 50.55(e) cn as NCR BLN CEB 8408. This was followed by our first interim report dated July 6, 1984. Enclosed is our second interim report. We expect to s4E lt                     our next report on or about September 13, 1985.                              .
P. E. Fredrickson on June 7, 1984 in accordance with 10 CFR 50.55(e) cn as NCR BLN CEB 8408. This was followed by our first interim report dated July 6, 1984.
If you have any questions, please get in touch with R. H. Shell at                       -
Enclosed is our second interim report. We expect to s4E lt our next report on or about September 13, 1985.
p FTS 858-2688.                                                                           co Very truly yours,                 cn cm TENNESSEE VALLEY AUTHORITY s      ..g Q
If you have any questions, please get in touch with R. H. Shell at
                                                                    . W. Hufham, Manager Licensing and Risk Protection Enclosure cc: Mr. James Taylor, Director (Enclosure)
-p FTS 858-2688.
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.     20555 Records Center (Enclosure)
co Very truly yours, cn cm TENNESSEE VALLEY AUTHORITY
Institute of Nuclear Power Operations                                                       l 1100 circle 75 Parkway, Suite 1500                                                         l Atlanta, Georgia     30339 l
..g s
Q
. W. Hufham, Manager Licensing and Risk Protection 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 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 l
g S21 W M 507to**WS S
g S21 W M 507to**WS S
3 An Equal Opportunity Employer                     '}      IEA7
3
'}
IEA7 An Equal Opportunity Employer


f
f
                                                                                      }
}
T .
T ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 OMISSION OF WATER WEIGHT IN VALVES IN PIPING ANALYSIS BY TELEDYNE BLRD-50-438/84-39, BLRD-50-439/84-36 NCR BLN CEB 8408 10 CFR 50.55(e)
ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 OMISSION OF WATER WEIGHT IN VALVES IN PIPING ANALYSIS BY TELEDYNE BLRD-50-438/84-39, BLRD-50-439/84-36 NCR BLN CEB 8408 10 CFR 50.55(e)
SECOND INTERIM REPORT Description of Deficiency In performing rigorous piping analysis on some valves in the aomponent cooling system, Teledyne Engineering Company, Waltham, Massa 2husetts, did not consider water weight inside the valves. This means that the results of the analysis are potentially unconservative for support loads, nozzles, and stress values.
SECOND INTERIM REPORT Description of Deficiency In performing rigorous piping analysis on some valves in the aomponent         ,
cooling system, Teledyne Engineering Company, Waltham, Massa 2husetts, did not consider water weight inside the valves. This means that the results of the analysis are potentially unconservative for support loads, nozzles, and stress values.
One common table of valve / flange data (which did not account for the weight of the water inside the valve) was prepared to be used in a number of component cooling system problems. All of the affected piping analysis problems are listed below:
One common table of valve / flange data (which did not account for the weight of the water inside the valve) was prepared to be used in a number of component cooling system problems. All of the affected piping analysis problems are listed below:
N4-1KC-P     N4-2KC-P     N4-2KC-G       N4-0KC-K   N4-2KC-H     N4-2KC-N N4-1KC-M     N4-2KC-M     N4-1 KC-G       N4-1KC-H   N4-1KC-N Interim Progress As indicated in our first report on this nonconformance, TVA is reviewing the affected piping analyses to determine the need for reanalysis. The findings to date indicate that the current analysis and related designs are adequate.
N4-1KC-P N4-2KC-P N4-2KC-G N4-0KC-K N4-2KC-H N4-2KC-N N4-1KC-M N4-2KC-M N4-1 KC-G N4-1KC-H N4-1KC-N Interim Progress As indicated in our first report on this nonconformance, TVA is reviewing the affected piping analyses to determine the need for reanalysis. The findings to date indicate that the current analysis and related designs are adequate.
We will provide further information in our next report to be submitted on or about September 13, 1985.
We will provide further information in our next report to be submitted on or about September 13, 1985.
\                                                                                     ]}}
\\
]}}

Latest revision as of 07:17, 12 December 2024

Second Interim Deficiency Rept Re Omission of Water Weight in Valves in Teledyne Engineering Co Piping Analysis. Initially Reported on 840607.Analysis Appears Adequate.Next Rept Expected by 850913
ML20133P014
Person / Time
Site: Bellefonte  
Issue date: 07/10/1985
From: Hufham J
TENNESSEE VALLEY AUTHORITY
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8508140105
Download: ML20133P014 (2)


Text

e TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 1630 Chestnut Street Tower II July 10, 1985 BLRD-50-438/84-39 BLRD-50-439/84-36 U.S. Nuclear Regulatory Commissicn Region II Attn:

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

Dear Dr. Grace:

BELLEFONTE NUCLEAR PLANTS UNITS 1 AND 2 - OMISSION OF WATER WEIGHT IN VALVES IN PIPING ANALYSIS BY TELEDYNE - BLRD-50-438/84-39, BLRD-50-439/84 SECOND INTERIM REPORT The subject deficiency was initially reported to NRC-OIE Inspector c,

P. E. Fredrickson on June 7, 1984 in accordance with 10 CFR 50.55(e) cn as NCR BLN CEB 8408. This was followed by our first interim report dated July 6, 1984.

Enclosed is our second interim report. We expect to s4E lt our next report on or about September 13, 1985.

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

-p FTS 858-2688.

co Very truly yours, cn cm TENNESSEE VALLEY AUTHORITY

..g s

Q

. W. Hufham, Manager Licensing and Risk Protection 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 circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 l

g S21 W M 507to**WS S

3

'}

IEA7 An Equal Opportunity Employer

f

}

T ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 OMISSION OF WATER WEIGHT IN VALVES IN PIPING ANALYSIS BY TELEDYNE BLRD-50-438/84-39, BLRD-50-439/84-36 NCR BLN CEB 8408 10 CFR 50.55(e)

SECOND INTERIM REPORT Description of Deficiency In performing rigorous piping analysis on some valves in the aomponent cooling system, Teledyne Engineering Company, Waltham, Massa 2husetts, did not consider water weight inside the valves. This means that the results of the analysis are potentially unconservative for support loads, nozzles, and stress values.

One common table of valve / flange data (which did not account for the weight of the water inside the valve) was prepared to be used in a number of component cooling system problems. All of the affected piping analysis problems are listed below:

N4-1KC-P N4-2KC-P N4-2KC-G N4-0KC-K N4-2KC-H N4-2KC-N N4-1KC-M N4-2KC-M N4-1 KC-G N4-1KC-H N4-1KC-N Interim Progress As indicated in our first report on this nonconformance, TVA is reviewing the affected piping analyses to determine the need for reanalysis. The findings to date indicate that the current analysis and related designs are adequate.

We will provide further information in our next report to be submitted on or about September 13, 1985.

\\

]