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Id k BOSTON EDIDON COMPANY GENERAL OFFICES 000 SQYLaTON STREET GOSTON. M A S S AC H u s ETTs D 219 9 G. CARL ANDOGNIN1 MANAGCR NUCLEAR OPERATIONS DEPARTMENT
Id k BOSTON EDIDON COMPANY GENERAL OFFICES 000 SQYLaTON STREET GOSTON. M A S S AC H u s ETTs D 219 9 G. CARL ANDOGNIN1 MANAGCR NUCLEAR OPERATIONS DEPARTMENT May 1, 1979
-,'~..                                                                                 May 1, 1979
-, ' ~..
                  '''N-..._                                                           BECo. Ltr. #79-84
'''N-..._
                                      ' ~ .,.
BECo. Ltr. #79-84
                                                  , ~
' ~.,.
Mr. Boyce H. Grier                               ' ' ~~ w Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission                                                   "'s_ ,'
, ~
631 Park Avenue                                                                                 s. _ '
Mr. Boyce H. Grier
King of Prussia, PA.       19406                                                                       ' '-
' ' ~~ w Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission
Licence No. DPR-35 Docket No. 50-293 Response to IE Bulletin #79-04
"'s_
631 Park Avenue
: s. _ '
King of Prussia, PA.
19406 Licence No. DPR-35 Docket No. 50-293 Response to IE Bulletin #79-04


==Dear Sir:==
==Dear Sir:==
 
In a {{letter dated|date=March 30, 1979|text=letter dated March 30, 1979}}, you transmitted IE Bulletin #79-04 titled,
In a letter dated March 30, 1979, you transmitted IE Bulletin #79-04 titled,
" Incorrect Weights For Swing Check Valves Manufactured By Velan Engineering Corporation". Boston Edison Company was requested to take the following actions to review this problem at Pilgrim Nuclear Power Station:
              " Incorrect Weights For Swing Check Valves Manufactured By Velan Engineering Corporation". Boston Edison Company was requested to take the following actions to review this problem at Pilgrim Nuclear Power Station:
1.
: 1. List all Seismic Category I piping systems (or portions thereof) where 3, 4, or 6 inch diam 2ter Velan swing check valves are installed or are scheduled to be installed.
List all Seismic Category I piping systems (or portions thereof) where 3, 4, or 6 inch diam 2ter Velan swing check valves are installed or are scheduled to be installed.


===Response===
===Response===
An examination of Seismic Category I piping systems showed the subject 3, 4, or 6 inch Velan swing check valves to be installed in the below listed systems.
An examination of Seismic Category I piping systems showed the subject 3, 4, or 6 inch Velan swing check valves to be installed in the below listed systems.
Systen                             Numbers of Valves                 Size HPCI Min. Recire. Line                                     1                     4" Core Spray Pump Test                                     2                     6" RHR Makeup Cond. Trans.                                   1                     6" Fuel Pool Cooling                                         1                     3" 2300 184 7906050 6 [
Systen Numbers of Valves Size HPCI Min. Recire. Line 1
4" Core Spray Pump Test 2
6" RHR Makeup Cond. Trans.
1 6"
Fuel Pool Cooling 1
3" 2300 184 7906050 6 [


s   _. .
s DDSTON EoiscN COMPANY Mr. Boyce H. Grier May 1, 1979 Page 2 2.
DDSTON EoiscN COMPANY Mr. Boyce H. Grier May 1, 1979 Page 2
Verify for all those systems identified in item 1 above that correct check valve weights were used in the piping analysis.
: 2. Verify for all those systems identified in item 1 above that correct check valve weights were used in the piping analysis.     Explain how and when the correct valve weights were determined.
Explain how and when the correct valve weights were determined.


===Response===
===Response===
The Velan Valve Company was contacted to determine if ths valve weights shown on project drawings were correct. Velan subsequently verified by weighing types of valves on an as built basis, and found the weights on the Pilgrim Project drawings to be correct. Boston Edison Company was informed of this on April 23, 1979.
The Velan Valve Company was contacted to determine if ths valve weights shown on project drawings were correct. Velan subsequently verified by weighing types of valves on an as built basis, and found the weights on the Pilgrim Project drawings to be correct. Boston Edison Company was informed of this on April 23, 1979.
We then examined the piping analysis to verify that correct weights were used in the calculations and some slight discrepencies were found.       An examination of the stress analysis report for lines containing these
We then examined the piping analysis to verify that correct weights were used in the calculations and some slight discrepencies were found.
'''-  m m valves showed that "as calculated" values were more conservative than
An examination of the stress analysis report for lines containing these valves showed that "as calculated" values were more conservative than m
              ,~'
m
                    ~~1.f the corrected weights were used for 3 of the systems listed.
,~'
                        ~~s,
~~1.f the corrected weights were used for 3 of the systems listed.
: 3. If inco[re'cE" valva. weights were used, explain what actions have been taken or are planned'~tusre-evaluate the piping systems affected.
~~s, If inco[re'cE" valva. weights were used, explain what actions have been 3.
                                                      ' ~ ,
taken or are planned'~tusre-evaluate the piping systems affected.
Response                                 '  ~
' ~,
 
===Response===
~
s~~
s~~
                                                                          ~~~'
~ ~ ~ '
Our plan of action is to re-analyze the af fected piping syas' ems substi-tuting the correct valve weights in our calculations.     This prutir.inary re-analysis to date shows that the seismic stresses and loads are belo'V's ,,
Our plan of action is to re-analyze the af fected piping syas' ems substi-tuting the correct valve weights in our calculations.
the maximum allowable limits and no significant changes are anticipated         ' ' ~ ,
This prutir.inary re-analysis to date shows that the seismic stresses and loads are belo'V's,,
in the outcome of the final analysis.     Should the final analysis indicate any discrepencies you will be immediately notified of a new plan of action.
the maximum allowable limits and no significant changes are anticipated
: 4. Specify for all the affected systems identified in Item I whether modifica-tions were or are required er the piping systems or their supports because of changes in valve weight. Also, include the basis for this determination.
' ' ~,
in the outcome of the final analysis.
Should the final analysis indicate any discrepencies you will be immediately notified of a new plan of action.
4.
Specify for all the affected systems identified in Item I whether modifica-tions were or are required er the piping systems or their supports because of changes in valve weight.
Also, include the basis for this determination.
For those systems in which the actual valve weight is greater than the de-sign weight provide a summary of stresses and loads and their allowable limits for the piping and its supports.
For those systems in which the actual valve weight is greater than the de-sign weight provide a summary of stresses and loads and their allowable limits for the piping and its supports.


===Response===
===Response===
Of the systems identified in Item 1, one case was found to have an actual valve weight greater than the design weight. However utilizing the criterion outlined in our FSAR Appendix A " Pressure Integrity of Piping and Equipment Pressure Parts", the preliminary calculations indicate that the allowable limits for stresses and loads for the piping and its supports do not exceed the original design criteria and therefore no modifications are considered necessary. A summary of stresses and loads for the affected system will be forwarded to you upon its completion but no later than June 1, 1979.
Of the systems identified in Item 1, one case was found to have an actual valve weight greater than the design weight. However utilizing the criterion outlined in our FSAR Appendix A " Pressure Integrity of Piping and Equipment Pressure Parts", the preliminary calculations indicate that the allowable limits for stresses and loads for the piping and its supports do not exceed the original design criteria and therefore no modifications are considered necessary.
A summary of stresses and loads for the affected system will be forwarded to you upon its completion but no later than June 1, 1979.
2300 185
2300 185


BOSTON EDISON COMPANY Mr. Boyce H. Grier May 1, 1979 Page 3
BOSTON EDISON COMPANY Mr. Boyce H. Grier May 1, 1979 Page 3 5.
: 5. Identify the analytical technique including identification of any computer codes used to determine the stresses indicated in Item 4.
Identify the analytical technique including identification of any computer codes used to determine the stresses indicated in Item 4.


===Response===
===Response===
The analytical technique utilized to determine the seismic stresses in Item 4 is the Bechtel Topical Report BP-TOP-1, Rev. 3, January, 1976, titled " Seismic Analysis of Piping Systems".
The analytical technique utilized to determine the seismic stresses in Item 4 is the Bechtel Topical Report BP-TOP-1, Rev. 3, January, 1976, titled " Seismic Analysis of Piping Systems".
Original piping calculations were made using the following computer codes:
Original piping calculations were made using the following computer codes:
Code                     Written By                           Verified By
Code Written By Verified By 1.
: 1. ME-632                 Bechtel Power Corp.               PISOL (EDS Nuclear),
ME-632 Bechtel Power Corp.
PISOL (EDS Nuclear),
PIPESD (UC Berkley &
PIPESD (UC Berkley &
John A. Blume & Assoc.)
John A. Blume & Assoc.)
TPIPE (PMP Systens Engineering Inc.)
TPIPE (PMP Systens Engineering Inc.)
: 2. PISOL                   EDS Nuclear                       NUPIPE (Nuclear Ser-vices Corp.) PIPESD, ADLPIPE (Arthur D.
2.
PISOL EDS Nuclear NUPIPE (Nuclear Ser-vices Corp.) PIPESD, ADLPIPE (Arthur D.
Little Corp) ME 101 (Bechtel Power Corp.)
Little Corp) ME 101 (Bechtel Power Corp.)
If there are any further questions on this subject please feel free to contact us at your convenience.
If there are any further questions on this subject please feel free to contact us at your convenience.
- ~ ,                                                     Very truly yours,
- ~,
                ~ "' ~,                               .
Very truly yours,
~ "' ~,
W/
W/
N   s
N s s. _,'s s.,,'~x ~ ~.
: s. _,'s s.,,'~
c[:
x ~ ~.
Director Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C.
c[:   Director                                                     - . .
20555 2300 186}}
Office of Inspection and Enforcement                                       .
Division of Reactor Operations Inspection                                       -
Washington, D. C. 20555 2300 186}}

Latest revision as of 07:40, 3 January 2025

Respond to IE Bulletin 79-04,Incorrect Weights for Swing Check Valves Mfg by Velan Engineering Corp. Lists Installed Valves by Sys,Number of Valves & Valve Size
ML19263E264
Person / Time
Site: Pilgrim
Issue date: 05/01/1979
From: Andognini G
BOSTON EDISON CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
79-84, NUDOCS 7906050435
Download: ML19263E264 (3)


Text

"

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Id k BOSTON EDIDON COMPANY GENERAL OFFICES 000 SQYLaTON STREET GOSTON. M A S S AC H u s ETTs D 219 9 G. CARL ANDOGNIN1 MANAGCR NUCLEAR OPERATIONS DEPARTMENT May 1, 1979

-, ' ~..

N-..._

BECo. Ltr. #79-84

' ~.,.

, ~

Mr. Boyce H. Grier

' ' ~~ w Office of Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission

"'s_

631 Park Avenue

s. _ '

King of Prussia, PA.

19406 Licence No. DPR-35 Docket No. 50-293 Response to IE Bulletin #79-04

Dear Sir:

In a letter dated March 30, 1979, you transmitted IE Bulletin #79-04 titled,

" Incorrect Weights For Swing Check Valves Manufactured By Velan Engineering Corporation". Boston Edison Company was requested to take the following actions to review this problem at Pilgrim Nuclear Power Station:

1.

List all Seismic Category I piping systems (or portions thereof) where 3, 4, or 6 inch diam 2ter Velan swing check valves are installed or are scheduled to be installed.

Response

An examination of Seismic Category I piping systems showed the subject 3, 4, or 6 inch Velan swing check valves to be installed in the below listed systems.

Systen Numbers of Valves Size HPCI Min. Recire. Line 1

4" Core Spray Pump Test 2

6" RHR Makeup Cond. Trans.

1 6"

Fuel Pool Cooling 1

3" 2300 184 7906050 6 [

s DDSTON EoiscN COMPANY Mr. Boyce H. Grier May 1, 1979 Page 2 2.

Verify for all those systems identified in item 1 above that correct check valve weights were used in the piping analysis.

Explain how and when the correct valve weights were determined.

Response

The Velan Valve Company was contacted to determine if ths valve weights shown on project drawings were correct. Velan subsequently verified by weighing types of valves on an as built basis, and found the weights on the Pilgrim Project drawings to be correct. Boston Edison Company was informed of this on April 23, 1979.

We then examined the piping analysis to verify that correct weights were used in the calculations and some slight discrepencies were found.

An examination of the stress analysis report for lines containing these valves showed that "as calculated" values were more conservative than m

m

,~'

~~1.f the corrected weights were used for 3 of the systems listed.

~~s, If inco[re'cE" valva. weights were used, explain what actions have been 3.

taken or are planned'~tusre-evaluate the piping systems affected.

' ~,

Response

~

s~~

~ ~ ~ '

Our plan of action is to re-analyze the af fected piping syas' ems substi-tuting the correct valve weights in our calculations.

This prutir.inary re-analysis to date shows that the seismic stresses and loads are belo'V's,,

the maximum allowable limits and no significant changes are anticipated

' ' ~,

in the outcome of the final analysis.

Should the final analysis indicate any discrepencies you will be immediately notified of a new plan of action.

4.

Specify for all the affected systems identified in Item I whether modifica-tions were or are required er the piping systems or their supports because of changes in valve weight.

Also, include the basis for this determination.

For those systems in which the actual valve weight is greater than the de-sign weight provide a summary of stresses and loads and their allowable limits for the piping and its supports.

Response

Of the systems identified in Item 1, one case was found to have an actual valve weight greater than the design weight. However utilizing the criterion outlined in our FSAR Appendix A " Pressure Integrity of Piping and Equipment Pressure Parts", the preliminary calculations indicate that the allowable limits for stresses and loads for the piping and its supports do not exceed the original design criteria and therefore no modifications are considered necessary.

A summary of stresses and loads for the affected system will be forwarded to you upon its completion but no later than June 1, 1979.

2300 185

BOSTON EDISON COMPANY Mr. Boyce H. Grier May 1, 1979 Page 3 5.

Identify the analytical technique including identification of any computer codes used to determine the stresses indicated in Item 4.

Response

The analytical technique utilized to determine the seismic stresses in Item 4 is the Bechtel Topical Report BP-TOP-1, Rev. 3, January, 1976, titled " Seismic Analysis of Piping Systems".

Original piping calculations were made using the following computer codes:

Code Written By Verified By 1.

ME-632 Bechtel Power Corp.

PISOL (EDS Nuclear),

PIPESD (UC Berkley &

John A. Blume & Assoc.)

TPIPE (PMP Systens Engineering Inc.)

2.

PISOL EDS Nuclear NUPIPE (Nuclear Ser-vices Corp.) PIPESD, ADLPIPE (Arthur D.

Little Corp) ME 101 (Bechtel Power Corp.)

If there are any further questions on this subject please feel free to contact us at your convenience.

- ~,

Very truly yours,

~ "' ~,

W/

N s s. _,'s s.,,'~x ~ ~.

c[:

Director Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C.

20555 2300 186