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| issue date = 03/25/1988
| issue date = 03/25/1988
| title = Forwards Reactor Containment Bldg Third/Final Inservice Integrated Leak Rate Test,First 10-Yr Insp Interval & Type B & C Surveillance Tests, Per 10CFR50,App J,Section V.B
| title = Forwards Reactor Containment Bldg Third/Final Inservice Integrated Leak Rate Test,First 10-Yr Insp Interval & Type B & C Surveillance Tests, Per 10CFR50,App J,Section V.B
| author name = MILTENBERGER S
| author name = Miltenberger S
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
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=Text=
=Text=
{{#Wiki_filter:( Public Service Electric and Gas Company Steven E. Miltenberger Vice President
{{#Wiki_filter:Public Service Electric and Gas Company Steven E. Miltenberger     Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 Vice President -
-Nuclear Operations Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 March 25, 1988 NLR-N88033 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
Nuclear Operations                                          March 25, 1988 NLR-N88033 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REPORT OF TEST RESULTS REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272 Attached is a summary technical report of the third periodic Inservice Containment Integrated Leak Rate (Type A) Test for Salem Unit No. 1. This report is being submitted pursuant to the requirement of 10CFR50, Appendix J, Section V.B. The test was performed during a 24 hour period which commenced at 1045 on December 23, 1987. The test results indicate that the "As-left" integrated containment leakage rate, with corrections, for both the Percent Total Time and Mass Point methods of calculation are 0.039 and 0.043 weight percent per day of containment free volume respectively, at the 95% upper confidence limit. This is in accordance with the acceptance criteria prescribed in 10CFR50, Appendix J and the Salem Unit No. 1 Technical Specifications.
REPORT OF TEST RESULTS REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272 Attached is a summary technical report of the third periodic Inservice Containment Integrated Leak Rate (Type A) Test for Salem Unit No. 1. This report is being submitted pursuant to the requirement of 10CFR50, Appendix J, Section V.B.
The calculated "As-found" integrated containment leakage rate was also within prescribed limits with a leakage rate of 0.063 weight percent per day.
The test was performed during a 24 hour period which commenced at 1045 on December 23, 1987. The test results indicate that the "As-left" integrated containment leakage rate, with corrections, for both the Percent Total Time and Mass Point methods of calculation are 0.039 and 0.043 weight percent per day of containment free volume respectively, at the 95% upper confidence limit. This is in accordance with the acceptance criteria prescribed in 10CFR50, Appendix J and the Salem Unit No. 1 Technical Specifications. The calculated "As-found" integrated containment leakage rate was also within prescribed limits with a leakage rate of 0.063 weight percent per day.
Also included in the report is a summary of rate (Type B & C) tests conducted immediately prior to the tnlrd inservice Type A test. This summary includes "As-found" data, for informational purposes.  
1~~'\.*:*
: ..  
Also included in the report is a summary of locaF:~leak rate (Type B & C) tests conducted immediately prior to the tnlrd inservice Type A test. This summary includes "As-found" data, for informational purposes.
.. If you have any further questions, do contact us. * '*. Attachment
:.~:m:!:* .
-----------------------,,
If you have any further questions, ple~~~- do not                                      h~sitate to contact us.                                           *             '*.
880325 PDR ADOCK 05000272 p DCD Sincerely, '"* not to .... **. 
Sincerely, Attachment
....... Document Control Desk 2 C Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628 03-25-88}}
(      880331002~ 880325 PDR ADOCK 05000272 p                 DCD
 
Document Control Desk           2       03-25-88 C Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628}}

Latest revision as of 06:44, 3 February 2020

Forwards Reactor Containment Bldg Third/Final Inservice Integrated Leak Rate Test,First 10-Yr Insp Interval & Type B & C Surveillance Tests, Per 10CFR50,App J,Section V.B
ML18093A763
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/25/1988
From: Miltenberger S
Public Service Enterprise Group
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18093A765 List:
References
NLR-N88033, NUDOCS 8803310022
Download: ML18093A763 (2)
v • d • e


Text

Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4199 Vice President -

Nuclear Operations March 25, 1988 NLR-N88033 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REPORT OF TEST RESULTS REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST SALEM GENERATING STATION UNIT NO. 1 DOCKET NO. 50-272 Attached is a summary technical report of the third periodic Inservice Containment Integrated Leak Rate (Type A) Test for Salem Unit No. 1. This report is being submitted pursuant to the requirement of 10CFR50, Appendix J, Section V.B.

The test was performed during a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period which commenced at 1045 on December 23, 1987. The test results indicate that the "As-left" integrated containment leakage rate, with corrections, for both the Percent Total Time and Mass Point methods of calculation are 0.039 and 0.043 weight percent per day of containment free volume respectively, at the 95% upper confidence limit. This is in accordance with the acceptance criteria prescribed in 10CFR50, Appendix J and the Salem Unit No. 1 Technical Specifications. The calculated "As-found" integrated containment leakage rate was also within prescribed limits with a leakage rate of 0.063 weight percent per day.

1~~'\.*:*

Also included in the report is a summary of locaF:~leak rate (Type B & C) tests conducted immediately prior to the tnlrd inservice Type A test. This summary includes "As-found" data, for informational purposes.

.~:m:!:* .

If you have any further questions, ple~~~- do not h~sitate to contact us. * '*.

Sincerely, Attachment

( 880331002~ 880325 PDR ADOCK 05000272 p DCD

Document Control Desk 2 03-25-88 C Mr. D. C. Fischer USNRC Licensing Project Manager Mr. T. J. Kenny USNRC Senior Resident Inspector Mr. W. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628

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