View source for SVP-98-041, Informs That re-evaluation of ISI Program Identified That Basis for Relief Request Is No Longer Applicable.Alternate Exam Has Been Deleted from Class 1 Pressure Test Procedure

{{Adams
| number = ML20202F228
| issue date = 02/10/1998
| title = Informs That re-evaluation of ISI Program Identified That Basis for Relief Request Is No Longer Applicable.Alternate Exam Has Been Deleted from Class 1 Pressure Test Procedure
| author name = Kraft E
| author affiliation = COMMONWEALTH EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000254, 05000265
| license number = 
| contact person = 
| document report number = SVP-98-041, SVP-98-41, NUDOCS 9802190154
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 1
| project = 
| stage = Request
}}

=Text=
{{#Wiki_filter:.
Comnmnw rakh ihn Comreany Quad Cities Gener.uing Station 22710 2&sth Aicnue North Conkna, 11.612424710
* Tel.4 m in 224i SVP-98441 February 10,1998 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention-        Document Control Desk

==Subject:==
Quad Cities Nuclear Power Station Units 1 and 2 ASME bection XI Relief Request Number PR-01 Sytem Leakage Test Pressure Following the Disassembly and bn-bly of Class 1 Mechanical Connects NRC Docket Numbers 50-254 and 50-265 4                

==Reference:==
(a) USNRC {{letter dated|date=September 15, 1995|text=letter dated September 15,1995}} to D. L. Farrar, " Safety Evaluatxm of the Third Ten-Year Internal Inspection Program and Associated Roquests for Relief."
In keferimce (a) Quad Cities was granted an ASME Relief Request. The alternate examination allows performance of a system leakage test of 920 psig during unit start-up when an unisolable Class 1 mechamal condition in the drywell has been disassembled and reassembled either: 1) subsequent to performance of the system pressure test conducted near the end of each refueling outage; or 2) during a forced maintenance outage in the course of an operating cycle.
Our re-evaluation of the Inservice Inspection Program identified that the basis for the relief request is no l<mger applicabic. Therefore, we have deleted this alternate examination from our Class I pressure test procedure, if you have any questions conceming Ns letter, please contact Mr. Charles Peterson, Regulatory Affairs Manager, at (309) 654-2241, extension 3609.
Respectfully, E. S. Kraft, Jr.
[
Site Vice President Quad Citics Station cc:       A. B. Beach, Regional Admmistrator, Region III                                          ,
R. M. Pulsifer, Project Manager, NRR C. G. Miller, Semor Resident Inspector, Quad Cities                          ,
jhf,] h W. D. Leech, MidAmerican Encgy Company D. C. Tubbs, MidAmerican Energy Company F. A. Spangenberg, Regulatory Affairs Manager, Dresden INPO Records Center Office of Nuclear Facility Safety, IDNS DCD License (both clectronic and hard copies)
M. E. Wagner, Licensing, Comed S * *"*' "'*
u os
                                                          '                           llllll11.lllollla' llll
                                                                                      - i i               , .
9902190154 980210 PDR   ADOCK 05000254 P                       PDR,}}