SVP-98-041, Informs That re-evaluation of ISI Program Identified That Basis for Relief Request Is No Longer Applicable.Alternate Exam Has Been Deleted from Class 1 Pressure Test Procedure: Difference between revisions

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


==Subject:==
==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               
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


==Reference:==
==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."
(a) USNRC {{letter dated|date=September 15, 1995|text=letter dated September 15,1995}} to D. L. Farrar, " Safety 4
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.
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.
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.
Respectfully, E. S. Kraft, Jr.
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Site Vice President Quad Citics Station cc:       A. B. Beach, Regional Admmistrator, Region III                                         ,
Site Vice President Quad Citics Station cc:
R. M. Pulsifer, Project Manager, NRR C. G. Miller, Semor Resident Inspector, Quad Cities                         ,
A. B. Beach, Regional Admmistrator, Region III R. M. Pulsifer, Project Manager, NRR j f,]
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)
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C. G. Miller, Semor Resident Inspector, Quad Cities 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)
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Latest revision as of 02:55, 8 December 2024

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
ML20202F228
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 02/10/1998
From: Kraft E
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
SVP-98-041, SVP-98-41, NUDOCS 9802190154
Download: ML20202F228 (1)
v • d • e


Text

.

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

Reference:

(a) USNRC letter dated September 15,1995 to D. L. Farrar, " Safety 4

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 j f,]

h h

C. G. Miller, Semor Resident Inspector, Quad Cities 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,

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