ML20133P660: Difference between revisions
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P ucl Servic s | 4 v Valley Power Staten g | ||
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 | Shippingport. PA 15077-0004 SUSHIL C.JAIN F '" | ||
1 | P ucl Servic s January 20, 1997 Nuclear Power Division i | ||
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 1 | |||
==Subject:== | ==Subject:== | ||
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 | Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Report of Facility Changes, Tests and Experin,.nts i | ||
Report of Facility Changes, Tests and Experin, .nts | i In accordance with 10 CFR 50.59, the Annual Report of Facility Changes, Tests, and Experiments for the Beaver Valley Power Station, Unit No.1, is attached. This i | ||
In accordance with 10 CFR 50.59, the Annual Report of Facility Changes, Tests, | report provides a brief description of each facility and procedure change and a summary of the safety evaluations. The annual report covers the period of January 23, 1995, through January 22,1996. | ||
Each change was evaluated to determine (1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously | Each change was evaluated to determine (1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Updated Final Safety Analysis Report may be increased, or (2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the Updated Final Safety Analysis Report may be created, or (3) if the margin of safety as defined in the basis for any technical specification is reduced. In each case, it was determined that the change did not constitute an unreviewed safety questbn as defined in 10 CFR 50.59. | ||
evaluated in the Updated Final Safety Analysis Report may be increased, or (2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the Updated Final Safety Analysis Report may be created, or (3) if the margin of safety as defined in the basis for any technical specification is reduced. In each case, it was determined that the change did not constitute an unreviewed safety questbn as defined in 10 CFR 50.59. | If you have any questions regarding this report, please contact R. K. Brosi, Manager, Nuclear Safety, at (412) 393-5210. | ||
If you have any questions regarding this report, please contact R. K. Brosi, Manager, Nuclear Safety, at (412) 393-5210. | Sincerely, | ||
/ | |||
l 9701270052 970120 | l Q | ||
9701270052 970120 X,OiI l | |||
Attachment c: | PDR ADOCK 05000334 t | ||
R PDR< | |||
Sushil C. Jam. | |||
/ | |||
~~~~~' | |||
Attachment c: | |||
Mr. D. M. Kern, Sr. Resident Inspector DEllVERING Mr. H. J. Miller, NRC Region I Administrator 0U A LIT Y Mr. D. S. Brinkman, Sr. Project Manager EAEAGV | |||
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Latest revision as of 07:12, 12 December 2024
| ML20133P660 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 01/20/1997 |
| From: | Jain S DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20133P662 | List: |
| References | |
| NUDOCS 9701270052 | |
| Download: ML20133P660 (1) | |
Text
. ~. - - ~ ~ ~ ~.,
.~.-... - -.. -.
t R
4 v Valley Power Staten g
Shippingport. PA 15077-0004 SUSHIL C.JAIN F '"
P ucl Servic s January 20, 1997 Nuclear Power Division i
U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 1
Subject:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Report of Facility Changes, Tests and Experin,.nts i
i In accordance with 10 CFR 50.59, the Annual Report of Facility Changes, Tests, and Experiments for the Beaver Valley Power Station, Unit No.1, is attached. This i
report provides a brief description of each facility and procedure change and a summary of the safety evaluations. The annual report covers the period of January 23, 1995, through January 22,1996.
Each change was evaluated to determine (1) if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the Updated Final Safety Analysis Report may be increased, or (2) if a possibility for an accident or malfunction of a different type than any evaluated previously in the Updated Final Safety Analysis Report may be created, or (3) if the margin of safety as defined in the basis for any technical specification is reduced. In each case, it was determined that the change did not constitute an unreviewed safety questbn as defined in 10 CFR 50.59.
If you have any questions regarding this report, please contact R. K. Brosi, Manager, Nuclear Safety, at (412) 393-5210.
Sincerely,
/
l Q
9701270052 970120 X,OiI l
PDR ADOCK 05000334 t
R PDR<
Sushil C. Jam.
/
~~~~~'
Attachment c:
Mr. D. M. Kern, Sr. Resident Inspector DEllVERING Mr. H. J. Miller, NRC Region I Administrator 0U A LIT Y Mr. D. S. Brinkman, Sr. Project Manager EAEAGV
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