Letter Sequence Other |
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Results
Other: 05000302/LER-1981-063-03, /03L-0:on 811005, 12 & 14,various Snubbers Discovered Inoperable.Snubber EFH-106 Failed Due to Bent shaft.RCH-53 & 85 Had Cracked Aluminum bushings.DHR-28, MSH-253 & MUH-46A Failed Due to Excessive Bleed Rate, ML20033B101, ML20033B103, ML20033B106, ML20033B443, ML20038C325, ML20038C331, ML20039E395, ML20039E407, ML20040C103, ML20040C115, ML20040E785
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MONTHYEARML20033B1061981-09-15015 September 1981 Proposed Tech Spec Page 3/4 7-25 & Tables 3 & 4 Re Hydraulic Snubbers Project stage: Other 05000302/LER-1981-063-03, /03L-0:on 811005, 12 & 14,various Snubbers Discovered Inoperable.Snubber EFH-106 Failed Due to Bent shaft.RCH-53 & 85 Had Cracked Aluminum bushings.DHR-28, MSH-253 & MUH-46A Failed Due to Excessive Bleed Rate1981-11-0404 November 1981 /03L-0:on 811005, 12 & 14,various Snubbers Discovered Inoperable.Snubber EFH-106 Failed Due to Bent shaft.RCH-53 & 85 Had Cracked Aluminum bushings.DHR-28, MSH-253 & MUH-46A Failed Due to Excessive Bleed Rate Project stage: Other ML20033B1031981-11-17017 November 1981 Tech Spec Change Request 85 for Amend to App a of License DPR-72,defining Term Operable. Certificate of Svc Encl Project stage: Other ML20033B1011981-11-17017 November 1981 Forwards Tech Spec Change Request 85 Re Amend to App a of OL to Provide Definition of Term Operable Project stage: Other ML20033B4431981-11-17017 November 1981 Advises of Enhanced Snubber Operability Program.Upgraded Program Will Consist of Replacing Bushings of Snubbers Under 50,000 Lb Capacity W/Stainless Steel.Requests That Visual Surveillance Remain at 18-month Intervals Project stage: Other ML20038C3311981-11-27027 November 1981 Notice of Issuance & Availability of Amend 45 to License DPR-72 Project stage: Other ML20038C3281981-11-27027 November 1981 Safety Evaluation Supporting Amend 45 to License DPR-72 Project stage: Approval ML20038C3251981-11-27027 November 1981 Amend 45 to License DPR-72,deleting 4 Hydraulic Shock Suppressors from Tech Specs Table 3.7-3 & Adding Definition of Operable for Snubbers Outside Reactor Bldg During Cycle 4 Operation Project stage: Other ML20039E4071981-12-28028 December 1981 Tech Spec Table 3.7-3 Re Safety Hydraulic Snubbers Project stage: Other ML20039E4051981-12-28028 December 1981 Application for Amend to License DPR-72,consisting of Tech Spec Change Request 38,Revision 1 to Add 120 Snubbers to Table 3.7-3.Table Designates Reactor Bldg Snubbers That Are Inaccessible During Operation Project stage: Request ML20039E3951981-12-28028 December 1981 Forwards Tech Spec Change Request 38,Revision 1,adding 120 Snubbers to Table 3.7-3 of License DPR-72 Tech Specs. Certificate of Svc Encl Project stage: Other ML20040C1151982-01-0707 January 1982 Notice of Issuance & Availability of Amend 49 to License DPR-72 Project stage: Other ML20040C1031982-01-0707 January 1982 Amend 49 to License DPR-72,revising Insp Interval for Hydraulic Snubbers Inside Reactor Bldg to 12 Months Plus 25% for First Insp Following 1981 Refueling Outage Project stage: Other ML20040C1101982-01-0707 January 1982 Safety Evaluation Supporting Amend 49 to License DPR-72 Project stage: Approval ML20040E7851982-01-22022 January 1982 Part 21 Rept Re Cracking of Power Piping Co Hydraulic Snubber Aluminum Adaptor Bushings.Caused by Misapplication of Matls,Resulting in Thermal Expansion.All Reactor Bldg Inside Snubbers Rebuilt.Remaining Snubbers to Be Rebuilt Project stage: Other 1981-12-28
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7590-01 UNITED STATES NUCLE _AR, REGULATORY COMMISSION DOCKET NO. 50-302 FLORIDA POWER CORPORATION, ET AL NOTICE OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE The U. S. Nuclear Regulatory Comission (the Comission) has issued Amendment No. 49 to facility Operating License No. DPR-72, issued to the Florida Power Corporation, City of Alachua, City of Bushnell, City of Gainesville, City of Kissimee, City of Leesburg, City of New Sntyrna Beach and Utilities Comission City of New Sntyrna Beach, City of Ocala, Orlando Utilities Comission and City of Orlando. Sebring Utilities Comission, Seminole Electric Cooperative, Inc., t.nd the City of Tallahassee (the licensees) which revised the Technical Specifications (TSs) for operation of the Crystal River Unit No.
3 Nuclear Generating Plant (the facility) located in Citrus County, Florida. The amendrent is effective as of the date of issuance.
The amendment revises the inspectim interval for hydraulic snubbers inside the reactor building to 12 months + 257. for the first inspection I
following the 1981 refueling outage.
The application for the amendment complies with the standards and requirements of the Atomic Energy Act of 1954,~ as amended (the Act), and the Commission's rules and regulations. The Commission has made l
appropriate findings as required by the Act and the Commission's rules l
and regulations in 10 CFR Chapter I, which are set forth in the license amendment. Prior public notice of this amendment was not required since the amendnent does not involve a significant hazards consideration.
9201270282 820107 PDR ADOCK 05000302 P
PDR
r s
7590-01 The Commission has determined that the issuance of this amendment will not result in any significant environmental impact and that pursuant to 10 CFR 551.5(d)(4) an environmental impact statement or negative declaration and environmental impact appraisal need not be l
prepared in connection with issuance of this amendment.
i For further details with respect to this action, see (1) the application for amendment dated November 17, 1981, (2) Amendment No. 49 to License No. DPR-72, and (3) the Commission's related Safety Evaluation.
All of these items are available for public inspection at the Commission's l
Public Document Room,1717 H Street, NW, Washington, D.C., and at the Crystal River Public Library, 668 N.W. First Avenue, Crystal River, Florida. A copy of items (2) and (3) may be obtained upon request addressed to the U.S. Nuclear Regulatory Commission, Washington, D.C.
20555, Attention:
Director, Division of Licensing.
Dated at Bethesda. Maryland, this 7th day of January 1982.
FOR THE NUCLEAR REGULATORY COMMISSION Jotii F. Stolz, Chief /
OpfratingReactorsBranch#4 Jtvision of Licensing l
t
(