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Results
Other: ML20133J280, ML20137H873, ML20137S539, ML20137U023, ML20138L219, ML20141F643, ML20151X932, ML20151Z255, ML20199D831, ML20203E089, ML20206J086, ML20210K261
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MONTHYEARIR 05000348/19850361985-09-19019 September 1985 Insp Repts 50-348/85-36 & 50-364/85-36 on 850811-0910.No Violations or Deviations Noted.Major Areas Inspected: Licensee Action on Previous Enforcement Matters,Monthly Surveillance Observations,Monthly Maint Observation & LERs Project stage: Request ML20133J2801985-10-14014 October 1985 Forwards Three Addl Requests for Relief from Inservice Insp Program for ASME Code Class 1,2 & 3 Components Re Reactor Vessel Flange Ligaments & Visual Exam of Reactor Coolant Pump Casing Pressure Boundary Surfaces.Fee Paid Project stage: Other ML20138L2191985-10-21021 October 1985 Requests Assistance in Reviewing Encl Util 850919 Proposed Administrative Tech Spec Change,Implementing Listed Mgt Changes.Ser & SALP Input Requested by 851031 Project stage: Other ML20137S6411985-11-17017 November 1985 Proposed Changes to Tech Spec 4.2.4.2 & Action 2.d of Table 3.3-1 to Allow Full Core Flux Map for Verifying Indicated Quadrant Power Tilt Ratio When One ex-core Power Range Detector Channel Inoperable Project stage: Request ML20137H8371985-11-22022 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,revising Note 9 of Tech Spec Table 4.3-1 to Require Clearing of Trip Signal Prior to P-9 Setpoint.Fee Paid Project stage: Request ML20137H8731985-11-22022 November 1985 Proposed Tech Spec Changes to Note 9 of Table 4.3-1, Requiring Clearing of Trip Signal Prior to P-9 Setpoint Project stage: Other ML20137U0231985-11-27027 November 1985 Proposed Tech Spec Pages 3/4 2-8,3/4 2-10 & B3/4 2-4, Deleting Rod Bow Penalty Project stage: Other ML20137K9071985-11-27027 November 1985 Forwards Summary of Activities Conducted Since 841130 Submittal & Schedule for Completing Remainder of Emergency Response Capability Integrated Implementation Plan Items. W/One Oversize Graphical Presentation of Plan & Schedule Project stage: Request ML20137U0111985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,deleting Rod Bow Penalty from Tech Specs.Fee Paid Project stage: Request ML20137S5391985-11-27027 November 1985 Proposed Tech Spec Changes,Eliminating Requirement to Shut Down Plant If Coolant Iodine Activity Above 1 Uci/G for Greater than 800 H in 12-month Period,Per Generic Ltr 85-19 Project stage: Other ML20137S5211985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,eliminating Tech Spec Requirement to Shut Down Plant If Coolant Iodine Activity Above 1 Uci/G for Greater than 800 H Period in 12 Months,Per Generic Ltr 85-19.Fee Paid Project stage: Request ML20137S6241985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8 to Permit Full Core Flux Map for Verifying Indicated Quadrant Power Tilt Ratio When One ex-core Power Range Detector Channel Inoperable Project stage: Request ML20136H6711985-12-27027 December 1985 Forwards Safety Evaluation Granting Util 851014 Request for Exemption from Section XI Requirements Re Reactor Vessel Flange Ligaments & Insp of Internal Pressure Boundary Surfaces & Flange Bolts Project stage: Approval ML20136H6821985-12-27027 December 1985 Safety Evaluation Granting Relief from Certain Inservice Testing/Insp Requirements Re Reactor Vessel Flange Ligaments,Reactor Coolant Pump Casing Internal Surfaces & Flange Bolts Project stage: Approval ML20151X9631986-01-27027 January 1986 Safety Evaluation Supporting Amends 60 & 51 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20151X9321986-01-27027 January 1986 Amends 60 & 51 to Licenses NPF-2 & NPF-8,respectively, Revising Administrative Controls Section of Tech Specs to Reflect Titles of Onsite & Offsite Licensee Mgt Project stage: Other ML20151Z2551986-02-0707 February 1986 Forwards Proposed Schedules for Completion of License Amend Requests & Other NRC-related Submittals Project stage: Other ML20199D8311986-03-14014 March 1986 Amends 61 & 52 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec Surveillance Requirements for Quadrant Power Tilt Ratio,Allowing Use of Full Core Flux Map Using Two Sets of Four Symmetric Thimble Locations Project stage: Other ML20199D8431986-03-14014 March 1986 Safety Evaluation Supporting Amends 61 & 52 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20141F6431986-04-11011 April 1986 Forwards Amended Significant Hazards Evaluation & Revised Tech Spec Pages Removing Rod Bow Penalty from Nuclear Enthalpy Hot Channel Factor,Per Util 851127 Request to Amend Licenses NPF-2 & NPF-8 Project stage: Other ML20203E0891986-04-15015 April 1986 Amends 62 & 53 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements Project stage: Other ML20203E0971986-04-15015 April 1986 Safety Evaluation Supporting Amends 62 & 53 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20210K2611986-04-16016 April 1986 Amend 63 & 54 to Licenses NPF-2 & NPF-8,respectively, Deleting Tech Spec 3.4.9 Action Statement a Requiring Plant Shutdown When Coolant Activity Exceeds Cumulative Spiking Limit Project stage: Other ML20210K2731986-04-16016 April 1986 Safety Evaluation Supporting Amends 63 & 54 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20206J0921986-06-16016 June 1986 Safety Evaluation Supporting Amends 64 & 57 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20206J0861986-06-16016 June 1986 Amends 64 & 57 to Licenses NPF-2 & NPF-8,respectively, Modifying Tech Spec 3.2.3 to Delete Rod Bow Penalty & Deleting Tech Spec Figure 3.2-3 Project stage: Other 1985-09-19
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Memng Addrash 2 Atbama Power Company 600 North 16th Street i
L Post Office Scx 2641 1 Birmingham, Alabama 35291
, Telephone 205 783-6090 R. P. Mcdonald Senior Vice President Flintridge Building AlabamaPower November 27, 1985 Docket-Nos. 50-348 50-364 Director, Nuclear. Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C.
20555 F-Attention: Mr. L. S. Rubenstein Joseph M. Farley Nuclear Plant - Units 1 and 2 Celetion 'of Rod Bow Penalty Technical Specification Change Gentlemen:
The phenomenon of fuel rod bowing is accounted for in the departure from-nucleate boiling. ratio (DNBR) safety analysis for Farley Nuclear Plant Units 1 and 2.
Westinghouse WCAP-8691,. Revision 1 has been accepted by the NRC as successfully demonstrating that applicable generic credits for margin result:ng from retained conservatism in the evaluation of DNBR and/or from imeasured plant parameters can be used to offset the effect of DNBR penalties
-due to rod bow. The Joseph M. Farley Nuclear Plant Units:1 and 2 safety analyses maintain sufficient margin'to fully offset the DNBR' effects of rod bow.--
It is therefore proposed that the rod bo.w penalty _(RBP) curre.cly included in the Farley Nuclear Plant Units 1 and 2 Technical Specifications be deleted.- This' penalty is no longer required and the deletion of this 4
penalty will result in the removal of an unnecessary restriction on plant operations. lists the changed Technical Specification pages and
. includes the proposed changed pages. Since the proposed Technical Specification change includes no changes which would significantly increase the probability or consequences of an accident previously. evaluated, no changes which create the possibility of a new or different kind of accident
'from.any' accidents previously evaluated and no changes which would involve a significant reduction in a margin of safety, it is considered t,y Alabama
- Power Company to not involve a significant hazards consideration as defined in 10CFR50.92. This conclusion is based upon this change maintaining the k#8 gj 0 182 851127 P
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Mr. L. S. Rubenstein-November 27, 1985 U. S. Nuclear Regulatory Commission Page 2
' margin inherent in the minimum DNBR limit of 1.30 for transients which must account for fuel rod bowing in the accident analysis and this change not altering the plant configuration or modes of operation. The details 'of the 10CFR50.92 evaluation are provided in Attachment '2.
Alabama Power Company's Plant Operations Review Committee has reviewed this proposed change and the Nuclear-l'perations _ Review Board.will review this proposed change at a future meeting.
As required by 10CFR170.21, the License Amendment Application Fee of
$150.00 is enclosed.
In accordance with 10CFR50.90, three signed originals and forty additional copies of this proposed change are enclosed. A copy of this proposed change has also been sent to Mr. Dan Turner, the Alabama State Designee, in accordance with 10CFR50.91(b)(1).
If-you have any questions, please advise.
Yours very trul,
b R. P. Mcdonald RPM /CJS:ddb-026 Attachments cc: Mr. L. B. Long SWORN TO AND SUBSCRIBE 0 BEFORE ME Dr. J. N. Grace Mr. E. A. Reeves THIS 17d DAY OFMp1985 Mr. W. H. Bradford Mr. Dan Turner
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