Letter Sequence Approval |
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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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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION L
o wasmmorow.o. c.roess c
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j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 63 TO FACILITY OPERATING LICENSE NO. NPF-2 AND AMENDMENT NO. 54 TO FACILITY OPERATING LICENSE NO. NPF-8 ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NOS. 1 AND 2 l
DOCKET NOS. 50-348 AND 50-364 i
Introduction and Evaluation l
Generic Letter 85-19, Reporting Requirements on Primary Coolant Iodine Spikes, is part of an ongoing Consnission effort to delete unnecessary reporting requirements. The NRC staff determined that reporting requirements related to primary coolant specific activity levels, specifically iodine spikes, 1
can be reduced from a short term report to an item to be included in the l
I annual report. Also, the staff detennined that existing shutdown requirements i
based on exceeding the primary coolant iodine activity limits for an accumulated
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period of over 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> are no longer necessary. This is based on an
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improvement in the quality of nuclear fuel over the past 10 years since 4
appropriate licensee actions would be initiated long before approaching the limit as currently specifiel.
By Generic Letter 85-19, the NRC staff reported these findings and provided j
model Technical Specifications (TS) in Standard Technical Specifiestion format to all licensees for consideration. The model TS deleted Action Statement a.
l which required a plant shutdown when coolant activity exceeded a cumulative l
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spiking limit. Alabama Power Company (APCo) proposed amending the Farley Units j
1 and 2 TS's to match the model TS which are acceptable. APCo also included in l
l the amendment request a proposal to change the definition of Dose Equivalent Iodine 131 (DEI-131) from one compatible with the TID 14844 dose conversion s
}
factors (DCFs) to the newer, less restrictive (i.e., results in lower doses)
Regulatory Guide 1.109 DCFs. This change would bring the DEI definition used by APCo in line with that used in Generic Letter 85-19. Since the Farley Final i
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Safety Analysis Report doses, still based on TID 14844 DCFs, would remain bounding, no increase in offsite consequences would result from this change.
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Safety Summary
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l Because there will be no change in offsite consequences and the.preposed l
amendment is consistent with NRC staff guidance contained in Generic Letter l
j 85-19 and Regulatory Guide 1.109, we find the proposed Technical Specifications acceptable.
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'.. Environmental Consideration These amendments involve a change in the installation or use of the facilities components located within the restricted areas as defined in 10 CFR 20. The staff has determined that these amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that these amendments involve no significant hazards c'ersideration and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR Sec 51.22(c)(9). These amendments also involve changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, with respect to these items, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
Conclusion We have concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Dated:
April 16,1986 1
Principal Contributor:
H. E. Gilpin e
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