Letter Sequence Other |
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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
[Table View] |
Text
Proposed Changed Pages Unit 1 3/4 3-14 Unit 2 3/4 3-14
\\
0512020498Ojoo 48 ADOCK O PDR PDR P
TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.
(1)
If not performed in previous 7 days.
]
(2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.
(3)
Compare incore to excore axial flux difference every 31 EFPD.
Recalibrate if the absolute difference is greater than or equal to 3 percent.
(4)
Manual ESF functional input check every 18 months.
(5)
Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6)
Neutron detectors may be-excluded from CHANNEL CALIBRATION.
(7)
Below the P-6 (Block of Source Range Reactor Trip) setpoint.
(8)
Logic only, if not performed in previous 92 days.
(9)
CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.
(10) - If not performed in the previous 31 days.
FARLEY-UNIT 1 3/4 3-14 AP2NDMENT NO.
TABLE 4.3-1 (Continued)
TABLE NOTATION With the reactor trip syctem breakers closed and the control rod drive system capable of rod withdrawal.
(1)
If not performed in previous 7 days.
(2)
Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference greater than 2 percent.
(3)
Compare incore to excore axial flux difference every 31 EFPD.
kecalibrate if the absolute difference is greater than or equal to 3 percent.
(4)
Manual ESF functional input check every 18 months.
(5) - Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.
(7)
Below the P-6 (Block of Source Range Reactor Trip) setpoint.
(8)
Logic only, if not performed in previous 92 days.
(9)
CHANNEL FUNCTIONAL TEST will consist of verifying that each channel indicates a turbine trip prior to latching the turbine and indicates no turbine trip prior to P-9.
(10) - If not performed in the previous 31 days.
FARLEY-UNIT 2 3/4 3-14 AMENDMENT NO.
