Letter Sequence Request |
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Results
Other: ML13303B031, ML13305A890, ML13310B024, ML13310B548, ML13310B550, ML13310B673, ML13316A805, ML13316A866, ML13316B055, ML20081B573, ML20133A063, ML20205H689, ML20207N580, ML20212R628
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MONTHYEARML13310B0241983-10-17017 October 1983
Informs of Organizational & Personnel Changes Resulting from Jan 1980 Centralization of Nuclear Engineering & Operations Dept.Revs to Tech Specs Being Prepared for Future Submittal
Project stage: Other
ML13305A5371984-03-0707 March 1984
Forwards Application for Amend 24 to License NPF-10 & Amend 10 to License NPF-15.Amends Revise Tech Spec 4.8.1.1.2.C Re Level of Insolubles in Diesel Fuel Oil & Section 6 Re Organizational Changes
Project stage: Request
ML20081B5641984-03-0707 March 1984
Application for Amend 10 to License NPF-15,revising Tech Spec 4.8.1.1.2.C to Determine Operability of Diesel Generator Should Diesel Fuel Oil Fail to Meet Test for Insolubles & Revising Section 6 Re Organization Changes
Project stage: Request
ML20081B5731984-03-0707 March 1984
Proposed Revs to Tech Spec 4.8.1.1.2.C to Determine Operability of Diesel Generator Should Diesel Fuel Oil Fail to Meet Test for Insolubles & Proposed Revs to Section 6 Re Organizational Changes
Project stage: Other
ML13310B5481984-07-17017 July 1984
Forwards Amend Application 122 to License DPR-13,changing Tech Specs to Reflect Staff Overtime & Administrative Requirements,Per Generic Ltrs 82-12 & 82-16.Fee Encl
Project stage: Other
ML13310B5511984-07-17017 July 1984
Proposed Changes to Tech Spec Section 6.2.2, Administrative Controls, to Add Requirements Re Administration & Use of Staff Overtime
Project stage: Request
ML13310B5501984-07-17017 July 1984
Amend Application 122 to License DPR-13,revising Tech Specs to Add Requirements Re Administration & Use of Unit Staff Overtime,Per Generic Ltrs 82-12 & 82-16
Project stage: Other
ML13310B6691984-09-0404 September 1984
Revised Application to Amend Licenses DPR-13,NPF-10 & NPF-15,changing Tech Specs Re Offsite Organization & Radiation Instrumentation Setpoint
Project stage: Request
ML13310B6731984-09-0404 September 1984
Proposed Tech Spec Table 3.5.10-1 Re Radiation Instrument Alarm Setpoint & Figures 6.2.1.1,5.2-1 & 6.2-1 Re Offsite Organization
Project stage: Other
ML13310B6811984-09-0505 September 1984
Revised Proposed Change 127 to Tech Spec Table 3.5.7-1
Project stage: Request
ML13310B6781984-09-0505 September 1984
Forwards Addl Info Re Proposed Change 127 to Tech Spec Table 3.5.7-1,in Response to 840723 Request
Project stage: Request
ML13330A4421984-09-0707 September 1984
Forwards Request for Addl Info Re Proposed Changes to Tech Specs Concerning Onsite Organization,Review Responsibilities & Control Room Command Function.Meeting Will Be Scheduled in Future
Project stage: RAI
ML13330A1671984-11-30030 November 1984
Rev 1 to Proposed Change 119 to Tech Specs,Revising Administrative Controls on Staff Working Hours by Job Classification
Project stage: Request
ML13330A4591984-11-30030 November 1984
Application for Amend to License DPR-13,consisting of Rev 1 to Proposed Change 119 to Tech Specs Re Administrative Controls on Working Hours of Staff Job Classifications,Per NUREG/CR-1764
Project stage: Request
ML13324A5301984-12-27027 December 1984
Summary of 841211 Meeting W/Util Re Proposed Tech Spec Changes on Administrative Controls.List of Attendees Encl
Project stage: Meeting
ML13316A8051985-03-0606 March 1985
Amend 88 to License DPR-13,adding Administrative Guidance & Requirements Re Assignment of Overtime to Personnel Performing safety-related Activities
Project stage: Other
ML13316A8031985-03-0606 March 1985
Forwards Amend 88 to License DPR-13 & Safety Evaluation. Amend Adds Administrative Guidance & Requirements Re Assignment of Overtime to Personnel Performing safety-related Activities
Project stage: Approval
ML13316A8081985-03-0606 March 1985
Safety Evaluation Supporting Amend 88 to License DPR-13
Project stage: Approval
ML13331A8031985-04-12012 April 1985
Forwards Responses to Questions Re Proposed Change 130 & Proposed Tech Spec Section 6.0, Administrative Controls. Onsite & Offsite Organization Charts Revised
Project stage: Request
ML13311A3851985-04-12012 April 1985
Rev 0 to Energy Balance Method Verification
Project stage: Request
ML20133A0631985-08-0202 August 1985
Proposed Tech Specs Extending Time Period for Submittal of Semiannual Radioactive Effluent Release Rept for 90 Days
Project stage: Other
ML13316A8691985-10-15015 October 1985
Safety Evaluation Supporting Amend 91 to License DPR-13
Project stage: Approval
ML13316A8661985-10-15015 October 1985
Amend 91 to License DPR-13,approving Tech Spec Revs Re Administrative Controls,Including Reporting Requirements,Min Shift Crew Composition & Offsite Organization
Project stage: Other
ML13316A8641985-10-15015 October 1985
Forwards Amend 91 to License DPR-13 & Safety Evaluation. Amend Approves Tech Spec Revs Re Administrative Controls, Including Reporting Requirements,Min Shift Crew Composition & Offsite Organization
Project stage: Approval
ML13305A8901986-06-30030 June 1986
Rev 2 to Chemistry Procedure SO123-III-6.6, Diesel Fuel Oil Specs & Testing Requirements
Project stage: Other
ML20206U7991986-09-30030 September 1986
Revised Proposed Tech Spec Change PCN 192,in Response to Generic Ltr 84-15 Concerning Cold Fast Start Testing.Addl Justification Also Encl,Per 860814 Meeting
Project stage: Meeting
ML20207N5331987-03-0909 March 1987
Forwards Notice of Withdrawal of License Amend Request NPF-10/15-75 Proposing Amends to Licenses NPF-10 & NPF-15. Withdrawn Amend Proposed Revs to Tech Spec 4.8.1.1.2.c & Was Superseded by Util 860317 Application
Project stage: Withdrawal
ML20207N5801987-03-0909 March 1987
Notice of Withdrawal for License Amend Request NPF-10/15-75. Amend Proposed Revs to Licenses NPF-10 & NPF-15 Re Determination of Diesel Generator Operability When Fuel Oil Fails to Pass Test for Insolubles
Project stage: Other
ML20212R6281987-04-0909 April 1987
Amends 59 & 48 to Licenses NPF-10 & NPF-15,respectively, Reducing Frequency of Emergency Diesel Generator (EDG) Fast Starts,Revising Diesel Fuel Oil Surveillance & Reducing Number of EDG Tests
Project stage: Other
ML20212R6481987-04-0909 April 1987
Safety Evaluation Supporting Amends 59 & 48 to Licenses NPF-10 & NPF-15,respectively
Project stage: Approval
ML13316B0521988-08-0303 August 1988
Forwards Amend 105 to License DPR-13 & Safety Evaluation. Amend Incorporates Recent Organizational Changes & Reflects Recent 10CFR50 NRC Correspondence Requirements.Changes Re Onsite & Offsite Organization Charts Not Included
Project stage: Approval
ML13316B0551988-08-0303 August 1988
Amend 105 to License DPR-13,revising Tech Specs to Be Consistent W/Recent Util Organizational Changes & Recent 10CFR50 NRC Correspondence Requirements
Project stage: Other
ML13316B0561988-08-0303 August 1988
Safety Evaluation Supporting Amend 105 to License DPR-13
Project stage: Approval
ML20205H6891988-10-18018 October 1988
Corrected Amends 68 & 57 to Licenses NPF-10 & NPF-15, Respectively,Deleting Onsite & Offsite Organization Charts & Revising Reporting Responsibility of Independent Safety Engineering Group & Nuclear Safety Group
Project stage: Other
ML13303B0311989-04-12012 April 1989
Advises That Proposed Change PCN-83 to Licenses NPF-10 & NPF-15,revising Section 6, Administrative Controls Withdrawn,In Response to Util Requests.Fr Notice of Withdrawal Will Be Prepared
Project stage: Other
ML13303B0911989-04-25025 April 1989
Forwards Notice of Withdrawal of 840307 Application for Amends to Licenses NPF-10 & NPF-15,revising Administrative Controls of Tech Specs to Reflect Changes in Util Organizational Structure
Project stage: Withdrawal
ML20245J6161989-04-25025 April 1989
Notice of Withdrawal of 840307 Application for Amends to Licenses NPF-10 & NPF-15,revising Tech Specs to Reflect Changes in Util Organizational Structure & to Incorporate New NRC Reporting Requirements
Project stage: Withdrawal
1985-03-06
[Table View] |
Text
ATTACHMENT 1 TABLE 3.5.7-1 AUXILIARY FEEDWATER INSTRUMENTATION MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION
- a. Manual Actuation 2
1 2
1, 2, 3 F
- b. Automatic Actuation Logic 2
1 2
1, 2. 3 G
- c. Steam Generator Water Level-Low
- i. Start Motor Driven Pump 3
,2 2
1, 2, 3 H, I ii. Start Turbine-Driven Pump 3
2 2
1, 2. 3 H, I ACTION F -
With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
ACTION G -
With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for surveillance testing per Specification 4.1.8 provided the other channel is OPERABLE.
ACTION H -
With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, or an operator shall assume continuous surveillance and actuate manual initiation of auxiliary feedwater, if necessary.
ACTION I -
With more than one channel inoperable, an operator shall assume continuous surveillance and actuate manual initiation of auxiliary feedwater, if necessary. Restore the system to no more than one channel inoperable within 7 days, or be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
8340910017 64:310905 PDR AMUC 05o)00206 PR
ATTACHMENT 2 4.1.9 Auxiliary Feedwater System Surveillance Applicability: Applies to the motor driven auxiliary feedwater pump, and turbine driven auxiliary feedwater pump, and auxiliary feedwater valves for MODES 1. 2 and 3.
ObJective:
To ensure the reliability of the auxiliary feedwater system.
Specification: A. Each auxiliary feedwater pump shall be demonstrated OPERABLE by testing each pump in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g).
except where specific written relief has been granted by the NRC pursuant to 10 CFR 50.55a(g)(6)(i).
B. At least once per 31 days an inspection shall be made to verify that each non-automatic valve in the emergency flow path that is not locked, sealed, or otherwise secured in position is in its correct position.
C. Each auxiliary feedwater pump shall be demonstrated OPERABLE at least once per 18 months by:
- 1. Verifying that each automatic valve in the flow path actuates to its correct position upon receipt of each auxiliary feedwater actuation test signal.
- 2. Verifying that each auxiliary feedwater pump starts as designed automatically upon receipt of each auxiliary feedwater actuation test signal. -Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering MODE 3, the steam driven auxiliary feedwater pump shall be similarly tested.
D. When the reactor coolant system pressure remains less than 500 psig for a period longer than thirty (30) days, a flow test shall be performed to verify the emergency flow path from the auxiliary feedwater storage tank to each steam generator, using the motor driven auxiliary feedwater pump prior to increasing reactor coolant system pressure above 500 psig. The flow test-shall be.
conducted with the auxiliary feedwater system valves in their emergency alignment. Within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after entering MODE 3, the steam driven auxiliary feedwater pump shall be similarly tested.
Basis:
The OPERABILITY of the auxiliary feedwater system ensures that the Reactor Coolant System can be cooled down to less than 350oF from normal operating conditions in the event of a total loss of offsite power.
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