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MONTHYEARML20096C6631984-08-27027 August 1984
Application for Amend to License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys.Fee Paid
Project stage: Request
ML20096C6821984-08-27027 August 1984
Proposed Tech Specs Reflecting Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys
Project stage: Other
ML20096C6401984-08-27027 August 1984
Forwards Application to Amend License NPF-3,revising Tech Specs to Reflect Changes in Reactor Vessel Matls Irradiation Surveillance Schedule & Flow Verification of Auxiliary Feedwater Sys
Project stage: Request
ML20101N4281984-12-11011 December 1984
Amend 79 to License NPF-3,changing Tech Spec Table 3.6-2 Re Containment Isolation Valve to Allow for Modified Steam Generator Blowdown & Drain Sys
Project stage: Other
ML20101N4481984-12-11011 December 1984
Safety Evaluation Supporting Amend 79 to License NPF-3
Project stage: Approval
ML20215L8391987-05-0404 May 1987
Proposed Tech Specs Re Auxiliary Feedwater Sys Surveillance Requirement 4.7.1.2d
Project stage: Other
ML20215K3801987-05-0404 May 1987
Requests Reissuance of Table 3.6-2, Containment Isolation Valves of Tech Spec 3/4.6.3,correcting Typos in 840911 Application to Amend License NPF-3
Project stage: Request
ML20215L8351987-05-0404 May 1987
Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d Re Auxiliary Feedwater Sys as Result of 850609 Loss of Feedwater Event. Supporting Documentation Encl
Project stage: Request
ML20215L8141987-05-0404 May 1987
Forwards Application for Amend to License NPF-3,deleting Portion of Tech Spec Surveillance Requirement 4.7.1.2d to Reflect Mods to Steam Line Piping to Auxiliary Feed Pump Turbine Following 850609 Loss of Feedwater Event.Fee Paid
Project stage: Request
ML20216H6041987-06-25025 June 1987
Advises That Based on B&W Analytical Studies for Primary Sys Blowdown Using RELAP5,use of Blowdown Valves Not Practicable for Feed & Bleed,Per 851204 Commitment.Listed Proposed Mods Will Be Implemented to Enhance Makeup Sys
Project stage: Other
ML20236G9801987-10-27027 October 1987
Application for Amend to License NPF-3,revising Tech Spec Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods.Fee Paid
Project stage: Request
ML20236H0211987-10-27027 October 1987
Proposed Tech Specs,Changing Section 3/4.3.2, Safety Sys Instrumentation, Table 3.3-5 & Section 3/4.6.3, Containment Isolation Valves, Table 3.6-2 to Support Enhanced Feed & Bleed Mods
Project stage: Other
ML20237A6881987-12-0808 December 1987
Informs of Changes Necessary to Support Fifth Refueling Outage in Feb 1988.Key Amend Requests Placed Into 1 of 3 Listed Categories.Nrc Should Allocate Necessary Resources to Provide Timely Support for Review & Issuance of Amends
Project stage: Other
ML20236Y3421987-12-0808 December 1987
Forwards Application for Amend to License NPF-3,revising Tech Spec 4.6.1.2c.3,Section 3/4.6.1.2 Re Containment Sys & Containment Leakage.Fee Paid
Project stage: Request
ML20150B0321988-03-0707 March 1988
Forwards Application for Amend to License NPF-3 Changing Tech Spec Section 4.6.1.2.a to Allow Third Type a Test & 10-yr Inservice Insps to Be Uncoupled & Performed in Separate Refueling Outages.Fee Paid
Project stage: Request
ML20148B1781988-03-14014 March 1988
Amend 110 to License NPF-3,revising Tech Specs to Permit Extension of Range of RCS Pressure Instrument on Auxiliary Shutdown Panel to 3,000 Psig from 2,500 Psig & Tech Spec 3.3.3.5,Table 3.3-9,Item 3
Project stage: Other
ML20151X2411988-04-29029 April 1988
Forwards Discussion of & Proposed Revs to Tech Specs for Resolution of NRC Comments Concerning Deletion of Auxiliary Feedwater Pump Turbine Inlet Steam Pressure Interlock Operability Requirements,Per 880406 Telcon
Project stage: Other
1987-05-04
[Table View] |
Text
r THIS PAGE PROVIDED l
81'0 T0 0 ""
PLANT SYSTEMS l
AUXILIARY FEEDWATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.1.2 Two independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE.
APPLICABILITY: MODES 1,-2 and 3*.
ACTION:
With one Auxiliary Feedwater System inoperable, restore the a.
inoperable system 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 HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.2 Each Auxiliary Feedwater System shall be demonstrated OPERABLE:
At least once per 31 days on a STAGGERED TEST BASIS by:
a.
1.
Verifying that each steam turbine driven pump develops a differential pressure of > 1070 psid on recirculation flow when the secondary steam supply pressure is greater than 800 psia, as measured on PI SP 12B for pump 1-1 and PI SP 12A for pump 1-2.
2.
Verifying that each valve (power operated or automatic) in the flow path is in its correct position.
3.
Verifying that all manual valves in the auxiliary feedwater pump suction and discharge lines that affect the system's capacity to deliver water to the steam generator are locked in their proper position.
b.
At least once per 18 months by:
1.
Verifying that each automatic valve in the flow path actuates to its correct position on an auxiliary feedwater actuation test signal prior to entering MODE 3.
Verifying that each pump starts automatically upon receipt of an auxiliary feedwater actuation test signal prior to entering MODE 2.
3.
Verifying that there is a flow path between each auxiliary feedwater pump and each steam generator by pumping water from the Condensate Storage Tank to the steam generator.
- Provision of section 3.0.4 is not applicable for entry into MODE 3.
DAVIS-BESSE, UNIT 1 3/4 7-4 Amendment No. 96 8705120395 B70504 PDR ADOCK 05000346 p
PDR
THIS PAllE PROVIDED FORINFORETION DE PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) f.
Following each extended cold shutdown (> 30 days in MODE 5), by:
1.
Verifying that there is a flow path between each auxiliary feedwater pump and each steam generator by pumping Conden-sate Storage Tank water to the steam generator. The flow path to the steam generator shall be verified by either steam generator level change or Auxiliary Feedwater Safety Grade Flow Indication.
Verification of the Auxiliary Feedwater System's flow capacity is not_ required.
DAVIS-BESSE, UNIT 1 3/4 7-Sa Amendment No. 96 L
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