Letter Sequence Other |
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Results
Other: ML17299A386, ML17299A407, ML17299A554, ML17299A653, ML17299A713, ML17299A726, ML17299A775, ML17299A819, ML17299B196, ML17303A254, ML17303A292
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MONTHYEARIR 05000528/19840481985-01-31031 January 1985
Insp Repts 50-528/84-48,50-529/84-41 & 50-530/84-31 on 840905-1214.No Violations or Deviations Identified.Major Areas Inspected:Licensee & Ae Activities in Area of as-built Configuration Control for Pipe Supports
Project stage: Request
ML17299A3861985-06-27027 June 1985
Requests Exemption from Tech Spec 3.4.1.2,3.4.1.3 & 3.7.1.6 Requirements for Performing Tests During Power Ascension Testing Program.Justification to Show Exemption Will Not Cause Risk to Public Health & Safety Encl
Project stage: Other
ML17299A4071985-07-0505 July 1985
Proposed Tech Spec one-time Exception,Allowing Performance of Startup Natural Circulation Test Program
Project stage: Other
ML17299A4041985-07-0505 July 1985
Application for Amend to License NPF-41,requesting Tech Spec one-time Exception to Allow for Performance of Startup Natural Circulation Test Program.Fee Paid
Project stage: Request
ML17299A5881985-08-27027 August 1985
Summary of 850627 Meeting W/Util & C-E in Bethesda,Md Re Procedure Used for Natural Circulation Cooldown Test.List of Meeting Attendees Encl
Project stage: Meeting
ML17299A5541985-08-29029 August 1985
Documents Actions to Resolve NRC Concerns Re Natural Circulation Testing Program.Testing Capability to Cool Down Plant from Hot Standby to Cold Shutdown Under Natural Circulation Will Be Demonstrated
Project stage: Other
ML17299A5461985-08-29029 August 1985
Forwards,For Review,Changes to FSAR Sections 1.15 & 1.9. Changes Involve Updated Schedules for Completion & Commercial Operation Dates & Exceptions to Cessar.Changes Will Be Included in Next FSAR Update
Project stage: Request
ML17299A6531985-09-18018 September 1985
Confirms 850917 Conference Call to Discuss 850912 Unscheduled Reactor Shutdown & Impact on Chemical & Vol Control Sys Design & Operation.Util Interim Resolution of NRC Concerns Listed
Project stage: Other
ML17299A6601985-10-0202 October 1985
Forwards Request for Addl Info Re Pressurizer Auxiliary Spray Sys,Based on 850912 Loss of All Three Charging Pumps During loss-of-load Test at Approx 55% Power.Response Requested within 20 Days of Ltr Date
Project stage: RAI
ML17299A6691985-10-15015 October 1985
Responds to Request & Commitments Made During 851008 Meeting & in Re Auxiliary Pressurizer Spray Sys. Implementation of Listed Enhancements Scheduled for First Refueling Outage for Unit 1.Concurrence Requested by 851022
Project stage: Meeting
ML17299A7261985-10-31031 October 1985
Approves Revised Procedure for Boron Mixing & Natural Circulation Cooldown Test Per .Test Date requested.Post-test Rept Re Conformance W/Branch Technical Position Rsb 5-1 Requested Following Test Completion
Project stage: Other
ML17299A7131985-11-0404 November 1985
Forwards Results of Steam Generator Tube Rupture W/Loss of Offsite Power & 851015 Schedule for Implementation of Mods, Per 851029 Telcon Re Auxiliary Pressurizer Spray Sys
Project stage: Other
ML17299A7781985-11-20020 November 1985
Forwards Summary & Anticipated Schedule for Remaining Chapter 14 Power Ascension Testing & Applicability of 851003 Loss of Power Event to Testing Requirements for Loss of Offsite Power,Per 851104 Meeting
Project stage: Meeting
ML17299A8191985-11-25025 November 1985
Forwards Addl Info Requested in 851120 Telcon Re Auxiliary Pressurizer Spray Sys,Including Pressurizer Vent Sys Description & Charging Pump Operation to Permit Issuance of Unit 2 OL
Project stage: Other
ML17299A7751985-11-27027 November 1985
Informs That Commitment Not to Exceed 5% Power in Unit 2 Until Natural Circulation Cooldown Test of Unit 1 Complete Acceptable,Unless Testing Schedule Changed,Per 851125 Request
Project stage: Other
ML17299A9251986-01-0707 January 1986
Summary of 850920 Meeting W/Representatives of Licensee in Bethesda,Md Re 850912 Loss of Load Test at 50% Power.List of Meeting Attendees Encl
Project stage: Meeting
ML17299B0581986-02-13013 February 1986
Summary of 860206 Meeting W/Util & C-E in Bethesda,Md Re Natural Circulation Cooldown Test Procedure.Attendee List & Viewgraphs Encl
Project stage: Meeting
ML17299B1961986-04-17017 April 1986
Advises That Mods to Chemical & Vol Control Sys (CVCS) Ref in Listed Ltrs Completed.Daily Insp of Level Instruments in Unit 2 Discontinued.Daily Insp in Unit 1 Will Be Discontinued Upon Completion of Mod to CVCS
Project stage: Other
ML17303A2541987-01-23023 January 1987
Confirms That Listed Mods to Charging Sys,Remote Shutdown Panel & Valves CHE-PDY-239B & CHE-PDY-240B Control Circuitry Completed,Per Commitments
Project stage: Other
ML17303A2921987-02-0909 February 1987
Forwards Rev 0 to Evaluation of Natural Circulation Cooldown Test Performed at Palo Verde Nuclear Generating Station:Compliance W/Testing Requirements of Branch Technical Position Rsb 5-1
Project stage: Other
ML17303B0701988-04-18018 April 1988
Forwards Safety Evaluation Supporting Util Natural Circulation Cooldown Capability.Test Results Combined W/ Supporting Analysis Demonstrate That Plant Meets Requirements of BTP Rsb 5-1 for Class 2 Plant
Project stage: Approval
1985-07-05
[Table View] |
Text
SPECIAL TEST EXCEPTIONS 3 4.10.9 NATURAL CIRCULATION TESTING PROGRAM LIMITING CONDITION FOR OPERATION 3.10.9 The limitations of Specifications 3.4.1.2, 3.4.1.3, and 3.7.1.6 may be suspended during the performance of the Startup Natural Circulation Testing Program
~
provided:
a.
Operations involving a reduction in boron concentration of the Reactor Coolant System are suspended.
b.
Core outlet temperature is maintained at least 10' below Saturation temperature.
c ~
A reactor coolant pump shall not be started with one or more of Reactor Coolant System cold leg temperatures less than or equal to 255' during cooldown, or 295' during heatup, unless the secondary water temperature (saturation temperature corresponding to steam generator pressure) of each steam generator is less than 100' above each of the Reactor Coolant System cold leg temperatures.
APPLICABILITY:
MODES 3 and 4 during Natural Circulation Testing.
ACTION:
With the Reactor Coolant System saturation margin less than 10',
place at least one reactor coolant loop in operation, with at least one reactor coolant pump.
SURVEILLANCE RE UIREMENTS 4.10.9.1 The saturation margin shall be determined to be within the above limits by continuous monito'ring with the saturation margin monitors required by Table 3.3-10 or, by calculating the saturation margin at least once per 30 minutes.
"Startup Natural Circulation Testing Program:
Loss of Offsite Power Test at 50% power Natural Circulation Cooldown Test at 80% power PALO VERDE Unit 1 8507090ii8 850705 PDR ADOCK 05000528 P,,
PDR'
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