Letter Sequence Other |
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Results
Other: ML20079P706, ML20087Q011, ML20090G560, ML20090G568, ML20091E083, ML20092A243, ML20092P177, ML20092P588, ML20093C995, ML20095L022, ML20140C660, ML20197H659
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MONTHYEARML20079P7061983-08-19019 August 1983 Proposed Plant Mods to Be Incorporated Into Analog Transmitter Trip Scram Design. GE Affidavit for Withholding Nede 22154-1, Analog Trip Sys for Engineered Safeguard Sensor Trip Inputs, Encl Project stage: Other ML20079P6921984-01-23023 January 1984 Application to Amend License NPF-5,supporting Mods Associated W/Installation of GE Analog Transmitter Trip Sys. Encl Proprietary Rev 1 to NEDE-22154-1, Analog Trip Sys for Engineered Safeguards Sensor Trip Inputs... Withheld Project stage: Request ML20080P3521984-02-0606 February 1984 Application for Amend to Licenses DPR-57 & NPF-5,consisting of Tech Spec Changes Re Aprm,Rod Block Monitor & Tech Spec Improvements Program.Affidavit Encl.Tech Spec Withheld (Ref 10CFR2.790) Project stage: Request ML20087P9511984-04-0303 April 1984 Forwards Hardware Descriptions & Drawings Submitted in Support of Review of 840206 Application for Amends to Licenses DPR-57 & NPF-5 Re Aprm.Revised Pages 1-4 Encl.W/O Drawings Project stage: Request ML20087Q0111984-04-0303 April 1984 Proposed Tech Specs Adding New Fuel Type MAPLHGR Curve & Changing Min Critical Power Ratio Curves for 8x8R & P8x8R Fuel to Support Reload 4 Core Design & Allowing Hybrid I Control Rod Assembly Operation Project stage: Other ML20087Q0071984-04-0303 April 1984 Application for Amend to License NPF-5,revising Tech Specs to Add New Fuel Type MAPLHGR Curve & Change Min Critical Power Ratio Curves for 8x8R & P8x8R Fuel to Support Reload 4 Core Design & Allow Hybrid I Control Rod Operation Project stage: Request ML20088A0041984-04-0303 April 1984 Application for Amend to License NPF-5,revising 840123 Request for Tech Spec Changes to Support Analog Transmitter Trip Sys Installation.Methodology for Significant Hazards Reviews Changed.Revised Review Encl Project stage: Request ML20091E0831984-05-10010 May 1984 Notice of Consideration of Issuance of Amends to Licenses DPR-57 & NPF-5 & for Prior Hearing Re Average Power Range Monitor Improvement Program.Nshc Available in Central Files Project stage: Other ML20092P1771984-06-0707 June 1984 Forwards Proprietary & Nonproprietary Responses to NRC 840517 Questions Re Analog Transmitter Trip Sys Tech Spec Package Submitted on 840123.Proprietary Responses Withheld. GE Affidavit Encl Project stage: Other ML20091N2871984-06-0707 June 1984 Responds to NRC 840423 Request for Info Re Safety Parameter Display Sys Per Suppl 1 to NUREG-0737.Safety Features,Data Validation,Human Factors & Method of Electrical Isolation Discussed.Description of Foxboro Optical Isolators Encl Project stage: Request ML20140C6601984-06-14014 June 1984 Forwards Revised Response to Question 1-2,incorporating Addl Info Requested by NRC & Corrected Response to Question 1-3 Re Proposed Analog Transmitter Trip Sys Tech Spec Changes, Per 840613 Telcon Project stage: Other ML20197H6591984-06-15015 June 1984 Submits Addl Info Re Proposed Tech Spec Changes,Per NRC Request.Hardware Associated W/Atts & non-ATTS Sys Discussed Project stage: Other ML20092A2431984-06-15015 June 1984 Responds to Generic Ltr 84-11 Re Insp of BWR Stainless Steel Piping.Current Plans for IGSCC & Leakage Detection Insp Encl Project stage: Other ML20092P5881984-06-27027 June 1984 Withdraws Request That Certain Tech Spec Pages Submitted on 840206 Be Treated as Proprietary.Supporting Data Base & Analysis Results Included W/Submittal Should Remain Proprietary Project stage: Other ML20093C9951984-07-0909 July 1984 Notice of Environ Assessment & Final Finding of No Significant Impact Re Proposed Amend to License NPF-5 Project stage: Other ML20090G5681984-07-13013 July 1984 Notice of Issuance & Availability of Amend 39 to License NPF-5 Project stage: Other ML20090G5641984-07-13013 July 1984 Safety Evaluation Supporting Amend 39 to License NPF-5 Project stage: Approval ML20090G5601984-07-13013 July 1984 Amend 39 to License NPF-5,amending Tech Specs Re Fuel Type, Operating Limit Min Critical Power Ratio & Allowing Use of Hybrid I Control Rod Assemblies Project stage: Other ML20095L0221984-08-23023 August 1984 Informs That During Startup Following Current Recirculation Pipe Replacement Outage,Util Will Invoke Special Test Exception Tech Spec 3.10.4 Re Operability of Recirculation Loop Project stage: Other ML20134E0821985-08-12012 August 1985 Advises That Ambiguous Statement in 840713 Safety Evaluation Re Amend 39 to License NPF-5,concerning Aprm/Rod Block Monitor Tech Spec Improvement Program,Has No Effect on Conclusions of Evaluation Project stage: Approval 1984-06-15
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~ Coogia Power Company "M,.. 5.
t323 Pedmcnt Ave.nue JAttanta Georg;a 30308 2
Telephone 404 526-6526
- Mailing Address:
Post Office Box 4545
- Atlanta, Georgia 30302 Georgia Power
' : L T. Gucwa.
A1 gust 23,19841 NED-84-399 the southern elecinc system Manager Nucteat Engineenng and Chief Nuc! ear Enginee-Director of M1 clear ReSctor Regulation Attention: 'Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing,_ '
.U. S. M1 clear Regulatory Conmission
~
. Washington, D. C.'
20535 s
- NRC DOCKErr 50-366 OPERATING' LICENSE NPF-5 ENIN I. HA'ICH NUCLEAR PIRff UNIT 2 USE OF SPECIAL TEST TIEHNICAL SPECIFICATIONS Gentlenen:
The following is provided for your information:
During the startup 'of Hatch Unit 2 followirg the c1rrent recira11ation pipe replacement outage, Georgia Power Conpany will invoke Special Test Exception Technical Specification 3.10.4, regarding operability of recirculation loops.
This action is necessary to verify transient reactor coastdown characteristics with the newly installed recirculation system piping.
In acx:ordance with Specification 3.10.4, the test will be performed as a PHYSICS TEST.
A PHYSIG TEST is defined as the nuasurement of fundamental n1 clear characteristics of the reactor core and related instnamentation.
'Ite test will verify transient power, total core flow and recirculation drive flow, heat flux, and water level characteristim cf the reactor using APRM
, (average power range monitor), jet ping, 5s otc.er related instrumentation readings.
Measurements will be obtaire fu a trip of both recira11ation pan, s and albsequent coastdovn.'
-N e.re of the test is to verify, following recirculation system pig sci.s a nt and recira11ation pump modifications, that the recira11ation ping trip time delay and reactor power and flow correspond to the values asalmed in the Hatch Unit 2 reload licensing thermal limit calculations.
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-Qs * :' u j
y (GeorgiaPoiver1 Director of N.1 clear Reactor Regalation Attention:' Mr. John F. Stolz, Chief Operating Reactors _ Branch No. 4
'. Alg.ist _23,.1%4
.page 2
'Ibe. two punp trip test will be performed as described in Chapter 14 of the Hatch Unit 2 ESAR (Startup Test Program).
The recira.11ation punps will be' tripped from conditions of 100 percent core flow and a maxinum power of 75 percent (test condition 3).
Very tn11y yours,
/ C Q_- w L. T. Gicwa REB /DLT xc:
J. T. Beckham, Jr.
H. C. Nix, Jr.
J. P. O'Reilly (NRC-RII)
Senior Resident Inspector, Plant Hatch
.I
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.