Letter Sequence Other |
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Results
Other: AECM-86-0160, Forwards Final Proposed Tech Specs for Core Stability Single Loop Operation & Max Extended Operating Domain, AECM-86-0218, Forwards Addl Info Supporting 860502 Proposed Amend to License NPF-29 for Max Extended Operating Domain.Info Includes Mar 1986, Grand Gulf Nuclear Station Feedwater Heaters Out-of-Svc Analysis,Grand Gulf Units 1 & 2, ML20155B085, ML20155B091, ML20197B884, ML20205H657, ML20206J534, ML20207G699, ML20214K627
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MONTHYEARML20155B0911986-02-28028 February 1986 Single Loop Operating Analysis Project stage: Other ML20155B0851986-03-31031 March 1986 Proposed Tech Specs Increasing Neutron Flux Noise Surveillance & Permitting Operation W/One Recirculation Loop Out of Svc Project stage: Other ML20207G6991986-03-31031 March 1986 Feedwater Heaters Out-of-Svc Analysis,Grand Gulf Units 1 & 2 Project stage: Other AECM-86-0092, Application for Amend to License NPF-29,changing Tech Specs to Increase Neutron Flux Noise Surveillance Per Rev 1 to GE Svc Info Ltr 380 & to Permit Operation W/One Recirculation Loop Out of Svc.Fee Paid1986-03-31031 March 1986 Application for Amend to License NPF-29,changing Tech Specs to Increase Neutron Flux Noise Surveillance Per Rev 1 to GE Svc Info Ltr 380 & to Permit Operation W/One Recirculation Loop Out of Svc.Fee Paid Project stage: Request ML20197B8841986-05-0202 May 1986 Proposed Tech Spec Changes Re Max Extended Operating Domain Project stage: Other AECM-86-0129, Application for Amend to License NPF-29,changing Tech Specs Re Max Extended Operating Domain.Amend Required to Support Cycle 1 Operations & Cycle 2 Reload Licensing Effort.Fee Paid1986-05-0202 May 1986 Application for Amend to License NPF-29,changing Tech Specs Re Max Extended Operating Domain.Amend Required to Support Cycle 1 Operations & Cycle 2 Reload Licensing Effort.Fee Paid Project stage: Request AECM-86-0160, Forwards Final Proposed Tech Specs for Core Stability Single Loop Operation & Max Extended Operating Domain1986-06-0202 June 1986 Forwards Final Proposed Tech Specs for Core Stability Single Loop Operation & Max Extended Operating Domain Project stage: Other AECM-86-0159, Application for Amend to License NPF-29,changing Tech Specs to Resolve NRC Concerns Re Core Stability & to Support Single Loop Operations1986-06-20020 June 1986 Application for Amend to License NPF-29,changing Tech Specs to Resolve NRC Concerns Re Core Stability & to Support Single Loop Operations Project stage: Request ML20206J5341986-06-20020 June 1986 Marked-up Proposed Tech Specs Resolving NRC Concerns Re Core Stability & Supporting Single Loop Operations Project stage: Other AECM-86-0218, Forwards Addl Info Supporting 860502 Proposed Amend to License NPF-29 for Max Extended Operating Domain.Info Includes Mar 1986, Grand Gulf Nuclear Station Feedwater Heaters Out-of-Svc Analysis,Grand Gulf Units 1 & 21986-07-11011 July 1986 Forwards Addl Info Supporting 860502 Proposed Amend to License NPF-29 for Max Extended Operating Domain.Info Includes Mar 1986, Grand Gulf Nuclear Station Feedwater Heaters Out-of-Svc Analysis,Grand Gulf Units 1 & 2 Project stage: Other AECM-86-0253, Errata to 860502 Application for Amend to License NPF-29, Changing Tech Specs Re Control Rod Block Instrumentation Setpoint & Allowable Value Associated W/Reactor Coolant Recirculation Flow1986-08-14014 August 1986 Errata to 860502 Application for Amend to License NPF-29, Changing Tech Specs Re Control Rod Block Instrumentation Setpoint & Allowable Value Associated W/Reactor Coolant Recirculation Flow Project stage: Request ML20205H6571986-08-14014 August 1986 Proposed Tech Specs,Changing Control Rod Block Instrumentation Setpoint & Allowable Value Associated W/ Reactor Coolant Recirculation Flow Project stage: Other ML20214K6271986-08-15015 August 1986 Amend 16 to License NPF-29,allowing Operation W/One Recirculation Loop Operable & W/Increased Reactor Core Cooling Water Flow Rates Up to 105% of Rated Flow Rate at Reduced Power Levels Project stage: Other ML20214K6341986-08-15015 August 1986 Safety Evaluation Supporting Amend 16 to License NPF-29 Project stage: Approval 1986-06-02
[Table View] |
Text
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TABLE 3.3.6-2 h
CONTROL ROD BLOCK INSTRUMENTATION SETPOINTS 5
TRIP FUNCTION TRIP SETPOINT ALLOWABLE VALUE g
G; 1.
R0D PATTERN CONTROL SYSTEM E
a.
Low Power Setpoint 20 + 15, -0% of RATED THERMAL 20 + 15, -0% of RATED THERMAL POWER POWER b.
High Power Setpoint 1 70% of RATED THERMAL POWER 1 70% of RATED THERMAL POWER g
2.
APRM Rc? tact wit 4 lHstnr (or Taste 3.3.(o-2 a.
Flow Biased Neutron Flux-
\\
ga;ga.,}
~
l Upscale (0.00 "
42%)T*
< (0.55 W ^ '5%)T*
% 3i, neu i
b.
Inoperative RA RA g.,og c.
Downscale 1 4% of RATED THERMAL POWER 1 3% of RATED THERMAL POWER g w,g 1
Startup i 12% of RATED THERMAL POWER 1 14% of RATED THERMAL POWER ah3 g;3 i
d.
Neutron Flux - Upscale 3.
SOURCE RANGE MONITORS w
A Detector not full in NA NA 5
a.
5
< 1.5 x 10 cps Y
b.
Upscale
< 1 x 10 cps tg c.
Inoperative RA RA d.
Downscale 1 0.7 cps 1 0.5 cps f
4.
INTERMEDIATE RANGE MONITORS l
a.
Detector not full in NA NA b.
Upscale
< 108/125 of full scale
< 110/125 of full scale c.
Inoperative NA RA d.
Downscale 1 5/125 of full scale 1 3/125 of full scale I
5.
SCRAM DISCHARGE VOLUME a.
Water Level-High 1 32 inches 1 33.5 inches y
l p w
l 5
6.
REACTOR COOLANT SYSTEM RECIRCULATION FLOW a.
Upscale i g of rated flow 1 g of rated flow III N IIN N 7.
REACTOR MODE SWITCH SHUTDOWN l
-1 POSITION NA NA z
?
- The Average Power Range rionii... r;d bl~-k function isgd_u e 4netie,, vimetrculation loop flow (W) and the ratio of FRACTI ILaf RATED-THERMAt ruwtn i.o th "avfMuM FRACTION of LIMITING POWER DENSIT
_(Liactee.
r p setting of this function must be maintained in accordance with-Specif.ication 3.2.2.
8608200129 860814 PDR ADOCK 05000416 PDR p