Letter Sequence Other |
|---|
|
|
MONTHYEARML20128P4251985-07-22022 July 1985
Application for Amends to Licenses NPF-35,NPF-9 & NPF-17, Authorizing Relaxation of Reactor Trip Sys Allowable Outage Times Based on Analysis Performed by Westinghouse Owners Group & Approved by Nrc.Fee Paid
Project stage: Request
ML20128P4491985-07-22022 July 1985
Proposed Tech Specs Relaxing Reactor Trip Sys Requirements
Project stage: Other
ML20134L6661985-08-30030 August 1985
Proposed Tech Specs,Deleting Turbine Valve Testing Requirements in Section 3.3.4 to Eliminate Need for Routine Turbine Valve Testing
Project stage: Other
ML20134L6521985-08-30030 August 1985
Application for Amends to Licenses NPF-9 & NPF-17,deleting Tech Spec 3.3.4 Re Turbine Valve Testing Requirements,Per 10CFR50.92.Significant Hazards Consideration Encl.Fee Paid
Project stage: Request
ML20133H5461985-10-15015 October 1985
Forwards Request for Addl Info Regarding Turbine Overspeed Protection to Complete Review of Util Re Proposed Tech Spec Changes.Response Requested within 60 Days of Ltr Date
Project stage: RAI
ML20138P4061985-12-13013 December 1985
Responds to 851015 Request for Addl Info Re 850830 Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Spec Re Turbine Overspeed Protection
Project stage: Request
ML20137K8411986-01-10010 January 1986
Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs Re Number of Operating Reactor Coolant Pumps When in Hot Standby & Ensuring That in Event of Limiting Accident at Zero Power,Design Basis Will Be Met.Fee Paid
Project stage: Request
ML20137K8541986-01-10010 January 1986
Proposed Tech Specs Re Number of Operating Reactor Coolant Pumps When in Hot Standby & Ensuring That in Event of Limiting Accident at Zero Power,Design Basis Will Be Met
Project stage: Other
ML20205P8401986-05-12012 May 1986
Supplemental Application for Amends to Licenses NPF-9 & NPF-17,changing Tech Specs to Increase Number of Operating Reactor Pumps Required in Mode 3 to at Least Two
Project stage: Supplement
ML20205P8541986-05-12012 May 1986
Proposed Tech Specs Increasing Number of Operating Reactor Pumps Required in Mode 3 to at Least Two
Project stage: Other
ML20199E1471986-06-12012 June 1986
Rescinds 850722 Proposed Deletion of Action Statement 11 Re Turbine Trip/Turbine Stop Valve Closure of McGuire Tech Spec Table 3.3-1.Time Allowed for Action Statement Should Be Changed from 1 to 6 H.Catawba Tech Specs Affected
Project stage: Other
ML20210G1481986-09-17017 September 1986
Amends 62 & 43 to Licenses NPF-9 & NPF-17,respectively, Changing Tech Specs Re Turbine Overspeed Trip Protection, Min Reactor Coolant Loops Required for Hot Standby & Turbine Trip/Reactor Trip Sys Outage Times
Project stage: Other
1985-08-30
[Table View] |
Text
-
l,, :
4 NOT STAND 8Y LIMITING CONDITION FOR OPERATION At least three of the reactor coolant 1 caps listed below shall be g7 OPERABLE and at least two of these reactor coolant loops shall be 4nA 3.4.1.2 operation:*
Reactor Coolant Loop A and its associated steam generator and a.
reactor coolant pump, Reactor Coolant Loop 8 and its associated steam generator and b.
reactor coolant pump, Reactor Coolant Loop C and its associated steam generator and c.
reactor coolant pump, and Reactor Coolant Loop D and its associated steam generator and d.
reactor coolant pump.
APPLICABILITY: MODE 3 ACTION:
With less than the above required reactor coolan a.
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 />.
/'
With only one reactor coolant loop in operation, restore at least /7 two loops to operation within 72' hours or open the Reactor Trip b.
j
(,,e System breakers.
With no reactor coolant loop in operation, suspe c.
System and immediately initiate corrective action to return the required reactor coolant loop to operation.
I SURVEILLANCE REQUIREMENTS At least the above required reactor coolant pumps, if not in operation, shall be determined OPERABLE once per 7 days by ve 4.4.1.2.1 breaker alignments and indicated power availability.
The required steam generators shall be determiaed OPERABLE by 12% at verifying secondary side water level to be greater than er equal to 4.4.1.2.2 least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
No l
At leastgreactor coolant loop shall be verified in operation 4.4.1.2.3 and circulating reactor coolant at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
"All reactor coolant pumps may be de-energized Coolant System boron concentration, and (2) core outlet temperature maintained at least 10*F below saturation temperature.
Amendment No.
(Unit 1) 3/4 4-2 McGUIRE - UNITS 1 and 2 Amendment No.
(Unit 2) 220123 860512 ADOCK 05000369 p
PDR
.
