|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20071G2111994-06-28028 June 1994 Sys 80+ Emergency Operations Guidelines, Replacement Pp ML20065M2971994-05-31031 May 1994 Draft Advanced Reactor Research & Development Programs 5-Yr Plan for Advanced Reactor Activities Under Energy Policy Act of 1992 ML20065P8031994-04-0909 April 1994 Proposed Tech Specs Technical Revs Agreed Upon in 940405-06 Meeting ML20067D3441994-02-10010 February 1994 Rev 2 to NPX80-SQP-0101.0, Software Program Manualfor Nuplex 80+ ML20058C3061993-11-10010 November 1993 Rev 1 to NPX80-SQP-0101.0, Software Program Manual for Nuplex 80+ ML20058C3251993-11-10010 November 1993 Draft Rev to Sys 80+ Emergency Operations Guidelines, Functional Recovery Guideline ML20059J9111993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, Loss of All Feedwater Recovery ML20059J9411993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, SBO Recovery Guideline ML20059J9331993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, Excess Steam Demand Event Recovery ML20059J9191993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, Loss of Offsite Power Recovery Guideline ML20059H5931993-11-0303 November 1993 SG Tube Rupture Recovery Guideline ML20059H5821993-11-0303 November 1993 Diagnostic Actions ML20059H5531993-11-0303 November 1993 Reactor Trip Recovery Guideline ML20059H5221993-11-0303 November 1993 Standard Post Trip Actions Recovery Guideline ML20059H5991993-11-0303 November 1993 LOCA Recovery Guideline ML20059B0401993-10-11011 October 1993 Proposed Tech Specs Identifying Differences from STS (NUREG-1432) & Basis for Differences ML20058N0941993-09-30030 September 1993 Plant Designers Operational Support Info Plan for ABB-CE Sys 80+ (Tm) ML20058N0851993-09-29029 September 1993 Rev 2 to NPX80-IC-DP790-01, Human Factors Program Plan for Sys 80+ (Tm) Std Plant Design ML20056D8151993-08-11011 August 1993 Proposed STS 3.1.7, Standby Liquid Control Sys ML20127M4251993-01-31031 January 1993 Plant Designer Operational Support Info Plan for ABB-C-E Sys 80+ ML20126F0801992-12-31031 December 1992 Rev 1 to Design Reliability Assuance Program Plan for Sys 80+ Standard Design ML20113J1081992-07-31031 July 1992 Sys 80+ Probabilistic Risk Assessment Program Plan ML20096G0661992-05-14014 May 1992 Rev 0 to Sys 80+ Reactor Coolant Pump Seal Loss of Seal Cooling,Test Data Rept ML20090D5981992-02-29029 February 1992 Description of Human Factors Program Plan for Sys 80+ (Tm) Standard Plant Design, for Plant Certification ML20092B8841992-01-31031 January 1992 Draft Rev 0 to Reliability Assurance Program Plan for Sys 80+ Nuclear Power Plant 1994-06-28
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20071G2111994-06-28028 June 1994 Sys 80+ Emergency Operations Guidelines, Replacement Pp ML20065M2971994-05-31031 May 1994 Draft Advanced Reactor Research & Development Programs 5-Yr Plan for Advanced Reactor Activities Under Energy Policy Act of 1992 ML20067D3441994-02-10010 February 1994 Rev 2 to NPX80-SQP-0101.0, Software Program Manualfor Nuplex 80+ ML20058C3061993-11-10010 November 1993 Rev 1 to NPX80-SQP-0101.0, Software Program Manual for Nuplex 80+ ML20058C3251993-11-10010 November 1993 Draft Rev to Sys 80+ Emergency Operations Guidelines, Functional Recovery Guideline ML20059J9411993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, SBO Recovery Guideline ML20059J9111993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, Loss of All Feedwater Recovery ML20059J9191993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, Loss of Offsite Power Recovery Guideline ML20059J9331993-11-0505 November 1993 Draft Sys 80+ Emergency Operations Guideline, Excess Steam Demand Event Recovery ML20059H5821993-11-0303 November 1993 Diagnostic Actions ML20059H5531993-11-0303 November 1993 Reactor Trip Recovery Guideline ML20059H5221993-11-0303 November 1993 Standard Post Trip Actions Recovery Guideline ML20059H5931993-11-0303 November 1993 SG Tube Rupture Recovery Guideline ML20059H5991993-11-0303 November 1993 LOCA Recovery Guideline ML20058N0941993-09-30030 September 1993 Plant Designers Operational Support Info Plan for ABB-CE Sys 80+ (Tm) ML20058N0851993-09-29029 September 1993 Rev 2 to NPX80-IC-DP790-01, Human Factors Program Plan for Sys 80+ (Tm) Std Plant Design ML20127M4251993-01-31031 January 1993 Plant Designer Operational Support Info Plan for ABB-C-E Sys 80+ ML20126F0801992-12-31031 December 1992 Rev 1 to Design Reliability Assuance Program Plan for Sys 80+ Standard Design ML20113J1081992-07-31031 July 1992 Sys 80+ Probabilistic Risk Assessment Program Plan ML20090D5981992-02-29029 February 1992 Description of Human Factors Program Plan for Sys 80+ (Tm) Standard Plant Design, for Plant Certification ML20092B8841992-01-31031 January 1992 Draft Rev 0 to Reliability Assurance Program Plan for Sys 80+ Nuclear Power Plant 1994-06-28
[Table view] |
Text
_ - _ _ - _ _ - _ _ _ _
s SYSTEM 80 + '" TITLE APPENDlX B LOWER MODE OPERATIONAL
O EMERGENCY OPERATIONS GUIDELINES Page 8 of " Revision 5.3.3 Isolation (closure of a containment isolation valve) in the non-operating SCS loop can reduce the possibility of an inadvertent draindown to the RCS.
5.3.4 Operations directly affecting the reactor vessel pressure boundary, i.e. In-core Instrumentation Seal Table evolutions, shall be prohibited during mid-loop operations.
5.3.5 Operational procedures are established to rapidly close specified containment -
penetrations. Personnel trained in these procedures are available to execute the procedures as required by the plant operating mode.
5.3.6 Disassembly and removal of the reactor vessel head should be avoided when mid-loop operation is planned and these t.volutions affect the operability of the high resolution level instrumentation utilized for determining RCS water level in the hot leg region.
5.4.0 OPERATIONAL GUIDANCE 5.4.1 Verify RCS vent path established per Technical Specification (3.10.3).
5.4.2 Verify that the shutdown cooling / containment spray cross connection isolation valves are administratively closed.
5.4.3 Perform the RCS drain procedure to lower RCS level to the desired reduced inventory elevation identified below:
Scheduled Maintenance Activity RCS Elevation S/G cold leg nozzle dams [ ]
S/G hot leg nozzle dams [ ]
RCP seal housing removal DVI nozzle 2A or 2B valve [ ]
maintenance O
i APPENDIX B B-8 ABB CE SYSTEM 80+*
06/17/94
$$8"5S$8[: $$0 f a - - _-