ML20069M823
ML20069M823 | |
Person / Time | |
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Site: | Oyster Creek |
Issue date: | 06/15/1994 |
From: | GENERAL PUBLIC UTILITIES CORP. |
To: | |
Shared Package | |
ML20069M785 | List: |
References | |
NUDOCS 9406220152 | |
Download: ML20069M823 (1) | |
Similar Documents at Oyster Creek | |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20209H5051999-07-14014 July 1999
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of Once Per Three Months ML20195C6561998-11-10010 November 1998 Proposed Tech Specs Section 5.1.A,removing Restriction on Sale or Lease of Property within Exclusion Area ML20155J7501998-11-0505 November 1998 Proposed Tech Specs,Modifying Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & to Verify Channel Operability ML20151V5091998-09-0303 September 1998 Proposed Tech Specs 3.4.A.10.e & 3.5.A.2.e Re Condensate Storage Tank Level ML20237D9591998-08-21021 August 1998 Proposed Tech Specs Removing Requirement for ADS Function of EMRV to Be Operable During Rv Pressure Testing & Correcting Note H of Table 3.1.1 ML20237B2221998-08-0606 August 1998 Proposed Revised Tech Specs Pages for Change Request 205,dtd 961031,correcting Minor & Inadvertent Editorial Changes in Locations Where Changes Have Not Been Proposed ML20236T1211998-07-23023 July 1998 Proposed Tech Specs Pages for Amend to License DPR-16,to Establish 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Reporting Instructions for Operations Personnel ML20072L4741994-08-19019 August 1994 Proposed Tech Specs Control Rod Exercising & Standby Liquid Control Pump Operability Testing ML20070J7971994-07-31031 July 1994 Rev 8 to Oyster Creek Nuclear Generating Station Pump & Valve Inservice Testing Program ML20070E3411994-07-0808 July 1994 Proposed Tech Specs Re Improved Protection to Safety Related Electrical Equipment from Loss of Capability 1999-09-05 |
Text
'
l FUNCTION
. - LIMITING SAFETY SYSTEM SETTINGS B. Neutron Flux, The Rod Block setting shall be Control Rod Block FRP !
S s [(0.90 x 10) W + 53.1] [MFLPD]
with a maximum setpoint of 108% for core flow equal to 61 x 106 lb/hr and j greater.
The definitions of S, W, FRP and MFLPD used above for the APRM scram trip apply.
The ratio of FRP to MFLPD shall be set equal to 1.0 unless the actual operating value is less than 1.0, in which case the actual operating value will be used.
This adjustment may be accomplished by increasing the APRM gain and thus reducing the flow referenced APRM rod block curve by the reciprocal of the APRM gain change.
C. Reactor High, 11060 psig l
Pressure, Scram D. Reactor High Pressure. 2 @ s 1085 psig Relief Valves Initiation 3 @ s 1105 psig E. Reactor High Pressure, 11060 psig with time delay Isolation Condenser 53 seconds initiation F. Reactor High Pressure, 4 @ 1212 psig 12 psi Safety Valve Initiation 5 @ 1221 psig 12 psi G. Low Pressure Main Steam MSly Closure 2825 psig (initiated in IRM Line, range 10)
H. Main Steam Line Isolation $10% Valve Closure from Valve Closure, Scram full open I. Reactor Low Water Level, 211'5" above the top of the Scram active fuel as indicated under normal operating conditions J. Reactor Low-Low Water 27'2" above the top of the Level, Main Steam Line active fuel as indicated under Isolation Valve Closure normal operating conditions OYSTER CREEK 2.3-2 Amendment No. 164, 9406220152 940615 PDR P
ADOCK 05000219 PDR