ML062610196

Technical Specification Pages Re Increase Safety Valve As-Found Setpoint Tolerance from 1 Percent to 3 Percent

ML062610196
Person / Time
Site:	Oyster Creek
Issue date:	09/13/2006
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
References
TAC MC9149
Download: ML062610196 (16)

Text

FUNCTION LIMITING SAFETY SYSTEM SETTINGS B. Neutron Flux, Control Rod The Rod Block setting shall be the minimum of:

Block For W _>0.0 x 106 lb / hr:

FRP S <_[(0.90 x 10") W + 60.1] MFLPD  ; or The applicable stability protection settings, as defined in the COLR, with a maximum setpoint of 115.0% for core flow equal to 61 x 106 lb/hr and 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 Pressure, <1060 psig Scram D. Reactor High Pressure, 2 @ < 1085 psig Relief Valves Initiation 3 @ < 1105 psig E. Reactor High Pressure, < 1060 psig with time delay Isolation Condenser < 3 seconds Initiation F. Reactor High Pressure, Safety Valve Initiation 4 @ 1212 psig 5 @ 1221 psig

_+/-36 psi

+/-36 psi I G. Low Pressure Main Steam > 825 psig (initiated in IRM Line, range 10)

MSIV Closure H. Main Steam Line Isolation :510% Valve Closure from full open Valve Closure, Scram OYSTER CREEK 2.3-2 Amendment No. 71,7-5,1114,0,14, 1 77, 208, 235, 2A-8, 261

4.3 REACTOR COOLANT Applicability: Applies to the surveillance requirements for the reactor coolant system.

Obiective: To determine the condition of the reactor coolant system and the operation of the safety devices related to it.

Specification: A. Materials surveillance specimens and neutron flux monitors shall be installed in the reactor vessel adjacent to the wall at the midplane of the active core.

Specimens and monitors shall be periodically removed, tested, and evaluated to determine the effects of neutron fluence on the fracture toughness of the vessel shell materials. The results of these evaluations shall be used to assess the adequacy of the P-T curves A, B, and C in Figures 3.3.1, 3.3.2 and 3.3.3. New curves shall be generated as required.

B. Inservice inspection of ASME Code Class 1, Class 2 and Class 3 systems and components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR, Section 50.55a(g)(6)(i).

C. Inservice testing of ASME Code Class 1, Class 2 and Class 3 pumps and valves shall be performed in accordance with Section Xl of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(f), except where specific written relief has been granted by the NRC pursuant to 10 CFR, Section 50.55a(f)(6)(i).

D. A visual examination for leaks shall be made with the reactor coolant system at pressure during each scheduled refueling outage or after major repairs have been made to the reactor coolant system in accordance with Article 5000, Section Xl. The requirements of specification 3.3.A shall be met during the test.

E. Each replacement safety valve or valve that has been repaired shall be tested in accordance with Specification C above. Setpoints shall be as follows:

I Number of Valves Set Points (psiq) 4 1212 t 36 5 1221 +/- 36 F. A sample of reactor coolant shall be analyzed at least every 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for the purpose of determining the content of chloride ion and to check the conductivity.

OYSTER CREEK 4.3-1 Amendment No.: 82, 00,1420, 160, 4154,6 ,88, 4,10 261