LR-N05-0387, Technical Specification Bases Change H05-11B Re Main Steam Line Low Pressure Isolation Function

Technical Specification Bases Change H05-11B Re Main Steam Line Low Pressure Isolation Function

ML052420464
Person / Time
Site:	Hope Creek
Issue date:	08/18/2005
From:	Benyak D Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
H05-11B, LR-N05-0387
Download: ML052420464 (4)

Text

8PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG AUG 1 8 2005 N\rlclearLLC LR-N05-0387 Bases Change H05-1 1B U.S. Nuclear Regulatory Commission Attn

Document Control Desk Washington, DC 20555-0001 TECHNICAL SPECIFICATION BASES CHANGE H05-11B HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 PSEG Nuclear, LLC (PSEG) has revised the Bases for Technical Specification (TS) 3/4.3.2. This change was reviewed in accordance with the requirements of the Technical Specification Bases Control Program and 10 CFR 50.59.

TS Bases 3/4.3.2 is being changed to correct an error in the description of the main steam line low pressure isolation function.

Attachment 1 contains the revised page for the Hope Creek Technical Specification Bases. Inaccordance with the TS Bases Control Program, PSEG has incorporated these changes into the Bases.

Should you have any questions regarding this transmittal, please contact Mr. Paul Duke at (856) 339-1466.

Sincerely, Darin Benyak Director - Regulatory Assurance Attachment 95-2168 REV. 7/99

Document Control Desk AUG 1 8 2005 LR-N05-0387 C Mr. S. Collins, Administrator- Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Bailey, Project Manager - Hope Creek U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 USNRC Senior Resident Inspector - Hope Creek (X24)

Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, NJ 08625

Attachment I LR-N05-0387 Bases Change H05-11B HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 REVISIONS TO THE TECHNICAL SPECIFICATIONS BASES Page B3/4 3-2h

INSTRUMENTATION BASES 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION APPLICABLE SAFETY ANALYSES, LCO, and APPLICABILITY (continued)

Main Steam Line Isolation 3.a. Reactor Vessel Water Level - Low Low Low, Level 1 Low reactor pressure vessel (RPV) water level indicates that the capability to cool the fuel may be threatened. Should RPV water level decrease too far, fuel damage could result. Therefore, isolation of the MSIVs and other interfaces with the reactor vessel occurs to prevent offsite dose limits from being exceeded. The Reactor Vessel Water Level - Low Low Low, Level 1 Function is one of the many Functions assumed to be OPERABLE and capable of providing isolation signals. The Reactor Vessel Water Level - Low Low Low, Level 1 Function associated with isolation is assumed in the analysis of the recirculation line break (Ref. 1). The isolation of the MSLs on Level 1 supports actions to ensure that offsite dose limits are not exceeded for a DBA.

Reactor vessel water level signals are initiated from four level transmitters that sense the difference between the pressure due to a constant column of water (reference leg) and the pressure due to the actual water level (variable leg) in the vessel. Four channels of Reactor Vessel Water Level - Low Low Low, Level 1 Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

The valve groups actuated by this Function are listed in Table 3.3.2-1.

3.b. Main Steam Line Radiation - High, High The Main Steam Line Radiation - High, High Function is provided to detect gross release of fission products from the fuel and to initiate closure of the reactor recirculation water sample line isolation valves.

Four detectors, one for each main steam line, monitor the gross gamma radiation. Each detector provides an input to one of the four trip logic channels.

3.c. Main Steam Line Pressure - Low Low MSL pressure indicates that there may be a problem with the turbine pressure regulation, which could result in a low reactor vessel water level condition and the RPV cooling down more than 100 0 F/hr if the pressure loss is allowed to continue. The Main Steam Line Pressure - Low Function is directly assumed in the analysis of the pressure regulator failure (Ref. 2). For this event, the closure of the MSIVs ensures that the RPV temperature change limit (100'F/hr) is not reached.

The MSL low pressure signals are initiated from four transmitters that are connected to the MSL header. Four channels of Main Steam Line Pressure -

Low Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

Hope Creek B3/4 3-2h August 15, 2005