View source for LR-N07-0036, LCR S06-03 Supplement Request for Change to Technical Specifications Accident Monitoring Instrumentation and Source Check Definition

{{Adams
| number = ML070600145
| issue date = 02/21/2007
| title = LCR S06-03 Supplement Request for Change to Technical Specifications Accident Monitoring Instrumentation and Source Check Definition
| author name = Joyce T
| author affiliation = PSEG Nuclear, LLC
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR/ADRO
| docket = 05000272, 05000311
| license number = DPR-070, DPR-075
| contact person = 
| case reference number = LR-N07-0036
| document type = Letter type:LR, Technical Specifications
| page count = 6
}}

=Text=
{{#Wiki_filter:PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 10 CFR 50.90 FB2 1 20?                                                                         PSEG Nuclear LLC LR-N07-0036 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SALEM GENERATING STATION - UNIT 1 AND UNIT 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 NRC DOCKET NOS. 50-272 AND 50-311

==Subject:==
LCR S06-03 SUPPLEMENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS ACCIDENT MONITORING INSTRUMENTATION AND SOURCE CHECK DEFINITION

==References:==
(1) Letter from PSEG to NRC: "LCR S06-03, Request for Change to Technical Specifications, Accident Monitoring Instrumentation and Source Check Definition, Salem Nuclear Generating Station, Units 1 and 2, Facility Operating Licenses DPR-70 and DPR-75, Docket Nos. 50-272 and 50-311", dated May 1, 2006 (2) Letter from PSEG to NRC: "Response to RAls on LCR S06-03, Request for Change to Technical Specifications, Accident Monitoring Instrumentation and Source Check Definition, Salem Nuclear Generating Station, Units 1 and 2, Facility Operating Licenses DPR-70 and DPR-75, Docket Nos. 50-272 and 50-311", dated October 9, 2006 In accordance with the requirements of 10 CFR 50.90, PSEG Nuclear LLC (PSEG) previously submitted License Change Request (LCR) S06-03, dated May 1, 2006, to amend the Technical Specifications (TS) for Salem Generating Station Unit 1 and Unit 2 (Reference 1). LCR S06-03 contained two proposed changes: (1) Relocation of the Main Steamline Discharge (Safety Valves and Atmospheric Dumps) Radiation Monitors (R46) from the radiation monitoring instrumentation technical specification (3.3.3.1) to the accident monitoring technical specification (3.3.3.7), and (2) Modification of TS Definition 1.31, SOURCE CHECKS, to allow for different methods to comply with the SOURCE CHECK requirement.
PSEG received a Request for Additional Information (RAI) from the NRC on LCR S06-
: 03. The response to the RAI was provided via Reference 2 dated October 9, 2006.
95-2168 REV. 7/99

FEB 2 1 2007 Document Control Desk                              -2  -
LR-N07-0036 On February 8, 2007, PSEG and the NRC Staff discussed (via telecon) the SOURCE CHECK definition change requested in LCR S06-03. PSEG agreed to revise the definition to include specific options for complying with the source check requirement.
The revised wording is provided below:
     "SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either (a) an external source of increased radioactivity, (b) an internal source of radioactivity (keep-alive source), or (c) an equivalent electronic source check."
The revised TS pages are provided in Attachment 1.
The revised definition is an updated clarification, and meets the intent of the original definition and ensures the proper functioning of detectors, based on the detector design.
Ifa detector is designed with source check capability via exposure to an external source (i.e., by an actual source attached to a mechanical device as part of the detector design), then this method would be employed. Improved technology detectors will be "qualitatively assessed" in a manner that is a significant improvement over the old methodology, and that is appropriate to their design. The proposed revised definition will allow for equivalent qualitative assessment methods, recognizing the technology of improved designs. As examples, the R46 detectors use a keep alive source, and the R44 detectors use an equivalent electronic source check (refer to Salem Amendments 272 and 253, NRC letter dated May 5, 2006)1.
If you have any questions or require additional information, please do not hesitate to contact Mr. Jamie Mallon at (610) 765-5507.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on               /Z/ /'i (Datel Sincerely, Thomas P. Joyce            /e Site Vice President Salem Generating Station Attachments 1 Note that the SOURCE CHECK requirement is only applicable for detectors in TS 3.3.3.1. The R44 detectors were relocated to TS 3.3.3.7, and the R46 detectors are proposed for relocation to TS 3.3.3.7.

FEB 21 2007 Document Control Desk                     LR-N07-0036 C    Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. Ennis, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission Mail Stop 08B1 Washington, DC 20555 USNRC Senior Resident Inspector - (Salem X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P. O. Box 415 Trenton, NJ 08625 LCR S06-03 LR-N07-0036 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License DPR-70 (Salem Unit 1) are affected by this change request:
Technical Specification                                 PaQe Definition 1.31                                         1-6 The following Technical Specifications for Facility Operating License DPR-75 (Salem Unit 2) are affected by this change request:
Technical Specification                                 PaQe Definition 1.31                                         1-6

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.
SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be FULLY WITHDRAWN.
SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.
SOLIDIFICATION 1.30 Not Used SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either (a) an external source of increased radioactivity, or(b) an internal source of radioactivity (keep-alive source), o4 (c) an equivalent electronic source check a surz* *f inezrzad eadleaetivity.
STAGGERED TEST BASIS 1.32 A STAGGERED TEST BASIS shall consist of:
: a. A test schedule for (n) systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into (n) equal subintervals.
SALEM - UNIT I                          1-6                      Amendment No. 4

DEFINITIONS REACTOR TRIP SYSTEM RESPONSE TIME 1.26 The REACTOR TRIP SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor until loss of stationary gripper coil voltage.
REPORTABLE EVENT 1.27 A REPORTABLE EVENT shall be any of those conditions specified in Section 50.73 to 10CFR Part 50.
SHUTDOWN MARGIN 1.28 SHUTDOWN MARGIN-shall be the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming all full length rod cluster assemblies (shutdown and control) are fully inserted except for the single rod cluster assembly of highest reactivity worth which is assumed to be FULLY WITHDRAWN.
SITE BOUNDARY 1.29 The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee, as shown in Figure 5.1-3, and which defines the exclusion area as shown in Figure 5.1-1.
SOLIDIFICATION 1.30   Not Used SOURCE CHECK 1.31 SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to either (a) an external source of increased radioactivity, or(b) an internal source of radioactivity (keep-alive source), or (c) an equivalent electronic source check a =curzz af inerzased radiaetivity.
STAGGERED TEST BASIS 1.32  A STAGGERED TEST BASIS shall consist of:
: a. A test schedule for (n) systems, subsystems, trains, or other designated components obtained by dividing the specified test interval into (n) equal subintervals.
SALEM - UNIT 2                          1-6                  Amendment No. 24-&  I}}