View source for BVY 08-081, Submittal of Revision of Technical Specification Bases Page 29

{{Adams
| number = ML083260572
| issue date = 11/17/2008
| title = Submittal of Revision of Technical Specification Bases Page 29
| author name = Colomb M
| author affiliation = Entergy Nuclear Operations, Inc
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000271
| license number = DPR-028
| contact person = 
| case reference number = BVY 08-081
| document type = Letter type:BVY, Technical Specification, Bases Change
| page count = 4
}}

=Text=
{{#Wiki_filter:m                                                            Entergy Nuclear Operations, Inc.
Vermont Yankee P.O. Box 0250 En                                              320 Governor Hunt Road Vernon, VT 05354 Tel 802 257 7711 November 17, 2008 BVY 08-081 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

==Subject:==
Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)
Revision of Technical Specification Bases Page 29

==Dear Sir or Madam,==

This letter provides revised Technical Specification (TS) Bases page. TS Bases page 29 was revised to recognize an additional condition under which the APRMs may be bypassed provided the minimum number of operable channels is maintained. The additional information is consistent with Vermont Yankee's licensing basis.
This change to the TS Bases was processed in accordance with the TS Bases Control Program specified in TS 6.7.E and has been determined to not require a license amendment in accordance with 10CFR50.59. Therefore, prior NRC approval is not required.
A revised TS Bases page is attached for your records. No NRC action is requested on this submittal.
There are no new regulatory commitments being made in this submittal.
If you have any questions concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304.
Sincerely, Michael J\.,oomUb Site Vice President Vermont Yankee Nuclear Power Station

==Attachment:==
Revised Technical Specification Bases Page cc list (next page)

BVY 08-081 Docket 50-271 Page 2 of 2 cc: Mr. Samuel J. Collins, Region 1 Administrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 USNRC Resident Inspector Vermont Yankee Nuclear Power Station 320 Governor Hunt Road P.O. Box 157 Vernon, VT 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street, Drawer 20 Montpelier, VT 05620-2601

BVY 08-081 Docket No. 50-271 Attachment 1 Vermont Yankee Nuclear Power Station Revised Technical Specification Bases Page

VYNPS BASES:
3.1   Reactor       Protection            System The      reactor protection               system automatically           initiates           a  reactor       scram to:
: 1. preserve the           integrity        of the fuel barrier;
: 2.      preserve the           integrity        of the primary system barrier;                       and
: 3.      minimize the           energy which must be absorbed, and prevent criticality following a          loss of coolant accident.
This specification                 provides the limiting            conditions for operation necessary to preserve the ability                     *of the system to tolerate                single      failures        and still perform its           intended function even during periods when instrument channels may be out of service because of maintenance,                                testing,          or calibration.          The basis for the allowable out-of-service                            times is provided in GE Topical Report NEDC-308512-A,                    "Technical Specification               Improvement Analysis for BWR Reactor Protection System," March 1988.
The reactor           protection          system is of the dual channel type.                            The system is made up of two independent logic channels, each having three subsystems of tripping        devices.           One of the three subsystems has inputs from the manual scram push buttons and the reactor                           mode switch.           Each of the two remaining subsystems has an input from at                        least    one independent sensor monitoring each of the critical                   parameters.          The outputs of these subsystems are combined in a 1 out 'of 2 logic;                       i.e.,    an input signal             on either         one or both of the subsystems.will cause a trip                           system trip.            The outputs of the trip systems are arranged so that                      a t-rip on both logic channels is required to produce a reactor                 scram.
The required conditions when the minimum instrument logic conditions are not met are chosen so as to bring station                              operation promptly to such a condition that             the particular          protection       instrument is not required; or the station       is placed in the protection                     or safe condition that                   the instrument initiates.            This is accomplished in a normal manner without subjecting                                        the plant      to abnormal operating conditions.
When the minimum requirements for the number of operable or operating trip system and instrumentation channels are satisfied,                                      the effectiveness           of the protection           system is preserved; i.e.,                  the system can tolerate                    a single failure       and still          perform its       intended function of scramming the reactor.
Three APRM instrument channels are provided for each protection                                               trip   system to provide ,for high neutron flux protection.                                APRM's A and E operate contacts in a trip                 subsystem, and APRM's C an E operate contacts in the other trip          subsystem.            APRM's B, D, and F are arranged similarly                             in the other protection               trip      system. Each protection            trip      system has one more APRM than is necessary to meet the minimum number required.                                                This allows the bypassing of one APRM per protection                            trip     system for maintenance, testing,        calibration,             or to minimize single           failure         vulnerabilities associated with shared LPRMs, while maintaining the minimum number of channels required for inputs to each trip                             system.          Operating with two APRMs bypassed meets all                 design and technical specification                       requirements.
Additional IRM channels have also been provided to allow bypassing of one such channel.              For a description             of the Neutron Monitoring Systems, see FSAR Section 7.5.
The bases for the scram settings                         for the IRM, APRM, high reactor                        pressure, reactor       low water level, turbine control valve fast                                closure, and turbine stop valve closure are discussed in Specification                                    2.1.
Amendment No.         24,     -+-4, 44-4, B,                      BVY 08-081                                                     29}}