View source for RBG-25339, Forwards Table 2.2.1-1,inadvertently Omitted from Encl 2 to 870128 Tech Spec Change Request,For Review & Concurrence

{{Adams
| number = ML20211A923
| issue date = 02/13/1987
| title = Forwards Table 2.2.1-1,inadvertently Omitted from Encl 2 to 870128 Tech Spec Change Request,For Review & Concurrence
| author name = Deddens J
| author affiliation = GULF STATES UTILITIES CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000458
| license number = 
| contact person = 
| document report number = RBG-25339, NUDOCS 8702190263
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 3
}}

=Text=
{{#Wiki_filter:i GULF STATES                        UTILITIES COMPANY HrVER BEND STATION     POST OFFICE BOX 220    ST FRANCISVILLE. LOUISIANA 70775 AREA CODE 504     635 6094     346 8651 l
February 13, 1987 RBG- 25339                           )
File No. G9.5                        j l
U.S. Nuclear Regulatory Commission                                                                          '
Document Control Desk Washington, DC 20555 Gentlemen:
River Bend Station - Unit 1 Docket No. 50-458 Gulf States Utilities (GSU) submitted by {{letter dated|date=January 28, 1987|text=letter dated January 28, 1987}} (RBG-25277) a technical specification change request for your review and concurrence. It has been brought to my attention that there was an omission of Enclosure 2 of our letter.                                          Please include the attached enclosure with the original submittal.
Since*ely,
                                                                                . C. Deddens Senior Vice President River Bend Nuclear Group Enclosures JCD/JEB       B          s
                                                                                                                \
8702190263 870213                                                                                          h0 PDR  ADOCK 05000450                                                                                           j)g P               PDR                                                                                             ,

n       -
3 cc:  Mr. Robert D. Martin, Regional Administrator
              -U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 NRC Senior Resident Inspector Mr. William H. Spell, Administrator Nuclear Energy. Division Louisiana Department of Environmental Quality P.O. Box 14690 Baton Rouge, LA 70898 f
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TABLE 2.2.1-1                                              -
REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS oo                                                                                                                                 ALLOWABLE FUNCTIONAL UNIT                                                     TRIP SETPOINT            VALUES 2
: 1. Intermediate Range Monitor, Neutron Flux-High                  < 120/125 divisions    < 122/125 divisions
[
se                                                                                                          of full scale          of full scale Z                                        2. Average Power Range Monitor:                                                                                    !
                                                             "                                                 Neutron Flux-High, Setdown                                < 15% of RATED         < 20% of RATED a.
THERMAL POWER         THERMAL POWER
: b. Flow 81ased Simulated Thermal Power-High
: 1) Flow Blased                                            1 0.66 W+48%, with     5 0.66 W+SIX, with        ,
a maximum of           a maximum of              !
: 2) High Flow Clamped                                      5 111.0% of RATED      1 113.0% of RATED         .
THERMAL POWER            THERMAL POWER
: c. Neutron Flux-High                                         5 118% of RATED        1 120E of RATED 1
THERMAL POWER         THERMAL POWER 2                                                             ro                                                                                                                             ,
I                                          d. Inoperative                                               NA                    NA n
: 3. Reactor Vessel Steam Dome Pressure - High                      5 1064.7 psig          $ 1079.7 psig        y
: 4. Reactor Vessel Water Level - Low, Level 3                       1 9.7 inches above    1 8.7 inches above   $
instrument zero*      instrument zero   y
: 5. Reactor Vessel Water Level-High, Level 8                       5 51.0 inches above    5 52.1 inches above  eo instrument zero*      instrument zero
: 5. Main Steam Line Isolation Valve - Closure                      1 8% closed            5 12% closed
: 7. Main Steam Line Radiation - High                                i 3.0 x full power    5 3.6 x full power background            background
: 8. Drywell Pressure - High                                         5 1.68 psig           5 1.88 psig
: 9. Scram Discharge Volume Water Level - High
: a. Level Transmitter - LISN601A and B                        < 49"                  < 53" LISN601C and D                      549"                  {    51.7"
: b. Float Switches - LSN013A and B                            5  A'  32"   48.76"    $ 53.50" LSN013C and D                          $ At   sa"   46.88"   1 49.00"
                                                                                                      *See Bases Figure B 3/4 3-1.
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