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

From kanterella
Jump to navigation Jump to search
Forwards Table 2.2.1-1,inadvertently Omitted from Encl 2 to 870128 Tech Spec Change Request,For Review & Concurrence
ML20211A923
Person / Time
Site: River Bend Entergy icon.png
Issue date: 02/13/1987
From: Deddens J
GULF STATES UTILITIES CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RBG-25339, NUDOCS 8702190263
Download: ML20211A923 (3)


Text

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 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

{

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.

l