ML20235G752
| ML20235G752 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 09/23/1987 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20235G755 | List: |
| References | |
| NUDOCS 8709300198 | |
| Download: ML20235G752 (9) | |
Text
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UNITED STATES i
'i NUCLEAR REGULATORY COMMISSION
.c <
y W ASHtNGTON. D. C. 20555
\\...../
GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 l
RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 11 License No. NPF-47 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by Gulf States Utilities Company, dated September 12, 1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-47 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amenument No.11 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
GSU shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8709300198 870923 PDR ADDCK 05000458 P
, 3.'
- This license' amendment'is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f/
lTt N i W
,[/ Jose A. Calvo, Director-
[,
Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
LChanges to the Technical Specifications 3
Date of Issuance: September 23, 1987 i
1 i
l
,q
' ATTACHMENT'TO LICENSE AMENDMENT NO.Il-T FACILITY 0PERATING LICENSE NO. NPF-47 DOCKET NO.-50-458.
Replace the.following_page of-the Appendix "A" Technical' Specifications with
'the enclosed page. The revised page is identified _by Amendment number and contains a vertical line indicating the area of change. Overleaf page
~
provided.to maintain document completeness.
REMOVE >
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l TABLE 3.3.2-3 l
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME I
TRIP FUNCTION-RESPONSE TIME (Seconds)#
1.
PRIMARY CONTAINMENT ISOLATION j
a.
Reactor Vessel Water Level - Low Low Level 2
< 10 ")
I 510(a) b.
Drywell Pressure - High g) c.
Containment Purge Isolation Radiation - High NA 1
2.
MAIN STEAM LINE ISOLATION l
a.
Reactor Vessel Water Level - Low Low Low l
< 1.0 */< 10 *)**
i f
Leyel 1 Main Steam Line Radiation - High(b)
I 1.0 */2 10((*a))**,
l b.
I 1.0 */2 10(a),,,
c.
Main Steam Line Pressure - Low 50.5*/510 d.
Main Steam Line Flow - High e.
Condenser Vacuum - Low NA f.
Main Steam Line Tunnel Temperature - High NA l
g.
Main Steam Line Tunnel a Temperature - High NA L
h.
Main Steam Line Area Temperature - High (Turbine Bldg)
NA 3.
SECONDARY CONTAINMENT ISOLATION I
< 10 *")
a.
Reactor Vessel Water Level - Low Low Level 2 f) 10 Drywell Pressure - High b.
Fuel Building Ventilation Exhaust Radiation - High(b)
NA c.
Reactor Building Annulus d.
Ventilation Exhaust Radiation - High(b)
~'
NA 4.
-REACTOR WATER CLEANUP SYSTEM ISOLATION i
1 10 *)##
I a.
a Flow - High b.
A Flow Timer NA
- c.. Equipment Area Temperature - High NA I
d.
Equipment Area A Temperature - High NA g)
I e.
Reactor Vessel Water Level - Low Low Level 2 5 10 f.
Main Steam Line Tunnel Ambient Temperature - High NA g.
Main Steam Line Tunnel a Temperature - High NA h.
SLCS Initiation NA 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION 1 10 ")###
j I
a.
RCIC Steam Line Flow - High t
b.
RCIC Steam Line Flow-High Timer NA
- c. -RCIC Steam Supply Pressure - Low 1 10(*)
d.
RCIC Turbine Exhaust Diaphragm Pressure - High NA
_e. RCIC Equipment Room Ambient Temperature - High NA f.
RCIC Equipment Room a Temperature - High NA g.
Main Steam Line Tunnel Ambient Temperature - High NA l
h.
Main Steam Line Tunnel 6 Temperature - High NA RIVER BEND - UNIT 1 3/4 3-24 l
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