ML20149H291
| ML20149H291 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 02/11/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20149H293 | List: |
| References | |
| NUDOCS 8802190203 | |
| Download: ML20149H291 (5) | |
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UNITED STATES g
8 NUCLEAR REGULATORY COMMISSION o
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GULF STATES UTILITIES COMPANY DOCKET NO. 50-458 RIVER BEND STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.18 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 August 5, 1987 as supplemented November 23, 1987, 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 4
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.
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. 2.
Accordingly, the. license is amended by changes to the Technical Specifi-cations as indicated in the attschment to this license amendment and l
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 Amendment No, 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.
3.
The license amendment is effective as of its date of issuance.
I FOR THE NUCLEAR REGULATORY COMMISSION D
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Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications Date of Issaance: February 11, 1988 I
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ATTACHMENT TO LICENSE AMENDMENT NO. 18 FACILITY OPERATING LICENSE NO. NPF-47 l
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 lina indicating the area of change.
Overleaf page provided to maintain document completeness.
REMOVE INSERT 3/4 7-36 3/4 7-36 B
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0 PLANT SYSTEMS 3/4.7.10 STRUCTURAL SETTLEMENT LIMITING CONDITION FOR OPERATION 3.7.10 Structural settlement shall be within the predicted values as shown in Table 3.7.10-1 and calculated differential settlements shall be within the allowable ranges shown in Table 3.7.10-2 for the following structures:
a.
Reactor Building b.
Auxiliary Building c.
Fuel Building d.
Control Building e.
Diesel Generator Building f.
Standby Cooling Tower, Basin and Pump House g.
BF Tunnel h.
Main Steam Tunnel i.
E Tunnel j.
G Tunnel APPLICABILITY:
At all times.
ACTION:
With the measured structual settlement of any of the above required structures outside of the limits of Tables 3.7.10-1 and 3.7.10-2, prepare and submit, within the next 30 days, a Special Report to the Commission, pursuant to Specification 6.9.2, providing a record of the settlement measurements and the predicted settlement, an analysis to demonstrate the continued structural integrity of the affected structure (s), and plans to monitor the settlement of the affected structure (s) in the future.
The provisions of Specification 3.0.3 and 3.0.4 are not applicable to the limits established in Table 3.7.10-1.
SURVEILLANCE REQUIREMENTS 4.7.10 The structural settlement of the above required structures shall be demonstrated to be within the limits of Tables 3.7.10-1 and 3.7.10-2:
a.
At least once per 92 days, until there is essentially no movement during those 92 days.
b.
At least once per 24 months, for at least 10 years.
c.
Following any seismic event equal to or greater than an Operational Ba. sis Earthquake (0BE).
RIVER BEND - UNIT 1 3/4 7-35
TABLE 3.7.10-1 TOTAL PREDICTED SETTLEMENTS OF MAJOR STRUCTURES SETTLEMENT PREDICTED STRUCTURE MARKER NO.
SETTLEMENT (IN.)
Reactor Building 15 4.0 16 4.0 17 4.0 Auxiliary Building 18 3.8 19 3.6 20 3.9 21 3.7 Fuel Building 11 3.7 12 4.0 13 3.5 14 3.8 Control Building 5
3.7 6
3.3 7
3.7 8
3.7 Diesel Generator Building 1
3.4 2
3.7 3
3.6 4
3.8 Standby Cooling Tower, Basin 30 2.7 i
and Pump House 31 3.2 1
32 2.4 BF Tunnel 9
2.1 i
10
- 2. 5 Main Steam Tunnel 22 3.8 23 3.8 E Tunnel 28 3.3 l
29 2.8
!l G Tunnel 33 2.6 1
34 1.3 l
RIVER BEND - UNIT 1 3/4 7-36 Amendment No.18