ML20207R963
| ML20207R963 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/03/1987 |
| From: | Joshua Wilson Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20207R964 | List: |
| References | |
| NUDOCS 8703180363 | |
| Download: ML20207R963 (6) | |
Text
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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 16 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment, dated February 12, 1987, by Louisiana Power and Light Company (licensee), complies with 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 (1) that the activities avthorized 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 cosmon defense and security or to the health and safety of the public; 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. MPF-38 is hereby amended to read as follows:
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2-(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 16, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in this license.
LP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of February 13, 1987.
FOR THE NUCLEAR REGULATORY COMMISSION
?"'s J
ts H. Wilson, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Attachment:
Changes to the Technical Specifications Date of Issuance:
Mrch 3,1987
..._..___.~..._m March 3, 1987 ATTACHMENT TO LICENSE AMENDMENT NO. 16 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following page of the Appendix A Technical Specification with the enclosed page.
Amendment Page 3/4 1-4 Pages 3/4 1-3 and 3/4 1-3a are reissued for pagination purposes.
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Reissued 3/3/87 REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - ALL CEAS FULLY INSERTED LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to that shown in Figure 3.1-0.
APPLICABILITY: MODE 2*#, 3, 4 and 5 with all CEAs fully inserted.
l ACTION:
With the SHUTDOWN MARGIN less than that shown in Figure 3.1-0, immediately initiate and continue boration at greater than or equal to 40 gpa of a solu-tion containing greater than or equal to 1720 ppe boron or equivalent until the required SHUTDOWN MARGIN is restored.
SURVEILLANCE REQUIREMENTS 4.1.1.2.1 With all full length CEAs fully inserted, the SHUTDOWN MARGIN shall be determined to be greater than or equal to that shown in Figure 3.1-0.
When in MODE 2 with k,ff less than 1.0, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to a.
achieving reactor criticality by verifying that the predicted critical CEA position is within the limits of Specification 3.1.3.6.
b.
When in MODES 3, 4, or 5, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by considera-tion of the following factors:
1.
Reactor Coolant System boron concentration, 2.
CEA position, 3.
Reactor Coolant System average temperature, 4.*
Fuel burnup based on gross themal energy generation, 5.
Xenon concentration,and 6.
Samarium concentration.
4.1.1.2.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within i 1.0K delta k/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated.in Specification 4.1.1.2.lb, above. The predicted reac-tivity values shall be adjusted (normalized) to correspond to the actual core conditionspriortoexceedingafuelburnupof,,dDEFPDaftereachfuelloading.
- With k,ff less than 1.0
- See Special Test Exception 3.10.1 WATERFORD - UNIT 3 3/4 1-3 AMEN 0 MENT NO. 11
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100 200' 300 400' 500' 600' COLD LEG TEMPERATURE (*F) i Figure 3.1-0 SHUTDOWN MARGIN AS A FUNCTION OF COLD LEG TEMPERATURE WATERFORD - UNIT 3 3/4 1-3a AMENDMENT NO. 11
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REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be:
-4 a.
Less positive than 0.5 x 10 delta k/k/*F whenever THERMAL POWER is < 70% RATED THERMAL POWER, and
~4 b.
Less positive than 0.0 x 10 delta k/k/*F whenever THERMAL POWER is > 70% RATED THERMAL POWER, and
-4 c.
Less negative than -3.3 x 10 delta k/k/*F at all levels of THERMAL POWER.
MODES 1 (1) and 2*#
APPLICABILITY:
ACTION:
With the moderator temperature coefficient outside any one of the above limits, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SURVEILLANCE REQUIREMENTS e-4.1.1.3.1 The MTC shall be determined to be within its limits by confirmatory measurements. MTC measured values shall be extrapolated and/or compensated to permit direct comparison with the above limits.
4.1.1.3.2 The MTC shall be determined at the following frequencies and THERMAL POWER conditions during each fuel cycle:
a.
Prior to initial operation above 5%.of RATED THERMAL POWER, after each fuel loading.
b.
At greater than 15% of RATED THERMAL POWER, prior to reaching 40 EFPD core burnup.
c.
At any THERMAL POWER, within 7 EFPD of reaching two-thirds of expected core burnup.
"With K,ff greater than or equal to 1.0.
- See Special Test Exception 3.10.2.
- (1)See Special Test Exception 3.10.2 applicable for Mode 1 during startup test of Cycle 2.
WATERFORD - UNIT 3 3/4 1-4 AMENDMENT NO. 16
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