ML20129E759
| ML20129E759 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/27/1996 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129E762 | List: |
| References | |
| NUDOCS 9610030279 | |
| Download: ML20129E759 (5) | |
Text
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p UNITED STATES y
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NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20086 0001 I
j I.
ENTERGY OPERATIONS. INC.
1 DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 l
AMENDMENT TO FACILITY OPERATING LICENSE i
i Amendment No. 121 License No. NPF-38 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the l
licensee) dated November 7,1995, as supplemented by letter dated April 11, 1996, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; i
i B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and 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; i
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.
1 i
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9610030279 960927 PDR ADOCK 05000382 P
PDR n
, 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. NPF-38 is hereby amended to read as follows:
(2) Technical Snecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.121, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION A
h Chandu P atel, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to th? Technical Specifications Date of Issuance: September 27, 1996
-n w
i ATTACHMENT TO LICENSE AMENDMENT NO.121 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGE INSERT PAGE 3/4 5-1 3/4 5-1
3/4.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3/4.5.1 SAFETY INJECTION TANKS LIMITING CONDITION FOR OPERATION 3.5.1 Each Reactor Coolant System safety injection tank shall be OPERABLE with:
a.
The isolation valve open, b.
A contained borated water volume of between 926 (40%) and 1807 l
(83.8%) cubic feet, c.
Between 1720 and 2300 ppe of boron, and d.
A nitrogen cover-pressure of between 600 and 670 psig.
l
- APPLICABILITY: MODES 1, 2, 3*, and 4*.
ACTION:
a.
With one safety injection tank inoperable, except as a result of a closed isolation valve, restore the inoperable tank to OPERABLE status within 'I hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With one safety injection tank inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within I hour and be in HOT SHUTDOWN within the next-12 hours.
SURVEILLANCE REQUIREMENTS 4.5.1 Each safety injection tank shall be demonstrated OPERABLE:
a.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by:
1.
Verifying the contained borated water volume and nitrogen cover-pressure in the tanks, and 2.
Verifying that each safety injection tank isolation valve is open.
- With pressurizer pressure greater than or equal to 1750 psia.. When pressurizer pressure is less than 1750 psia, at least three safety injection tanks must be OPERABLE, each with a minimum pressure of 235 psig and a maximum pressure of 670 psig, and a contained borated water volume of between 1332 l
(61%) and 1807 (83.8%) cubic. feet. With all four safety injection tanks OPERABLE, each tank shall have a minimum pressure of 235 psig and a maximum pressure of 670 psig, a boron concentration of between 1720 and 2300 ppm
[
boron, and a contained borated water volume of between 888 (39%) and 1807 (83.8%) cubic feet.
In MODE 4 with pressurizer pressure less than 392 psia (700 psia for remote shutdown from LCP-43), the safety injection tanks may be isolated.
WATERFORD - UNIT 3 3/4 5-1 AMENDMENT NO.121
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4 EMERGENCY CORE COOLING SYSTEMS 2
]
SURVEILLANCE REQUIREMENTS (Continued) t b.
At least once per 31 days and within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after each solution
{i volume increase of greater than or equal to 1% of tank volume i
by verifying the boron concentration of the safety injection tank solution.
j c.
At least once per 31 days when the RCS pressure is above 1750 psia, i
by verifying that' the isolation valve operator breakers are padlocked in the open position.
i l
d.
At least once per 18 months by verifying that each safety injection i
tank isolation valve opens automatically under each of the following conditions:
i i
i 1.
When an actual or simulated RCS pressure signal exceeds 535 psia, and J
l 2.
Upon receipt of a safety injection test signal.
4 WATERFORD - UNIT 3 3/4 5-2