ML20118A829
| ML20118A829 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/18/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20118A830 | List: |
| References | |
| NUDOCS 9209280232 | |
| Download: ML20118A829 (7) | |
Text
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- o UNITED STATES I
[ *4 3 4 7,,g NUCI.E AR REGULATORY COMMISSION p
WASHINGTON, D. C. 205%
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382
)LATERFORD STEAM ELECTRIC STATION. UNIT 3 BiENDMENT TO FAClllTY OPERATING llCENSE Amendment No. 76 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated April 24, 1992, as supplemented by letter dated August 27, 1992, 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; 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; 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.
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. 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 Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment t;o. 76, 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 Pian.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION V
John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects III/IV/V Office of Nuclear P.eactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 18, 1992 l
6 I
ATTACHMENT TO LICENSE AMENDMENT NO. 76 TO FACILITY OPERATING LICENSE N0. NPF-38 DOCKET _NO. 50-382 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE PAGES INSERT par [g 1
3/4 7-9 3/4 7-9 3/4 3-23 3/4 3-23
i-PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTION:
MODE 1 With one main steam line isolation valve inoperable but open, POWER OPERATION may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />; otherwise, 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 />.
MODES 2, 3, and 4 With one main steam line isolation valve inoperable, subsequent operation in MODE 2, 3, or 4 may proceed provided:
a.
The isolation valve is maintained closed.
b.
The prov'sions of Specification 3.0.4 are not applicable.
Otherwise, be in at least POT 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 COLD SHUTOOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.5 Each main steam line isolation valve shall be demonstrated OPERABLE.
by verifying full closure within 4.0 seconds-when tested pursuant to l
Specification 4,0.5.
WATERFORD - UNIT 3 3/4 7-9 Amendment No. 76 l
^
4 PLANT SYSTEMS 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION LIMITING CONDITION FOR OPERATION 3.7.2 The temperature of the secondary coolant in the steam generators shall be greater than il5'F when the pressure of the secondary coolant is greater than 210 psig.
APPLICABILITY:
At all times.
ACTION:
With the requirements of the above specification not satisfied:
Reduse the steam generator pressure to less than or equal to a.
210 psig within 30 minutes, and b.
Perform an ent,ineering evaluation to determine the effect of the overpressurization on the structural integrity of the steam generator.
Determine that the steam generator remains acceptable for continued operation prior to increasing its temperatures above 200*F.
b SURVE?LLANCE DEQUIREMENTS 4.7.2 The pressure of the steam generators shall be determined to be less than 210 psig at least once per hour when the temperature of the secondary coolant is less than 115'F.
WATERFORD - UNIT 3 3/4 7-10 Amendment No, 6
TAL!.E-3.3-5 (Continued).
a
'NGINEERED SAFETY-FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION-RESPONSE TIME IN SECONOS 3_
2.-
Pressurizer Pressure-Low a.-
' Safety Injection (ECCS)
(1) High Pressure Safety Injection
< 30.0*/18.5**
-(2) Low Pressure Safety. Injection 545.5*/34.0**-
b.
. Containment Isolation s'23.5*/12.0**
c.
Containment Cooling 5 31.0*/19.5**
-3.
Containment Pressure-High a.
Safety Injection (ECCS)
(1) High Pressure Safety Injection
.< 30.0*/18.5**
(2) Low Pressure Safety Injection 545.5*/34.0**
l b.
Containment Isolation
< 23.5*/12.0**
c.
Main Steam-Isolation E 5.0*/5.0**
l d.
Main Feedwater Isolation 56.0*/6.0**
e.
Containment Cooling 5 31.0*/19.5**-
4.
Containment Pressure--High-HiaF l
a.
Containment Spray Pump
< 15.2*/2.7**
b.
Containment Spray Valves 7 11.0*/11 0**
c.
CCW to RCP Valves 323.5*/12.0**
5.
Containment Area Radiation-High#
Containment Purge' Valves Isolation 1 6.2*/6.2**
6.
Steam Generator Pressure-Low a
a.
Main Steam Isolation
< 5.0*/5.~0**
- I:
b.
Main Feedwater Isolation
_3_6.0*/6.0**
1 7.
Refueling Water Storage Pool-Low Containment Sump Recirculation-5 120.0*/108.5**-
8.
4.16-kV Emergency Bus Undervoltage--(Loss of Voltage)_
Loss of Power (0 volts)~
?$ 2***
9.
480V Emergency Bus Undervoltage'(Loss of Voltage)
Loss of Power _(0 volts)
N.A.
10.
4.16 kV Emergency' Bus Undervoltage (Degraded Voltage)-
Loss of Power
$ 11***
WATERFORDl-UNIT-3 3/4 3-23 Amendment No. 76
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i TABLE 3.3-5 (Continued)
ENGINEERED SAFETY FEATURES RESPONSE TIMES INITIATING SIGNAL AND FUNCTION RESPONSE TIME IN SECONDS 11.
Steam Generator Level-Low Emergency Feedwater Pump and 1 54.0*/42.0**
Block Valves 12.
Wide Range Steam Generator Level-Low Emergency Feedwater Control Valves
< 25.0*/25.0**
l NOTE:
Response time for all Motor-Driven 1 54.0 and Steam-Driven Emergency Feedwater l
Pumps on all ESF signal starts.
TABLE NOTATIONS.
- Diesel generator starting and sequence loading delays included.
Response
time limit includes movement of valves and attainment of pump or blower discharge pressure.
i l
- Diesel generator starting and sequence loading delays not included.
Offsite power available.. Response time limit includes movement of valves and attainment of pump or blower discharge pressure.
- Response time measured from the sensing-relay to the channel output'only.
l
- Response time does not include the detector.
WATERFORD - UNIT 3 3/4 3-24