ML20196D673
| ML20196D673 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 12/02/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20196D678 | List: |
| References | |
| NUDOCS 8812090159 | |
| Download: ML20196D673 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION 5
WASHINGTON, D. C. 20066
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LOUISIANA POWER AND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STAT 10 M NIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-38 1.
The Nuclear Regulatory Comission (the Corcission) has found that:
A.
The application for amendment by Louisiana Power and Light Contpany (the licensee) dated June 7,1988 as supplemented by letter dated August 8, 1988, complies with the standards and requirerrents of the Atomic Energy Act af 1954, as amended (the Act), and the Comission's rules and regulations ses forth in 10 CFR Chapter I; B.
The facility will operate in conforniity with the application, the provisions of toe Act, and the rules and regulations of the Comission; C.
Thereisreasonableas*.urance(1)thattheactivitiesauthorized by this arrendrent can be conducted without endangering the health er,d safety of the public, and (ii) that such activitier, will be corducteo in compliance with the Cutaission's regulations; D.
The issuance of this anendment will not be inimical to the cortzon defense and securit) 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 Corsnission's regulations and all applicable requirements have been satisfied.
i es12090159 881202 PDR ADOCK 050003G2 FDC p
e 2-2.
Accordingly, the license is acended by changes to the Technical Specifications as indicated in the attachnent to this license aniendment, 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 Amer.dment No. 46, and the Environmental Prciection 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.
FOR THE NUCLEAR REGULATORY COMMISSION j
d.
Cwk Jose A. Calvo, Direr.or Project Directorate - IV Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation Attachn.ent:
Changes to the Technical Specifications Date of Issuance: December 2,1988
e ATTACHMENT _Tp, LICENSE AMENDMENT,Np.,46 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKETNO.50-3!2 Replace the following page of the Appendix A Technical Specifications with the attached page. The revised page is identified by Amendment r.umb4r and contains a vertical line indicating the area of change. The cor esponding overleaf page is also provided to maintain document completeness.
Remove Insert 3/4 3-3 3/4 3-3 O
TABLE 3.3-1 I
f y
REACTOR PROTECTIVE INSTRUMENTATION 2
- o MINIMUM TOTAL NO.
CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERA 8LE MODES ACTION Z
1.
Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1 2 1
A w
2 sets of 2 1 set of 2 2 sets of 2 3, 4*, 5*
8 2.
Linear Power Level - High 4
2 3
1, 2 2#, 3#
3.
Logarithmic Power Level-High a.
Startup and Operating 4
2(a)(d) 3 2**
2#, 3#
4 2
3 3*, 4*, 5*
8 b.
Shutdown 4
0 2
3, 4, 5 4
4.
Pressurizer Pressure - High 4
2 3
1, 2 2#, 3#
y 5.
Pressurizer Pressure - Low 4
2(b) 3 1, 2 2#, 3#
6.
Containment Pressure - High 4
2 3
1, 2 2#, 3#
w 7.
Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#
8.
Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#, 3#
9.
Local Power Density - High 4
2(c)(d) 3 1, 2 2#, 3#
- 10. Dost - Low 4
2(c)(d) 3 1, 2 2#, 3#
- 11. Steam Generator Level - High 4/SG 2/SG(g) 3/SG 1, 2 2#, 3#
- 12. Reactor Protection System Logic 4
2 3
1 2 5
4 I
3, 4*, 5*
8 m5
- 13. Reactor Trip Breakers 4
2(f) 4 1 2 5
J, I3, 4*, 5*
8
- 14. Core Protection Calculators 4
2(c)(d) 3 1, 2 2#, 3# and 7
- 15. CEA Calculators 2
1 2(e) 1, 2 6 and 7
,M
- 16. Reactor Coolant Flow - Low 4/SG 2/SG(c) 3/SG 1, 2 2#, 3#
l
6 TABLE 3.3-1 (Continued)
TABLE NOTATION a
With the protective systen trip breakers in the closed position, the CEA drive system capable of CEA withdrawal, and fuel in the reactor vessel.
The provisions of Specification 3.0.4 are not app)icable.
- Not applicable above 10'4% RATED THERMAL POWER.
(a) Trip say be manually bypassed above 10'4% of RATED THERMAL POWER; bypass shal)4be automatically removed when THERMAL POWER is less than or equal to 10
% of RATED THERMAL POWER.
(b)
Trip say be manually bypassed below 400 psia bypass shall be auto-matica11y removed whenever pressurizer pressu;re is greater than or equal to 500 psia.
(c) Trip may be manually bypassed below 10'4% of RATED THERMAL POWER; bypass shall br4 automatically removed when THERMAL POWER is grsster than or equal to 10 % of RATED THERMAL POWER.
During testing pursuant to Special Test Exception 3.10.3, trip say ba manually bypassed below 5%
of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 5% of RATED THERMAL POWER.
(d) Trip say be bypassed during testing pursuant to Special Test Exception 3.10.3.
(e) See Special Test Exception 3.10.2.
(t) Each channel shall be comprised of two trip breakers; actual trip logic shall be one-out-of-two taken twice.
1 (g) High steam generator level trip say be manually bypassed in Modes 1 and 2' at 20% power and below.
1 ACTION STATEMENTS ACTION 1 With the nun 6sr of channels OPERA 8LE one its than required by the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERABLE status within 44 hours5.092593e-4 days <br />0.0122 hours <br />7.275132e-5 weeks <br />1.6742e-5 months <br /> or be in at least HOT STAM08Y within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the protective system trip breakers.
ACTION 2 With the number of channels OPERABLE one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may continue provided the inoperable channel is placed in the bypassed or tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with Specification 6.5.1.6k.
The channel shall be returned to OPERABLE status prior to STARTUP following the next COLD SHUTDOWN.
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WATERFCRD - UNIT 3 3/4 324 AMENOMENT N0. ZA,40
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