ML19332D251
| ML19332D251 | |
| Person / Time | |
|---|---|
| Site: | Waterford  (NPF-38-A-059, NPF-38-A-59) |
| Issue date: | 11/14/1989 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19332D252 | List: |
| References | |
| NUDOCS 8911300221 | |
| Download: ML19332D251 (6) | |
Text
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NUCLE AR REGULATORY COMMISSION g-
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LOUISIANA POWER A_ND LIGHT COMPANY DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION, UNITj ANENDMENT TO FACILITY OPERATING LICENSE Amendment No. 59 License No. NPF-38 1.
The Nuclear Regu16 tory Commission (the Concission) has found that:
A.
The application for amenoment by Louisiana Power and Light Company -(the licensee) dated October 5,1989 as supplemented by letters dated October 23 and hovember 1,1989, complies with the standrds and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commiss1on's rules and regulations set forth in 10 CFR Chapter I; E.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulatier.s of the l
Commissicn; L
C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without encangering the behlth and safety of the public, and (11) that such activities will be concocted in conpliance with the Comission's regul6tions; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the i
L public; and E.
The issuance of this amendnent is in accordance with 10 CFR l
Part 51 of the Comission's regulhtions and all applicable L
requirements have been satisfied.
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1 8911300221 891114 ADOCK0500g2 PDR l
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2 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachnent to this license i
amendrent, 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 Amenoment No. 59 and the Environnental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specificattors and the Environnental Protection Plan.
3.
This license ar,endment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C011 MISSION s,
Frectrick J. Hebc;cn, Director Project Directorate IV Division of Reactor Projects - !!!,
IV, V and Special Projects Office of Nuclear Reactor Regulation Attachne nt:
Chenges to ti>e Technicc1 Specificationt Date of Issuance: November 14, 1989
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ATTACHMENT TO LICENSE AMENDriENT I40. 59 TO FACILITY OPERATING LICENSE NO. NPF-38 DOCKET NO. 50-382 Replace the following pages of the Appendix A Technical $pecifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change. The corresponding overleaf page is also provided to maintain document completeness.
Remove Insert 3/4 1-15 3/4 1-15 i
3/4 1-10 3/4 1-16 I
t 1
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REACTIVITY CONTROL SYSTEMS BORON DILUTION LIMITING CONDITION FOR OPERATION 3.1.2.9 Boron conenntration shall be verified consistent with SHUTDOWN MARGIN requirements of Specifications 3.1.1.1, 3.1.1.2, and 3.9.1.
Boron dilution events shall be precluded by either "a" or "b" below.
a.
1.
Two boron dilution alarms (startup channel high neutron flux) shall be OPERABLE with the alarms set in accordance with Specification 4.1.2.9.5 A.d 2.
i.
If the plant is in MODE 4, then remove power to at least one charging pump.
ii.
If the plant is in MODE 5 with k power to at least one charging p6h.~< 0.97, then remove iii. If the plant is in MODE 5 with k powertoatleasttwochargingp8ks>.0.97,thenremove r
iv.
If the plant is in MODE 6, then remove power to at least two charging pumps.
0R b.
1.
The primary makeup water flow path to the reactor coolant system shall be isolated and 2.
Do not operate the plant in the configurations prohibited by Tables 3.1-1 through 3.1-5 for the current MODE.
APPLICABILITY:
MODES 3*, 4, 5, and 6.
- While any shutdown CEA is less than 145 inches withdrawn.
ACTION:
With the boron concentration not consistent with required SHUTDOWN a.
MARGIN, initiate emergency boration.
b.
With one boron dilution alarin inoperable and the primary makeup water flow path to the reactor coolant system not isolated, determine reactor coolant system boron concentration within one hour and at least at the monitoring frequency specified in Tables 3.1-1 through 3.1-5.
c.
With both boron dilution alarms inoperable and the primary makeup water flow path to the reactor coolant system not isolated, determine the reactor coolant system boron concentration by two independent means within one hour and at least at the monitoring frequency specified in Tables 3.1-1 through 3.1-5; otherwise, immediately suspend all operations involving positive reactivity changes or CORE ALTERATIONS (if applicable).
WATERFORD - UNIT-3 3/4 1-15 AMENDMENT NO. 9,4,59
REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
(Continued) d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.1.2.9.1 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 from MODE 2.
4.1.2.9.2 Each required boron dilutien alarm shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK nt least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.
4.1.2.9.3 If the primary makeup water flow path to the Reactor Coolant System is isolated to fulfill 3.1.2.9.b, the required primary makeup water flow path l
to the Reactor Coolant System shall be verified to be isolated by either locked closed manual valves, deactivated automatic valves secured in the isolation position, or by power being removed from all charging pumps, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.1.2.9.4 The requirements of Specification 3.1.2.9.a.2 or 3.1.2.9.b.2 shall be l
verified at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.1.2.9.5 Each required boron dilution alarm setpoint shall be adjusted to less than or equal to twice (2x) the existing neutron flux (cps) at the follow-ing f requencies:
a.
At least once per 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> if the reactor has been shut down less than 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />; b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the reactor has been shut down greater than or equal to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> but less than 7 days; At least once per 7 days if the reactor has been shut down greater c.
than or equal to 7 days.
WATERFORD - UNIT 3 3/4 1-16 AMENDMENT NO. 9,48,59
4 I
REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
F ACTION:
(Continued)-
d.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.1.2.9.1 The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 from MODE 2.
4.1.2.9.2 Each required boron dilution alarm shall be demonstrated OPERABLE by the performance of a CHANNEL CHECK at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a CHANNEL FUNCTIONAL TEST at least once per 31 days, and a CHANNEL CALIBRATION at least once per 18 months.
4.1.2.9.3 If the primary makeup water flow path to the Reactor Coolant System is isolated to fulfill 3.1.2.9.b. the required primary makeup water flow path l
to the Reactor Coolant System shall be verified to be isolated by either locked closed manual valves, deactivated automatic valves secured in the isolation position, or by power being removed from all charging pumps, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.1.2.9.4 The requirements of Specification 3.1.2.9.a.2 or 3.1.2.9.b.2 shall be l
verified at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
4.1.2.9.5 Each required boron dilution alarm setpoint shall be adjusted to less than or equal to twice (2x) the existing neutron flux (cps) at the follow-ing frequencies:
a.
At least once per 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> if the reactor has been shut down less than 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />; b.
At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the reactor has been shut down greater than or equal to 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> but less than 7 days; c.
At least once per 7 days if the reactor has been shut down greater than or equal to 7 days.
WATERFORD - UNIT 3 3/4 1-16 AMENDMENT NO. 9,4,59
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