ML20137U238
| ML20137U238 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/11/1997 |
| From: | Chandu Patel NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20137U242 | List: |
| References | |
| NUDOCS 9704160329 | |
| Download: ML20137U238 (6) | |
Text
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k UNITED STATES s
j NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 20066-0001 o
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.115 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
1 A.
The application for amendment by Entergy Operations, Inc. (the i
licensee) dated October 16, 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; 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.
9704160329 970411 PDR ADOCK 05000382 P
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2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, j
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 No.125, 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
&&t bf Chandu P. Patel, Project Manager Project Directorate IV-I Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Spectin:ations Date of Issuance
.x,ril 11, 1997
e ATTACHMENT TO LICENSE AMENDMENT NO.125 TO FACILITY OPERATING LICENSE NO. 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 PAGES 3/4 3-12 3/4 3-12 3/4 3-12a 4
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4 i
4
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g TABLE 4.3-1 (Continued)
Og REACTOR PROTECTIVE INSTRUNENTATION SURVEILLANCE REQUIREMENTS 28 CHANNEL MODES FOR MffCH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE c.
5 FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED w
w 13.
Reactor Trip Breakers N.A.
N.A.
M(10),S/U(1) 1, 2, 3*, 4*, 5*
i 14.
Core Protection Calculators S
D(2,4),R(4,5) Q(9),R(6) 1, 2
- 15. CEA Calculators S
R Q,R(6) 1, 2 16.
Reactor Coolant Flow - Low S
R q
1, 2 f
w Yd T
T I-E 32
=s 5
i
.$ P t
i 5
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TABLE 4.3-1 (Continued)
TABLE NOTATIONS
'With the reactor trip breakers in the closed position, the CEA drive i
system capable of CEA withdrawal, and fuel in the reactor vessel.
- The provisions of Specification 4.0.4 are not applicable when l
reducing reactor power to less than 10-4% of RATED THERMAL POWER from l
a reactor power level greater than 10-4% of RATED THERMAL POWER.
Upon reducing power below 10-4% of RATED THERMAL POWER, a CHANNEL FUNCTIONAL TEST shall be performed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if not performed
)
t during the previous 31 days. This requirement does not apply with the reactor trip breakers open.
(1) Each startup or when required with the reactor trip breakers closed and the CEA drive system capable of rod withdrawal, if not performed in the previous 7 days.
(2) Heat balance only (CHANNEL FUNCTIONAL TEST not included):
a.
Between 15% and 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC at AT power, and CPC nL9 ear power signals to the calorimetric calculation.
If any signal is within -0.5% to +10% of the calorimetric calculation, then d2 noi calibrate except as required during initial power ascension following refueling.
If any signal is less than the calorimetric calculation by more than 0.5%, then adjust the affected signal (s) to within 0.0% to
+10.0% of the calorimetric caluclation.
If any signal is greater than the calorimetric calculation by more than 10%, then adjust the affected signal (s) to within 0.0%
to 10% of the calorimetric.
b.
At or above 80% of RATED THERMAL POWER, compare the Linear Power Level, the CPC A T power, and CPC nuclear power signals to the calorimetric calculation.
If any signal differs from the calorimetric calculation by an absolute difference of more than 2%, then adjust the affected signal'.) to agree with the calcrimetric calculation within -2% to +2%.
During PHYSICS TESTS, these daily calibrations may be suspended provided these calibrations are performed upon reaching each major test power plateau and pHor to proceeding to the next major test power plateau.
(3) Above 15% of RATED THERMAL POWER, verify that the linear power sub-channel gains of the excore detectors are consistent with the values used to establish the shape annealing matrix elements in the Core Protection Calculators.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) After each fuel loading and prior to exceeding 70% of RATED THERMAL POWER, the incore detectors shall be used to determine or verify acceptable vaines for the shape annealing matrix elements used in the s
Core Protection Calculators.
WATERFORD - UNIT 3 3/4 3-12 AMENDMENT NO. 69,125
I I&BLE_L 1-1 (Continued)
TABLE NOTATIONS (Continued)
(G) This CHANNEL FUNCTIONAL TEST shall include the injection of simulated j
process signals into the channel as close to the sensors as practicable to verify OPERABILITY including alarm and/or trip i
functions.
i (7) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate i
as indicated by each CPC is less than or equal to the actual RCS total flow rate determined by either usina the reactor coolant pump i
differential pressure instrumentation or by calorimetric calculations i
and if necessary, adjust the CPC addressable constant flow co-efficients such that each CPC indicated flow is less than or equal to the actual flow rate. The flow measurement uncertainty is included l
in the BERR1 term in the CPC and is equal to or greater than 4%.
I (8) Above 70% of RATED THERMAL POWER, verify that the total RCS flow rate i
as indicated by each CPC is less than or equal to the actual RCS l
total flow rate determined by calorimetric calculations.
l (9) The quarterly CHANNEL FUNCTIONAL TEST shall include verification that t
the correct values of addressable constants are installed in ehch j
l l
(10) At least once per 18 months and following maintenance or adjustment of the reactor trip breakers, the CHANNEL FUNCTIONAL TEST shall include independent verification of the undervoltage trip function i
j and the shunt trip function.
I 4
/
WATERFORD - UNIT 3 3/4 3-12a AMENDMENT NO.125 l