ML20070K782
| ML20070K782 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 03/15/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070K785 | List: |
| References | |
| NUDOCS 9103190152 | |
| Download: ML20070K782 (7) | |
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3 Mf'+ t UNITED STATES i
NUCLEAR REGULATORY COMMISSION
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o WASHINoToN. o.C. 20666 y-ENTERGY OPERATIONS, INC.
DOCKET NO. 50-382 WATERFORO STEAM ELECTRIC STATION, UNIT 3 AMEN 0 MENT TO FACILITY OPERATlHG LICENSE Amendment Noi 67 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 July 25, 1990, complies with the standards and requirements of the Atomic Energy Act of_1954, as amer:ded (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.
l 9103190152 910315" ADOCK0500g2 PDR P
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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 No. 67, 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.
FOR THE NUCLEAR REGULATORY COMMISSION jtorLw M., tty _
Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects III, IV, and V Of fice of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 15,1991 i
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l-ATTACHMENT TO LICENSE AMENDMENT NO. 67 l
TO FACILITY OPERATING LICENSE NO. NPF-38 00CKET NO. 50-382 l
Replace the following pages of the Appendix A Technical Specifications _with the atteched pages.
The revised pages are. identified by Amendment number and contein vertical lines indicating the areas of change. The corresponding overleaf pages l
ore also provided to maintain document completeness.
l REMOVE PAGES INSERT PAGES 3/4 3-25 3/4 ?-25 3/4 3-27 3/4 3-27 i
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r jE TABLE 4.3-2 G4 i
5 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTAION SURVEILLANCE RrQUIREMENTS E$
1 C'
4 CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE Si FUNCTIONAL UNIT.
CHECK CALIBRATION TEST IS REQUIRED i
II 1.
SAFETY INJECTION (SIAS)
_ to a.
Manual (Trip Buttons)
N.A.
N.A.
R 1,2,3,4 b.
Containment Pressure - High 5
R M
1,2,3 c.
Pressurizer Pressure - Low 5
R M
1,2,3 i
i d.
Automatic Actuation Logic N.A.
N. A.
M(2) (3) (6) 1, 2, 3 l
{
2.
CONTAINMENT SPRAY (CSAS) a.
Manual (Trip Buttons)
N.A.
N.A.
R 1,2,3,4 to b.
Containment' Pressure --
l High.- High S
R M
1, 2, 3
.43 c.
Automatic Actuation Logic
'N.A.
N.A.
M(1) (2) (3) 1, 2, 3
)
n.>
ui 3.
, CONTAINMENT ISOLATION (CIAS) i a.
Manual.CIAS (Trip Buttons)
N.A.
N.A.
R 1,2,3,4
~
b.
Containment' Pressure - High S
R M
1,2,3 c.
Pressurizer Pressure - Low S
R M
1,2,3 i
. d.
Automatic Actuation Logic.
N.A.
N.A.
M(1) (2) (3) 1, 2, 3 i
4.
MAIN STEAM LINE ISOLATION a.
Manual (Trip Buttons)
N.A.
N.A.
R 1, 2, 3
' b'.
Steam Generator Pressure Low S R
M 1, 2, 3 c.
Containment Pressure - High S
R M
1,2,3 1
d.
Automatic Actuation Logic-N.A.
N.A.
M(1) (2) (3) 1, 2, 3
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9 BE 52 e
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TABLE 4.3-2 (Continued)
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>gj ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVElttANCE REQUIREMENTS
%j; CHANNEL MODES FOR WHICH 3
t)
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE
}
FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED i
i
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t3 5.
SAFETY INJECTION SYSTEM RECIRCULATION (RAS) a.
Manual RAS (Trip Buttons)
N.A.
N.A.
R 1, 2, 3, 4 b.
Refueling Water Storage i
t Pool -' Low S'
R M
1, 2, 3, 4
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c.
Automatic-Actuation Logic N.A.
N.A.
M(1) (2) (3) 1, 2, 3, 4 d
i 6.
LOSS OF POWER (LOV) i, a.
4.16 kV Emergency Bus
'{
Undervoltage (Loss of i
Voltage)
N.A.
R D(4) 1, 2, 3
{
b.
480 V Emergency Bus
'Undervoltage (loss of j
g, Voltage)
N.A.
R D(4) 1, 2, 3
. cs c.
'4.16 kV Emergency. Bus
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Undervoltage (Degraded I
i Voltage)
N.A.
R D(4) 1, 2, 3 l
5-4 i
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e jE TABLE 4.3.-2 (Continued)
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ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 55 CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE gj FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED Z
7.
EMERGENCY FEEDWATER (EFAS) l to a.
Manual (Trip Buttons)
N.A.
N.A.
R 1,2,3 b.
SG Level (1/2)-Low and AP (1/2) - High 5
R M
1, 2, 3 c.
SG Level (1/2) - Low and No Pressure - Low Trip (1/2)
S R
M 1,2,3 d.
Automatic Actuation Logic N.A.
N.A.
M(1) (2) (3) 1, 2, 3 e.
Control Valve Logic 5
R SA(5) 1, 2, 3 (Wide Range SG Level - Low) u, k
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TABLE NOTATION I
-(1) Each train or logic channel'shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(2) Testing of Automatic Actuation Logic shall include energization/deenergization of each initiation relay and verification of the OPERABILITY of each initiation relay.
i (3) A subgroup relay test shall be performed which shall include the energization/deenergization of each s
subgroup relay and verification of the OPERABILITY of each subgroup relay.
Relays K109, K114, K202, gg K301, K305, K308 and K313 are exempt from testing during pcuer operation but shall be tested at least 3
gj once per 18 months and during each COLD SHUTDOWN condition unless tested within the previous 62 days.
l t
z (4) Using installed test switches.
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.(5) To be performed during es;n COLD SHUTDOWN if not performed in the previous 6 months.
E3 I
(6) Each' train shall be tested, with the exemption of relays, K110, K410 and K412, at least every 62 days on a STAGGERED' TEST BASIS.
Relays K110 K410 and K412 shall be tested a'-
least every 62 days but will be exempt from the STAGGERED TEST BASIS.
4
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INSTRUMENTATION 3/4.3.3 MONITORING INjTD.UMENTATION RADIATION MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation mor,itoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alarm / trip setpoints within the specified limits.
APPLICABILITY:
As shown in Table 3.3-6.
ACTION:
With a radiation monitoring channel alarm / trip sctpoint exceeding a.
the value shown in Table 3.3-6, adjust the setpoint to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable, b.
With one or more radiation monitoring channels inoperable, take the ACTION shown in Table 3.3-6.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
c.
SURVEILLANCE REQUIREMENTS 4.3.3.1 iach radiation monitoring instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-3.
WATERFORD - UNIl 3 3/4 3-28