ML20116M251
| ML20116M251 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/09/1992 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20116M252 | List: |
| References | |
| NUDOCS 9211200159 | |
| Download: ML20116M251 (7) | |
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NUCLEAR REGULATORY COMMISSION
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DLT.f.RGY OPERATIONS. It!C.
LOCKET No. 50-382 WATERFORD STEAM ELECTRIC STATION. UNIT 3 MDfDMENT TO FACILITY OPERATING LIGiti}E Amendment No. 78 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 October 11, 1991, as supplemented by letters dated December 18, 1991, and August 27, 1992, complies with
- ndards and requirements of the Atomic Energy Act of 1954, as.
d (the Act), and the Commission's rules and regulations set for u in 10 CFR Chapter 1; D.
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 (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the pu'olic, 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 defence 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) 1.tchnical Sracifications and Environmental Protection Pign The Technical Specifications contained in Appendix A, as revised through Amendment No. 78, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the licerse.
The licensee shall operate the f4cility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is offective as of its date of issuance.
FOR THE NUCLLAR REGULATOP.Y COMMISSION W
g John T. Larkins, Director Project Directorate IV-1 Division of Rer.ctor Projects Ill/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
November 9, 1992
8 4
9 ATTACHMENT TO LICENSE AMENDMENLNO, 78 ID.fAtlllTY OPERATING LICENSE NO. NPF-38 00LKET NO. 50-182 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 page is also provided to maintain document completeness.
REMOVE PAGES INSERT PAGES i
3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26 3/4 3-27 3/4 3-27 t
l l
l
k TABLE 4.3-2 j
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTAION SURVEILLANCE REQUIREMENTS g..
- o-CHANNEL MODES FOR VHICH 7'
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED l
z l
Z ; 1.
SAFETY INJECTION (SIAS) to a.
Manual (Trip Buttons)
N.A.
N.A.
R 1,2,3,4 b.
Containment Pressure - High S
R Q
1, 2, 3
- c..
Pressurizer Pressure - Low 5
R Q
1, 2, 3 d.
Automatic Actuation Logic
'except subgroup relays).
N.A.
N.A.
Q(2) 1, 2, 3
- tuation Subgroup Relays N.A.
M.A.
M(3) (6) 1, 2, 3 2.
CONTAINMENT SPRAY _(CSAS) a.
Manual (Trip Buttons)
N.A.
N.A.
R I, 2, 3, 4 b.
Containment Pres ure --
.R High - High S
R Q
1, 2, 3 c.
Automatic Actuation Logic
'f
,(except subgroup relays)
N.A.
N.A.
Q(2) 1, 2, 3
~. E?,
Actuation Subgroup Relays N.A.
N.A.
M(1) (3) 1, 2, 3 l
3.
CONTAINMENT ISOLATION (CIAS) a.
Manual CIAS (Trip Buttons)
N.A.
N.A.
R 1, 2, 3, 4 b.
Containment Pressure - High.
5 R
Q 1,2,3 c.
Pressurizer Pressure - Low S
R Q
1, 2, 3 d.
. Automatic Actuation Logic l
(except. subgroup relays)
N. A.
N.A.
Q(2.)
1, 2, 3 g
Actuation Tubgroup Relays N.A.
N. A.
M(1) (3) 1, 2, 3 i
z SE. 4.
MAIN STEAM LINE ISOLATION 9
- a. -
Manual (Trip Buttons)
N.A.
N.A.
R 1, 2, 3 b.
Steam Generator Pressure - Low S R
Q-1,2,3 5
c..
- Containment Pressure - High 5
R
-Q 1,2,3
~
d.
Automatic Actuation Logic 4
(except subgroup relays).
N.A.
M.A.
Q(2) 1, 2, 3
~
Actuation Subgroup Relays N. A. -
N.A.
M(1) (3) 1, 2, 3 I
- w
t
,c.
TABLE 4.3-2-(Continued)
.%-9 ENGINEERED SAFETY FEATURES ACTUATIGN SYSTEM INSTRLNENTATION SURVEILLANCE REQUIREMENTS
-: g B.
CHANNEL NODES FOR WHICH CHANNEL C".ANNEL FUNCTIONAL SURVEILLANCE l
' FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED
. c.
z.
'~. 5.
SAFETY INJECTION SYSTEM I
RECIRCULATION'(RAS)
.a.
%nual RAS (Trip Buttons)
N.A.
N.A.
R 1, 2, 3, 4 b.
Refueling Water Storage.
Pool - Low 5
R Q
1,2,3,4
' c.
Automatic Actuation Logic-(except subgroup relays)
N.A.
N.A.
Q(2) 1, 2, 3 l
' Actuation Subgroup Relays N.A.
N.A.
N(1) (3) 1, 2, 3 l
6.:
LOSS ~0F POWER (LOV)'
w 4.16'kV Emergency Bus
[
a.-
Y Undervoltage (Loss of~
[
Voltage)
N.A.
R D(4) 1, 2, 3 w4 b.
480 V Emergency Eus Undervoltage (Loss of Voltage)
N.A.
R D(4) 1,2,3
.c.
'4.16 kV Emergency. Bus Undervoltage (Degraded Voltage)
N.A.
R D(4) 1, 2, 3 m
+
TABLE 4.3.-2 (Continued) 2-ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS c'
CHANNEL MODES FOR W'ilCH
- =
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE
[
FUNCTIONAL UNIT CHECK CALIBRATION
_ TEST IS REQUIRED 7.
EMERGENCY FEEDWATER (EFAS) w a.
Mancal (Trip Buttons)
N.A.
N. A.
R 1, 2, 3 b.
SG Level (1/2)-Low and AP (1/2) - High 5
R Q
1, 2, 3 c.
SG Level (1/2) - Low and No Pressure - Low Trip (1/2)
S R
Q 1, 2, 3 d.
Automatic Actuation Logic (except subgroup relays)
N.A.
N.A.
Q(2) 1, 2, 3 Actuation Sitgroup Relays N.A.
N.A.
M(1) (3)
I, 2, 3 e.
Control Valve Logic 5
R SA(:i) 1, 2, 3 (Wide Ra',e CG Level - Low) l k
Y Z
TABLE NOTATION (1) Each train or logic channel shall be tested at least every 62 days cn a STAGGERED TEST BASIS.
Tescing of Automatic Actuation Lol c shall include energization/deenergization of each initiation relay i
(2) and verif',' cation of the OPERABILIN of each initiation relay.
A subgroup relay test shall be peeformed which shall include the energizatfori/deenergization of each 3 (3) subgmup relay and verification of the OPERABILITY of each subgroup relay.
Relays K109, K114, K202, 9
K301, K305, X308 and K313 are exampt from testing during power operation but shall be tested at least
{
once per 18 months anti during each COLD SHUTCCWN condition unless tested within tae previous 62 days.
z
] (4) Using installed test switches.
O (5) To ~0e perforced during each COLD SHUTUOWN if not perforred in the previous 6 months.
(6) Each train shall be tested, with the exeription of relays, K110, K410 and K412, at least
~
E every 62 days on a STAGGERED TES7 BASIS.
Relays K110, K410 and K412 shall be tested at least every 62 days but will be exempt from the STAGGERED TEST BASIS.
y co
]NSTRUMRN1AT10N 3/4.3.3 MONITORING INSTRUMENTATION RAD]AT]ON MONITOR:NG INSTRL' MENTATION LIMITING CONDITION FOR OPERATION 4
l 3.3.3.1 1he radiation monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE with their alare/ trip setpoints within the specified limits.
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APPL]CABILITY:
As shown in Table 3.3-6.
i ACTl04:
i I
With a radiation monitoring char.nel alarm / trip setpoint exceeding a.
the value shown in Table 3-.3-6, adjust the setpoint to within the linit 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.
l i
b.
With one or more radiation monitoring channels inoperable, take the ACT10h sho.n in Table 3.3-6.
The provisions of Sp?cifications 3.0.3 and 3.0.4 are not applicable.
C.
SURi!!;LAN:[ R[QUIR[M!NTS 4.3.3.1 lath raciation monitoring instrumentation channel sht11 be-ce*:astratec OPERABLE by the performance of the CHANNEL CHECK, CHANNEL Cht1 ERA 7]DS anc CHANNEL FUNCTIONAL TEST operations for th MODES and at the.
fre:ve,:ies shown in Table 4.3 3.
WA7ERTORD - UNIT 3 3/4 3 26 n
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