ML20065P923
| ML20065P923 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/10/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20065P925 | List: |
| References | |
| NUDOCS 9012140140 | |
| Download: ML20065P923 (10) | |
Text
. - - - _ -
[(
fo UNITED STATES
+
g l
g NUCLEAR REGULATORY COMMISSION l-W ASHINGTON, D. C. 20555 l
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-250 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.180 License No. DPR-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 24, 1990 as supplemented September 17, 1990, 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 satisf %d.
l 9012140140 901210 PDR ADOCK 05000260 p
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4 i
., -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. DPR-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.180, are hereby incorporated in the
. license.- The licensee shall operate the facility. in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION f k f
-Frederick J. HeMon, Director Project Directorate 11-4, NRR Division of Reactor Projects - 1/II Office of Nuclear Reactor. Regulation-
Attachment:
Changes to the Technical Specifications-Date of issuance: December 10, 1990 l
4 4
ATTACHMENT TO LICENSE AMENDMENT NO.180 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised paget are identified by the captioned amendment number and contain marginal lines indicating the area of change.
Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.2/4.2-16 3.2/4.2-16 3.2/4.2-17 3.2/4.2-17*
3.2/4.2-40 3.2/4.2-40 3.2/4.2-41 3.2/4.2-41*
3.2/4.2-44 3.2/4.2-44*
3.2/4.2-45 3.2/4.2-45 3.2/4.2-61 3.2/4.2-61
~
3.2/4.2-61a 3.2/4.2-61a
i TABLE 3.2.8 (Continued)
CM Minimue No.
4 i
- dE Operable Per Trio Sys(11 Function Trio Level Settino Action Remarks u
2 Instrument Channel 450 psig 2 15 A
1.
Below trip setting permissive Reactor Low Pressure (PIS-3-74 A & B)
admission valves.
(PIS-68-95, % ).
2 Instrument Channel -
230 psig 2 15
.A 1.
Recirculation discharge valve Reactor low Pressure actuation.
(PS-3-74 A & B)
(PS-68-95. %)
2 Core Spray Auto Sequencing 61 t 18 sec.
B 1.
With diesel power
{-
2 Timers (5) 2.
One per motor 2
LPCI Auto Sequencing 01 t 11 sec.
B 1.
With diesel power Timers (5) 2.
One per motor b
1 RHR$W A1, B3,'C1 and D3 131 t 115 sec.
A 1.
With diesel power Timers 2.
One per pug l
7 2
Core Spray and LPCI Auto 01 t il sec.
3 1
With normal power i
Sequencing Timers (6) 61 t 18 sec.
2.
One per CSS motor 121 t 116 sec.
3.
Two per RHR motor 181 t 124 sec.
t 1
RHP.SW A1, B3, C1 and D3 271 t i 29 sec.
A 1.
With normal power 4
j Timers 2.
One per pump i
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s TABLE 3.2.8 (Continued)
EE Minimum No.
p2 Operable Per Trio Svsf11 Function Trio tevel Settino Action Remarks w
1(16)
ADS Timer 105 sec 7
A 1.
Above trip setting in 1
conjunction with low reactor water level permissive, low reactor water level drywell pressure or, high high drywell pressure a
bypass timer timed out.
- and RHR or CSS pumps running, initiates ADS.
1(16)
ADS Timer (121/2 min.)
12 1/2 min.
2 A
- i. Above trip setting, in (High Drywell Pressure Bypass Timer) conjunction with low reactor water level permissive. Iow reactor water level 105 sec.
delay timer, and RHR or CSS pumps running, initiates ADS.
w 2
Instrument Channel -
100 10 psig A
1.
Below trip setting defers ADS 2
.RHR Discharge Pressure actuation.
7 2
Instrument Channel 185 2 0 psig A
1.
Below trip setting defers ADS 1
CSS Pump Discharge Pressure actuation.
1(3)
Core Spray Sparger to 2 psid 014 A
1.
Alarm to detect core sparger Reactor Pressure Vessel d/p pipe break.
RHR (LPCI) Trip System bus N/A C
1.
Monitors availability of power monitor power to logic systems.
1 1
Core Spray Trip System bus N/A C
1.
Monitors availability of power monitor power to logic systems.
1 ADS Trip System bus power N/A C
1.
Monitors availability of 9
^
monitor power to logic systems i
and valves.
?.S c,
t M
i
.O M
j C) to 3
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TABLE 4.2.A E$
SURVEILLANCE REQUIREMENTS FOR PRIMARY CONTAINMENT AND REACT @ BUILDING ISOLATION INSTRUMENTATION Function Functional Test Celibration Frecuency Instrument Check w
Instrument Channel -
(1) (27)
Once/18 Months (28)
Once/ day Reactor Low Water Level (LIS-3-203A-0)
Instrument Channel -
(31)
Once/18 months None Reactor High Pressure (PS-68-93 & 94)
Instrument Channel -
(1) (27)
Once/18 months (28)
Once/ day Reactor Low Water Level (LIS-3-56A-D)
Instrument Channel -
(1) (27)
Once/18 Months (28)
N/A High Drywell Pressure Id (PIS-64-56A-D) h Instrument Channel -
29 (5)
Once/ day High Radiation Main Steam 13 Line Tunnel n
CD Instrument Channel -
(29) (27)
Once/18 Months (28)
None Low Pressure Main Steam Line (PIS-1-72, 76, 82, 86)
Instrument Channel -
(29) (27)
Once/18 Months (28)
Once/ day High Flow Main Steae Line 1
(PdIS-1-13A-D 25A-D, 36A-0. SOA-D) 8 3-O
mumum
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l TABLE 4.2.A (Cont'd)
SURVEILLANCE REQUIREMENTS FOR PRIMARY CONTAINMENT AND REACTOR BUILDING ISOLATION INSTRtP8ENTATION hE Function Functional Test Calibration Frecuency Instrument Check w
Instrument Channel -
Once/3 months (27)
Once/cperating cycle None Main Steam Line Tunnel High Temperature Instrument Channel -
(1) (22)
Once/3 months Once/ day (8)
Reactor Building Ventilation High Radiation - Reactor Zone Instrument Channel -
(1) (22)
Once/3 Honths Once/ day (8)
Reactor Building Ventilation High Radiation - Refueling Zone Instrument Channel -
(4)
(9)
N/A SGTS Train A Heaters Instrument Channel -
(4)
(9)
N/A y
SGTS Train B Heaters Instrument Channel -
(4)
(9)
N/A j
SGTS Train C Heaters Reactor Building Isolation (4)
Once/ operating cycle N/A Timer (refueling floor)
Reactor Building Isolation (4)
Once/ operating cycle N/A Timer (reactor zone)
I
,,,s s=3 2
.O N
A CC
TABLE 4.2.8 SURVEILLANCE REQUIREMENTS FDR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS C: cp
$2 Function Functional Test Calibration Instrument Check 7
to Instrument Channel (1) (27)
Once/18 Months (28)
Once/ day Reactor Low Water Level (LIS-3-SEA-D)
Instrument Channel (1) (27)
Once/18 Months (28)
Once/ day Reactor Low Water Level (LIS-3-184 & 185)
Instrument Channel (1) (27)
Once/18 Months (28)
Once/ day Reactor Low Water Level (LIS-3-52 & 62A)
Instrument Channel (1) (27)
Once/18 Months (28) none Drywell High Pressure (PIS-64-58E-H)
I" Instrument Channel (1) (27)
Once/18 Months (28) none R3 Drywell High Pressure
.d (PIS-64-58A-D) 9#
Instrument Channel (1) (27)
Once/18 Months (28) none 7
Drywell High Pressure (PIS-64-57A-0)
Instrument Channel (1) (27)
Once/6 Months
- 28) none Reactor Low Pressure
( PIS-3-74A A. PS-3-74A&B)
(PIS-68-95, PS-58-95)
(PIS-68-%, PS-68 96) 2=
I CD EI ES en Ei
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$3 84 CD 9
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i TABLE 4.2.B (Continued)
SURVEILUUICE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS -
E$
Function Functional Test Calibration Instrument Check M.
Core Spray Auto Sequencing
_(4)
Once/ operating cycle none Tiners (Normal Po ver) i Core Spray Auto Sequencing (4)
Once/ operating cycle none-r Timers (Diesel' Power)
LPCI Auto Sequencing Timers (4).
Once/ operating cycle none (Norwal Power) t f
LPCI Auto Sequencing Timers (4)
Once/ operating cycle none (Diesel Pcwer)
RHRSW A1. 83. C1. D3 Tiners (4)
Once/ operating e.vele (Normal Power) none RHRSW A1.'B3 C1.-D3 Timers (4)
Once/ operating cycle none y
(Diesel Power)
ADS Timer (105 sec.)
(4)
Once/ operating cycle none ADS Timer (121/2 min.)
(4)
N 1
(High Drywell Pressure Bypass Once/ operating cycle none v
Timer)
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4-TNis PACE INTENTIONALLY ley ~y gLgyg BPN 3.2/4.2-61a Unit 2 Amendment 180