ML20094M240

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Amend 202 to License DPR-68,responding to 950913 Application Re Removal of Requirement to Perform Daily Instrument Checks on Rcics & Hpcis & Correcting Typo
ML20094M240
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 11/13/1995
From: Williams J
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20094M242 List:
References
NUDOCS 9511210340
Download: ML20094M240 (7)


Text

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UNITED STATES j

j NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 2005H001

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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT. UNIT 3 AMENOMENT TO FACILITY OPERATING LICENSE Amendment No. 202 License No. DPR-68 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated September 13, 1995, 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; sp 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 (1) 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 Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

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9511210340 951113 PDR ADOCK 05000296 p

PDR c

s 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-68 is hereby amended to read as follows:

(2) Technical Soecifications The Technical Specifications contained in Appendices A and.8, as revised' through Amendment No. 202, 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 ci its date of issuance and shall be implemented within 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION

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Frederick J. Hebdon, Director Project Directorate II-4 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: Novenber 13, 1995

4 ATTACHMENT TO LICENSE AMENDMENT NO.909 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-221 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. *0verleaf page is provided to maintain document completeness.

REMOVE INSERT 3.2/4.2-45 3.2/4.2-45 3.2/4.2-46 3.2/4.2-46 3.2/4.2-49 3.2/4.2-49 3.2/4.2-49a 3.2/4.2-49a*

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TABLE'4.2.8 (Cont'd)

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cw SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS'

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Function Functional Test Calibration Instrument Check i

Instrument Channel -

(1) once/3 months none RHR Pump Discharge Pressure Instrument Channel -

(1) once/3 months none Core Spray Pump Discharge Pressure Core Spray Sparger to RPV d/p (1) once/3 months once/ day Trip System Bus Power Monitor once/ operating Cycle N/A none Instrument Channel -

(1) once/3 months nene Condensate Header Level (LS-73-56A 8)

Instrument Channel -

(1) cnce/3 months none Suppression Chamber High Level Instrument Channel -

(1)(28) once/18 months (29) once/ day Reactor High Water Level F

(LIS-3-208A-D)

Instrument Channel -

(1)(28) once/18 months (29) none RCIC Turbine Steam Line High Flow a

Instrument Channel -

once/31 days once/18 months none l

RCIC Steam Supply Low Pressure l

Instrument Channel -

once/31 days once/18 months none RCIC Turbine Enhaust Diaphragm g

High Pressure h

RCIC Steam Line Space (1) once/3 months none o

Torus Area h

High Temperature t

RCIC Steam Line Space (1) once/3 months none Z

RCIC Pump Room Area

.O High Temperature o

HPCI Steam Line Space (1) once/3 months none N

Torus Area High Temperature HPCI Steam Line Space (1) once/3 months

.none HPCI Pump Room Area High Temperature

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4 TABLE 4.2.B (Cont'd)

SURVEILLANCE REQUIRENENTS FOR INSTRUMENTATION THAT INITIATE OR CONTROL THE CSCS Function Functional Test Calibration Instrument Check ew ay p

Instrument Channel -

(1)(28) once/18 months-(29) none HPCI Turbine Steam Line High Flow Instrument Channel -

once/31 days once/18 months none l

HPCI Steam Supply Low Pressure Instrument Channel -

once/31 days once/18 months none HPCI Turbine Exhaust Diaphragn l-High Pressure Core Spray System' Logic once/18 months (6)

N/A RCIC System (Initiating) Logic once/18 months N/A N/A RCIC System (Isolation) Logic once/18 months (6)

N/A HPCI System (Initiating) Logic once/18 months (6)

N/A y

HPCI System (Isolatirn) Logic once/18 months (6)

N/A ADS Logic once/18 months (6)

N/A LPCI (Initiating) Logic once/18 months (6)

N/A LPCI (Containment Spray) Logic once/18 months (6)

N/A i

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TABLE 4.2.C SURVEILLANCE REQUIREMENTS FOR INSTRUMENTATION THAT INITIATE R00 BLOCKS y"

Function Functional Test Calibration (17)

Instrument Check rE APRM Upscale (Flow Blas)

(1)

(13).

once/3 months once/ day (8)

APRM Upscale (Startup Mode)

(1)

(13) once/3 months once/ day (8)

APRM Downscale (1)

(13) once/3 months once/ day (8) f APRM Inoperative (1)

(13)

N/A once/ day (8)

RBM Upscale (Flow Blas)

(1)

(13) once/6 months once/ day (8)

RBM Downscale (1)

(13) once/6 months once/ day (8)

RBM Inoperative (1)

(13)

N/A once/ day (8)

IRM Upscale (1)(2)

(13) once/3 months once/ day (8)

IRM Downscale (1)(2)

(13) once/3 months once/ day (8)

IRM Detector Not in Startup Position (2) (once operating cycle) once/ operating cycle (12)

N/A

{

F IRM Inoperative (1)(2)

(13)

N/A N/A w2 SRM Upscale (1)(2)

(13) once/3 months once/ day (8) l SRM Downscale (1)(2)

(13) once/3 months once/ day (8)

SRM Detector Not in Startup Position (2) (once/ operating cycle) once/ operating cycle (12)

N/A SRM Inoperative (1)(2)

(13)

N/A N/A Flow Bias Comparator (1)(15) once/ operating cycle (20)

N/A.

Flow Bias Upscale (1)(15) once/3 months N/A Rod Block Logic (16)

N/A N/A West Scram Discharge once/ quarter once/ operating cycle N/A Tank Water Level High i

(LS-85-45L) i East Scram Discharge once/ quarter once/ operating cycle N/A z

Tank Water Level High

,o (LS-85-45M) ra

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l BFN 3.2/4.2-49a AMENDMENT NO. I 6 9 l

Unit 3 l

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