ML20077E046
| ML20077E046 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/07/1994 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20077E050 | List: |
| References | |
| NUDOCS 9412120076 | |
| Download: ML20077E046 (9) | |
Text
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NUCLEAR REGULATORY COMMISSION
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WASHINOTON, D.C. 20555-0001 TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-260 BROWNS FERRY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.228 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 11, 1994, 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.
9412120076 941207 PDR ADOCK 05000260 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. 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. 228, 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 anc shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSIOl s
Frederick J. Heb@ n, 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:
December 7, 1994 t
ATTACHMENT TO LICENSE AMENDMENT NO. 77a FACILITY OPERATING LICENSE NO. DPR-52 DOCKET N0. 50-260 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are i
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 3.9/4.9-5 3.9/4.9-5*
i 3.9/4.9-6 3.9/4.9-6 3.9/4.9-10a 3.9/4.9-10b 3.9/4.9-11 3.9/4.9-11 3.9/4.9-12 3.9/4.9-12*
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s 3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.A.
Auxiliary Electrical Eautoment 4.9.A.
Auxiliary Electrical Systga 3.
Buses and Boards Available 3.
Logic Systems a.
The respective start bus a.
Both divisions of the is energized for each common accident signal common station-service logic system shall be transformer designated as tested every 18 months l
an offsite power source, to demonstrate that it will function on actuation of the core spray system of each reactor to provide an automatic start signal to all 4 units 1 and 2 diesel generators.
b.
The 4-kV bus tie board b.
Once every 18 months, l
is energized and capable the condition under of supplying power to the whic1. the 480-volt load unita 1 and 2 shutdown shedding logic system boards if a cooling tower is required shall be transformer is designated simulated using pendant as an offsite power source.
test switches and/or pushbutton test switches to demonstrate that the load shedding logic system would initiate load shedding signals on the diesel auxiliary boards, RMOV boards, and the 480-V shutdown boards.
c.
The units 1 and 2 4-kV shutdown boards are energized.
BFN 3.9/4.9-5 AMENDMENT NO.19 9 Unit 2
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3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEII.T AMCE REOUIREMENTS 3.9.A.
Auxiliary Electrical Eautoment 4.9.A.
Auxiliary Electrical System j
i 3.9.A.3. (Cont'd) d.
The 480-V shutdown boards 2A and 2B are energized.
e.
The unita 1 and 2 diesel auxiliary boards are energized.
f.
Loss of voltage and degraded voltage relays OPERABLE on 4-kV shutdown boards A, B, C, and D.
g.
Shutdown buses 1 and 2 energized.
h.
The 480-V reactor motor-operated valve (RMOV) boards 2D & 2E are energized with motor-generator (mg) sets 2DN, 2DA, 2EN, and 2EA in service.
4.
The three 250-V unit batteries, 4.
Undervoltage Relays the four shutdown board batteries, a battery charger a.
(Deleted) f for each battery, and associated battery boards are b.
Once every 18' months, l
OPERABLE.*
the conditions under which the loss of voltage and degraded voltage i
relays are required shall be simulated with an undervoltage on each shutdown board to demonstrate that the associated diesel generator will start.
- Except as specified in 3.9.B.8.c on page 3.9/4.9-10a from January 1,1995, to December 31, 1995.
BFN 3.9/4.9-6 NERDIENT NO. 228 Unit 2
3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.B Ooeration With Inocerable Equipment L
- 8. From and after the date that one of the 250-V shutdown board batteries and/or its associated battery board is found to be inoperable for any reason, continued REACTOR POWER OPERATION is permissible during the succeeding five days in accordance t
with 3.9.B.7 except as noted in 3.9.B.8.a, b, and e below:
a.
For the purpose of shutdown board battery and component i
replacement only, REACTOR POWER OPERATION is j
permissible for the succeeding forty-five (45) days providing:
1.
Only one of the shutdown board batteries and associated components is being replaced at a time.
2.
All components normally supplied from the shutdown board battery which is being replaced are fed from its alternate source.
3.
Unita 1 and 3 are defueled.
b.
NRC notification for 3.9.B.7 is not required for shutdown board battery and component replacement.
c.
Resumption of REACTOR POWER OPERATION is permissible following a shutdown while shutdown board battery and component replacements are in progress.
- From January 1, 1995, to December 31, 1995, the provisions of Specification 3.9 B.8 on this page will apply while modifications are being performed on the shutdown board batteries and/or their associated battery boards.
BFN 3.9/4.9-10a A}E2HXH20E NO. 228 Unit 2
i THIS PAGE INTENTIONALLY LEFT BLANK l
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l BFN 3.9/4.9-10b NIFilDlIFJTT NO. 228 Unit 2 i
3.9/4.9 AUXILIARY ELECTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEIu AMCE REOUIREMElfrS 3.'9.B Operation With Inonerable Eauipment a
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- 8.
From and after the date that one of the 250-V shutdown board batteries and/or its associated battery board is found to be INOPERABLE for any reason, continued REACTOR POWER _0PERATION is permissible during the succeeding five days in accordance with 3.9.B.7.
9.
When one division of the logic system is INOPERABLE, continued REACTOR POWER OPERATION is permissible under this condition for seven days, provided the CSCS requirements listed in Specification 3.9.B.3 are satisfied. The NRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or' the situation, the precautions to be taken during this period, and the plans to return the failed component to an OPERABLE state.
10.
(deleted) 11.
The following limiting conditions for operation exist for the undervoltage relays which start the diesel generators on the 4-kV shutdown boards.
From January 1, 1995, to December 31, 1995, the provicions of Specification 3.9.B.8 on page 3.9/4.9-10a will apply while modifications are being performed on the shutdown board batteries and/or their associated battery boards.
BFN 3.9/4.9-11 Unit 2 t
2,9/4.9 AUXILIARY ELECTRICAL SYSTFM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.B.
Operation With Inocerable Eauipment 3.9.B.11 (Cont'd) a.
The loss of voltage relay channel which starts the diesel generator for a complete loss of voltage on a 4-kV shutdown board may be INOPERABLE for 10 days provided the degraded voltage relay channel on that shutdown board is OPERABLE (within the surveillance schedule of 4.9.A.4.b).
b.
The degraded voltage relay channel which starts the diesel generator for degraded voltage on a 4-kV shutdown board may be INOPERABLE for 10 days provided the loss of voltage relay channel on that shutdown board is OPERABLE (within the surveillance schedule of 4.9.A.4.b).
c.
One of the three phase-to-phase degraded voltage j
relays provided to 1
detect a degraded voltage on a 4-kV l
shutdown board may be INOPERABLE for 15 days provided both of the following conditions are satisfied.
BFN 3.9/4.9-12 Unit 2