ML20078P209
| ML20078P209 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/14/1995 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078P213 | List: |
| References | |
| NUDOCS 9502160327 | |
| Download: ML20078P209 (8) | |
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UNITED STATES i
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j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20565-0001
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 189 License No. DPR-68 t
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 29, 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 nill 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 thr' 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.
i 9502160327 950214 PDR ADOCK 05000296 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-68 is hereby i
amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.189, 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 3
(dbm b,;..
Frederick J. Hebdok 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: February 14, 1995 b
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ATTACHMENT TO LICENSE AMENDMENT N0. 189 FACILITY OPERATING LICENSE NO. OPR-68 DOCKET NO. 50-296 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. Overleaf
- pages are provided to maintain document completeness.
REMOVE INSERT 3.9/4.9-5 3.9/4.9-5 3.9/4.9-6 3.9/4.9-6*
3.9/4.9-7 3.9/4.9-7 3.9/4.9-8 3.9/4.9-8*
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3.9/4.9 AUXILIARY RfRCTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEIT.T.AnCE Rf0UI h =15 3.9.A.
Auxiliary Electrical Eauloment 4.9.A.
Aurflia.v Electrical System 3.
Buses mad Boards Available 3.
Loaic Spj;333 a.
The respective start bus a.
Both divisions of the is energized for each accident signal logic common station-service system shall be transformer designated as tested every 18 months an offsite power source, to demonecrate that it will fr/ action on actuacion of the core i
spray system of the reactor to provide an automatic start signal to all 4 dic ci generators.
b.
The 4-kV bus tie board b.
Once every 18 months, is energized if a the condition under cooling tower transformer which the 480-volt load is designated as an shedding logic system offsite power source.
is required shall be simulated to demonstrate that the load shedding logic system would initiate load shedding signals on the diesel auxiliary boards, RMOV boards, and the 480-volt shutdown boards.
c.
The 4-kV shutdown boards (3EA, 3EB, 3EC, 3ED) are energized.
d.
The 480-V shutdown boards 3A and 3B are energized.
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BFN 3.9/4.9-5 I m ndnent No. 189 Unit 3
6.9/4.9 AUTILIARY Rf.RCTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEIT.T AMCE REOUIRErim5 3.9.A.
Auxiliary Electrical Eauipmerl 4.9.A.
Auriliary Electrical System 3.9.A.3. (Cont'd) e.
Loss of voltage and degraded voltage relays OPERABLE on 4-kV shutdown boards 3EA, 3EB, 3EC, and 3ED.
f.
The 480-V diesel auxiliary boards 3EA and 3EB are energized.
g.
The 480-V reactor motor-operated valve (RMOV) boards 3D & 3E are energized with motor-generator (mg) sets 3DN, 3DA, 3EN, and 3EA in service.
4.
The 250-V shutdown board
- 4. Undervoltare Relays 3EB battery, all three unit batteries, a battery a.
(Deleted) charger for each battery, and associated battery b.
Once every 18 months, l
boards are OPERABLE.
the conditions under which the loss of voltage and degraded voltage relays are required shall be simulated with an undervoltage on each shutdown board to demonstrate that the associ ated diesel generator will start.
BFN 3.9/4.9-6 AMENDMENT NO.15 8 Unit 3
3.9/4.9 AUXILIARY RTRCTRICAL SYSTEM LIMITING CONDITIONS FOR OPRDATION SURVEIT.T.AuCE REOUIREMENTS 3.9.A.
Auriliary Electrical Eauin= ant 4.9.A.
Aurfliary Electrical System 4.9.A.4. (Cont'd) i c.
The loss of voltage and degraded voltage relays 1
which start the diesel generators from the 4-kV l
shutdown boards shall be calibrated annually for trip and reset and the measurements logged. These relays shall be calibrated as specified in Table 4.9.A.4.c.
d.
4-kV shutdown board voltages shall be recorded once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
5.
Logic Systems 5.
480-V RMOV Boards 3D and 3E l
a.
Accident signal logic system is OPERABLE, a.
Once per operating cycle, the automatic b.
480-volt load shedding transfer feature logic system is OPERABLE.
for 480-V RMOV boards 3D and 3E shall be functionally tested to verify auto-transfer capability.
6.
There shall be a minimum of 35,280 gallons of diesel fuel in each of the 7-day diesel-generator fuel tank assemblies.
BFN 3.9/4.9-7 Arunxhumit No.189 Unit ?
3.9/4.9 AUXILIARY RLRCTRICAL SYSTEM LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9.B.
Operation with Inocerable 4.9.B.
Operation with Inoverable EauiDaent Eauipment Whenever the reactor is in STARTUP mode or RUN mode and not in a Cold Condition, the availability of electric power shall be as specified in 3.9.A except as specified herein.-
1.
From and after the date
- 1. When only one that only one offsite offsite power source power source is available, is OPERABLE, all unit 3 reactor operation is diesel generators must permissible under this be demonstrated to be condition for seven days.
OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and power availability for the associated boards shall be verified within I hour and at least once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
2.
When one unit 3 diesel
- 2. When one unit 3 diesel generator (3A, 3B, 3C, generator is found to be or 3D) is inoperable, inoperable, all of the continued reactor operation remaining unit 3 diesel is permissible during the generators shall be succeeding 7 days, provided demonstrated to be that two offsite power OPERABLE within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, sources are available as and power availability specified in 3.9.A.l.c.
for the associated boards and all of the CS, RHR shall be verified within (LPCI and containment I hour and at least once cooling) systems, and the per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter.
i remaining three unit 3 diesel generators are OPERABLE.
If this require-ment cannot be met, an orderly shutdown shall be initiated and the reactor shall be shut down and in the Cold Condition within j
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l BFN 3.9/4.9-8 Unit 3 4