ML18030B015
| ML18030B015 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 01/13/1986 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18030B016 | List: |
| References | |
| DPR-33-A-126, DPR-52-A-121, DPR-68-A-097 NUDOCS 8601220392 | |
| Download: ML18030B015 (21) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 126 License No.
DPR-33 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 5, 1985, 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 inim'ical 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.
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-33 is hereby amended to read as follows:
seOi22OS92 BSOlSS i
PDR ADOCK 05000259 P
PDR t,
(2)
Techni ca 1 S eci ficati ons
-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 126, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 13, 1986 Daniel R. Muller, Director BWR Project Directorate b2 Division of BWR Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
FACILITY OPERATING LICENSE NO.
DPR-33 DOCKET NO. 50-259 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
52, 76, 285 2.
The marginal lines on these pages denote the areas being changed.
'LLGTING CONDITIONS FOR OPERATTON SURVEILLANCE REOUIR~NTS 3.2.D Off-QlIlkf~I?S (b) Prom and after the date that one of the two offgas post treatment radiation monitors is made or found to be inop-
- erable, continued reactor power operation is permissible during the next seven days, provided that the inoperable monitor is tripped in the downscale pos-ition.
One radiation monitor may be out of service for four hours for functional test and/
or calibration without the monitor being in a downscale tripped condition.
Both moni-tors may be taken out of service for less than one hour for purging of monitors during SI performance.
- 4. 2.D f-.a~
Isolation Function (c) Upon the loss of both off-gas post treatment radiation moni-tors, initiate an orderly shut-down and shut the mainsteam isolation valves or the off-gas isolation valve within 10 hrs.
Purging during SI performance is not considered a loss of monitoring capability.
E. Dr ell Leak Detection The limiting conditions of operation for the instrumentation that monit-ors drywell leak detection, are given in Table 3.2.E.
E. Dr ell Leak Detection Instiumentation shall be calibrated and checked as indicated in Table 4.2.E.
F. Surveillance Instrumentation The limiting conditions for the instrumentation that provides sur-veillance information readouts are given in Table 3.2.P.
F. Surveillance Instrumentation Instrumentation shall be cal-ibrated and checked as indic-ated in Table 4.2.7.
Control Room Isolation The limiting conditions for instru-mentation that isolates the control room and initiates the control room emergency pressurization systems are given in Table 3.2.G.
G. Control Room Isolation Instrumentation shall be calibrated and checked as in-dicated in Table 4.2.G.
Amendment No. 126 52
TABLE 3 ~ 2.D OFF-GAS POST TREATHENT ISOLATION INSTRUHENTATION I
f Hin. No.
2 O
- 1) (4)
Function Off-Gas Post Treatment lionitor Tri Level Set tin Note 3 Action(2) Remarks AorB l.
2 upscales, or 1 downscale and 1 upscale, or 2 down-scales will isolate off-gas line.
Off Gas Post Treatment Isolation Note 3 1.
One trip system with auto transfer to another source Nates:
Whenever the minimum number operable cannot be met the indicat d
ti h ll b L l.
c e
ac on s a
be taken.
Purging during SI performance is not considered a loss of monitoring capabilitty.
2.
Action A.
Refer to Rection 3.2.D.l.b B.
Refer to Section 3.2.D.l.c 3.
Trip setting to correspond to Specification 3.2.D.l.a
0
LIMIT1NG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 8.
Radioactive gases released from each unit's turbine and reactor. building roof vents, the radwaste building roof vents, and the main stack shall bc coaeinuously monitored.
To accomplish this, at least one reactor building and one turbine building vent monitoring system per unit shall be operating whenever that unit's building ventilation system is in service.
Also, one radwaste building system vent monitoring channel shall be operating whenever the radwaste ventilation system is in service.
At least one main stack monitoring channel shall be operating whenever any unit's air e)ector, mechanical vacuum pump, or a standby gas treatment system train is in service.
If normal monitoring systems are not available, temporary monitors or other systems shall be used to monitor effluent.
A monitoring channel may be out-of-service for 4, hours for functional testing and calibration without providing a temporary monitor.
Both, stack monitors may be taken out-of-service for less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for purging of monitors during SI performance.
4.8.8 Airborne Effluents IE these requirements are not satisfied for the stack or radwaste
- monitor, the reactors shall be in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the stack and 10 days for the radwaste vent.
Purging during SI performance is not considered a loss of= monitoring capability.
If these requirements are not satisfied for the reactor and turbine building vents, the affected reactor shall be in hot shutdown condition within 10 days.
Amendment No. 126 285
'ISREcu P0 I
O UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. l21 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 August 5, 1985, 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 inim'ical 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.
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 S ecifications
-The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 121, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 13, 1986 Daniel R. Muller, Director BWR Project Directorate P2 Division of BWR Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
121 FACILITY OPERATING LICENSE NO.
DPR-52 DOCKET NO. 50-260 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
52, 76, 285 2.
The marginal lines on these pages denote the areas being changed.
LLMTING CONDITIONS FOR OPERATION SURVEILLANCE REOUI~NTS 3.2.D ff-Bu~~
(b) 'From and after the date that one of the two offgas post treatment radiation monitors is made or found to be inop-
- erable, continued reactor power operation's permissible during the next seven
- days, provided that the inoperable monitor is tripped in the downscale pos-ition.
One radiation monitor may be out of service for four hours for functional test and/
or calibration without the monitor being in a downscale tripped condition.
Both moni-tors may be taken out of service for less than one hour for purging of monitors during SI performance.
4.2.D H'- a Isolation Function (c) Upon the loss of both off-gas post treatment radiation moni-tors, initiate an orderly shut-down and shut the mainsteam isolation valves or the off-gas isolation valve within 10 hrs.
Purging during, SI performance is not considered a loss of monitoring capability.
E; Dr ell Leak Detection The limiting conditions of operation for the instrumentation that monit-ors drywell leak detection are given in Table 3.2.E.
E. Dr ell Leak Detection Instr'umentation shall be calibrated and checked as indicated in Table 4.2.E.
F. Surveillance Instrumentation The limiting conditions for the instrumentation that provides sur-veillance information readouts are given in Table 3.2.F.
'F. Surveillance Instrumentation Instrumentation shall be cal-ibrated and checked as indic-ated in Table 4.2.7.
G. Control Room Isolation The limiting conditions for instru-mentation that isolates the control room and initiates the control room emergency pressurization systems are given in Table 3.2.G.
G. Control Room Isolation Instrumentation shall be calibrated and checked as in-dicated in Table 4.2.G.
Amendment No.
121 52
TABLE 3.2.D OFF-GAS POST TREA'PENT ISOLATION INSTRUMENTATION f
Min. No.
2 Function Tri Level Setting Action(2)
Remarks O
Off-Gas Post Treatment Monitor Note 3 Aor8 l.
2 upscales, or 1 downscale and 1 upscale, or 2 down-scales will isolate off-gas line.
Off Gas Post Treatment Isolation Note 3
1.
One trip system with auto transfer to another source Notes:
Whenever the minimum number operable cannot be met the indi t d i
h L
1.
d e
n ca e
act on s all be taken.
Pur in uring SI performance is not considered a loss of monitoring capability.
g ng 2.
Action A.
Refer to Rection 3.2.D.l.b B.
Refer to Section 3.2.D.l.c 3.
Trip setting to correspond to Specification 3.2.D.l.a
1,1MITIYG CONDITIONS FOR OP1>RATI(N SURVI'.1l.i.AiVCi Rl'.qUIREMl'.NTS 8.
Radioactive gases released from each unit's turbine and reactor building roof vents, the radwaste building roof vents, and the main stack shall be continuously monitored.
To accomplish this, at least one reactor building and one turbine building vent monitor:ng system per unit shall be operating whenever that unit s br!ildir!g ventilation system is in service.
- Also, one radwaste build'ing system vent monitoring channel shall be operating whenever the radwaste vent.ilation system is in service.
At least one main stack mon'itoring cl!annel shall be operating whenever any unit's air ejector, mechanical v>!cuum pump, or a standby gas treatment syste!n train is in service.
lf. normal monitoring systems are not availai>le, temporary monitors or ot:her systems shall be used to monitor effluent.
A monitoring clrannel may be out-of-service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing and calibration without providing a temporary monitor.
Both stack monitors may be taken out-of-service for less than l hour. for purging of monitors during SI performance.
4.8.B Airborne Effluents If tire;:e requirements are not satisfied for the st.trek or radwaste
- monitor, the reactors shall be in the hot shutdown condition within 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />'or tire strr<.k and 10 days for the r dwaste vent.
Purging during Si performance is not considered a loss of n!onieorfng c;rpability.
If these requir=ments are not satisfied for tire reactor and turbine building vents, the affected reactor shall be in hot shutdown condition witlrin 10 days.
Amendment Ho.
121 285
'S REgy (4
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O I
kg*y4 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
97 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 August 5, 1985, 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.
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 S ecifications
-The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
97
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective 90 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 13, 1986 Daniel R. Muller, Director BWR Project Directorate k'2 Division of BWR Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
97 FACILITY OPERATING LICENSE NO.
DPR-68 DOCKET NO. 50-296 Revise Appendix A as follows:
1.
Remove the following pages and replace with identically numbered pages.
52, 79, 306, 307 2.
The marginal lines on these pages denote the areas being changed.
LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.2 PROTECTIVE INSTRUMENTATION 4.2 PROTECTIVE INSTRUMENTATION D.
Off-Gas Post Treatment IsolaEion Function continued reactor power operation is permissible during the next seven
- days, provided that the inopcrab3e, monitor is tripped in the downscale position.
Onc radiation monitor may be out-of-service for four hours for Iunctional test and/or calibration without the monitor being in a downscale tripped condition.
Both monitors may be taken out-of-service for less than one hour'fo> purging of monitors during SI performance.
(c)
Upon the loss of both off-gas post treatment radiation
'onitors, initiate an orderly shutdown and shut the mainsteam isolation valves or. the off-gas isolation valve within 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.
Purging during SI performance
's not considered a loss of monitoring capability.
Amendment No.
97 52
TABLE 3.2.D OFF-GAS POST TREA'BENT ISOLATION INSTRUMENTATION Function Tri Level Set tin Action(2) Remarks Off-Gas Post Treatment Monitor Off Gas Post Treatment Isolation Note 3 Note 3 AorB 1.
2 upscales, or 1 downscale and 1 upscale, or 2 down-scales will isolate off-gas line.
1.
One trip system with auto transfer to another source Notes:
1.
whenever the minimum number operable cannot be met th i di d
e n
cate action shall be taken.
during SI performance is not considered a loss of monitoring capability.
Purging 2.
Action A.
Refer to Section 3.2.D.1.b B.
Refer to Section 3.2.D.l.c 3.
Trip setting to correspond to Specification 3.2.D.l.a
0
1.1NIT 1?IG 00?IDET'1 U?IS 1'OR Oi'ERA'I'ION SllRVI'. I I,I.AIICI RE<JU1REHEHTS 8.
Radioactive gases released from each unit's turbin(! and reactor buildi>>g roof vents, th< radwaste building roof vents, aud the main stack shal,l be coatinuously monitored.
To accomplish this, at least one reactor building and one turbine building vent monitoring system per unit shall be operating whenever that unit's building ventilation system ls in service.
Also, one radwaste building sys"e~.: vent monitoring channel shali.
be operating whenever the radwaste ventilation system is in service.
At least one mal.n stack monitoring channel shall be operating whenever any unit's a':r ejector, mechanical vacuum pump, or a standby gas tteatm-nt system train is it> service.
IF norm.l monitoring systems are not available temporary monitors or other systems shall be used to mon1to: efiluent.
A monitoring channel may be out-nl'-service for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for functional testing and calibration without providing a temporary monitor.
Both stack monitor may be taken out-of-service for less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for purging of monitors during Si performance.
4.8.11 Airborne Ef fluents I f then(
re<]'ll. ement 'le not satisfied Eor the stack or radwaste
- monitor, the reactors shall be in the hot shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the stack and 10 days for the radwast.e vent.
Purging during SI performance is not consider d
a los.
ol monitoring capability.
IF these requIrements are not satisfied f'r the reactor and turbine building vent.:,
the affected reactor shall be in hot shutdown condition within 10 days.
Amendment No.
97 306
LXHITING CONDI-XQBS PQR OPERATION SURVEILLANCE REQUIREHENTS 3 ~ 8 RADIOACTIVE MAT""3 P LS 0.8 OhCTIVE HATER S
C.
V<cna icaJ Vacu u. ~~
1.
Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a s gnal of high radioactivity in the steam lines whenever the main steam isolation valves are open.
C.
e an ca V
u P
ht least once during each oper atinq cycle ver ify automatic securing and isolation of the mechanical vacuum pampa.
2.
Ii a vacuum pump cannot meet the limits of 3.8.C.l, that vacuum pump shall be iso-lated.
Amendment No.
97