ML18029A721
| ML18029A721 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 07/08/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Tennessee Valley Authority |
| Shared Package | |
| ML18029A722 | List: |
| References | |
| DPR-33-A-119, DPR-52-A-114, DPR-68-A-090 NUDOCS 8507230507 | |
| Download: ML18029A721 (22) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROh'NS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TQ FACILITY OPERATING LICENSE Amendment No. 119 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 December 21, 1984, 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-33 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.
119, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
8507830507 850708 +
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3.
This license amendment is effective within 90 days of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 8, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch 82 Divisi on of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO. 119 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.
271 286 291 2.
The marginal lines on these pages denote the area being changed.
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Vacuum Relief The purpose af the vacuum relief'alve.". i.. t<< equalize tl<<. pica.".>>re between thc drywall and suppression chamber. and rcnctar buildinp sa that t)<c structural inteprity of the containment is maintained'.
Tlie vacuum relief system f'rom the pres"ure suppression chamber to reactor building consists of tua 100< vacuum relief breakers (2 parallel sct" af 2 valves in series).
Opcrntian of either system vill maintain the prcssure differential less than 2 psig; the external design prcssure.
One reactor building vacuum breaker mny be aut of service for repairs for a period of seven diny
. If repairs cannot be comp'cted vithin seven days, the reactor coo)ant system is brought to a condition where vacuum relief is no longer required.
. 'Nicn a dryucll-suppression chamber vacuum breaker valve is cxcrcised
'thrnugh nn npeninr;clasinr. cycle the position indicatinr. lirhts in the control roam are dc"igncd to.function ss specif'icd below:
~+
Initial and Final Check - On (Fully closed)
Condition Green - On Red Off'pening Cycle Closing Cycle Check - Orr Green - Off
'ed
- On Check << On Green - On Red
- Orr (Cracked open)
(> 80 Open)
(> 3" Open)
(Fully Cloned)
(< 80~ oper.)
c 30 Open)
The valve position indicating lights consist of one check light. on the check light panel vhich confirms full closure, one green light next to the hund. svitch vhich confirms 80 ofull opcninp, nnd one re<1 light next 0
to tht hand suitch uhich confirms "near c)azure" (uithii<.'," ac f'ul) clorurc).
Fmch light. is on'a aepninte switch. If the chock light circuit in nporsblo uhcii thc valve is excrci<ic<l by its nir operator thoro exists a
confirm<ition that the valve vill fully close.
gf the red lipht circuit is
- operable, there exists a canfirmatioii that the valve vill at least
>>nearly close" (vithin 3 of full closure).
Tnc green light circuit confkrms the valve vill fully open.
Zf none nf the lights change indication during thc cycle, the air operator must be inoperable ar the valve disc is stuck.
For this case, n check light on and red lipht off cnnrin...", the di c in in a near'y closed position even if one or thc indicntiann is in error.
Althouph the valve may be inoperable for full closure,.it does not consti-tute a safety threat.
If the red lipht circuit alone in inoperable, the valve "hali still be considered fully aperable.
If'he preen and red or the preen light'ircuit a)ong i'naperuble thc valve shall bc sonsidcred inoperablc for 27) r Amendment No.
119
LIMITING CONDITIONS POR OPERATION C.
Mechanical Vacuum Pumps SURVEILLANCE RE(}UIREMENTS C. Mechanical Vacuum Pum s l.
Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a signal of high radioactivity in the steam lines whenever the main steam isolation valves are open.
2.
If a vacuum pump cannot meet the limits of 3.8.C.l, that vacuum pump shall be iso-lated.
D.
Miscellaneous Radioactive Materials"Sources
- 1. Source Leakage Test Each sealed source contain-ing radioactive material in excess of those quantities of byproduct material listed in 10 CFR 30.71 Schedule B
and all other sources, in-cluding alpha emitters, in excess of O.l microcurie>
shall be free of %0.005 mic-rocurie of removable contam-ination.
Each sealed source with removable contamination in excess of the above limit shall be immediately with-drawn from use and (a) eithe decontaminated and (b) dis>>
posed of in accordance with Commission Regulations.
At least once during each operating.
cycle verify automatic securing and isolation of the mechanical vacuum pumps'.
Miscellaneous Radioactive Materials Sources
- 1. Surveillance Re uirements Teste for leakage and/or contamin-ation shall be performed by the licensee or by other persons specifically authori-sed by the Commission or an agreement
- State, as followst a.
Each sealed
- source, except startup sources sub5ect to core flux, con-taining radioactive material, other than Hydrogen 3, with a half-life greater than thirty dave and in any fohn-other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.
The leakage test shall be capable of detecting the presence of O.OOS microcurie of radioactive material on the test sample.
- b. The periodic leek test required does not apply to sealed sources that are stored and not being used.
The sources excepted from this test shall be test'ed for leakage prior to any use or transfer to another user un-less they have been leak tested with-in six months prior to the date of use or transfer.
In the absence of a certification from a transferor in-dicating that a test has been made within six months prior to t:he trans-fer, sealed sources shall not be put into use until tested.
Amendment NO.
119 286
- c. Startup sources shall be leak tested prior to and following any repair or maintenance and before being sub5ect-ed to core flux.
3.8~C/0.8.C Hechan cal Vacuum Pum The purpose of isolating the mechanical vacuum pump lines is to limit the release of activity from the main condenser.
During an
- accident, fission products would be &ansported from the reactor through the main steam lines to the condenser The fission product radioactivity would be sensed by the main steam line radioactivity monitors which initiate isolation.
0.8.A and 0.8.B BASES The surveillance reguirements given under Specification 0 8 h and 4.8.B provide assurance that liquid and gaseous wastes are properly controlled and monitored during any release of radioactive materials in the liquid and gaseous effluents These surveillance requirements provide the data for the licensee and the Commission to evaluate the station's perfornuLnce relative to radioactive wastes released to the environment Reports on the quantiti.es of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications.
On the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as the Commission deema appropriate.
The objective of this specification is to assure that leakage from'byproduct,
- source, and special nuclear radioactive material sources does not exceed allowable limits Amendment No. 1l9 291
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Cy UNITED STATES NUCLEAR REGULATORY COMMISSION WASHlNGTON, D. C. 20555 TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 114 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 December 21,
- 1984, 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-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.
114, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective within 90 days of the date of its issuance.
FOR THE NUCLEA REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 8, 1985 Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
114 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.
271 286 291 2.
The marginal lines on these pages denote the area being changed.
BAS)'"i Vacuum Relief The purpose of the vacuum relief valves 'o c<)ualizc U>c pressu> c betveen the dryvell and suppression chamber and reactor iuilding so thnt the structural integrity of the containment is maintained.
The vacuum relief system from the pressure suppression chamber to reactor building consists of tvo 100$ vacuum relief breakers (2 parallel sets of 2 valves in series):
Operation of either system vill maintain the pressure differential less than 2 poig; the external design prcssure.
One reactor b'>ildin<< vacuun breaker may be out of service for repniro for n period of sever. days.
5 repairs cannot be completed vithin seven days, thc react. or coolant system is brought to a condition where vacuum relief is no longer required.
1').en a <iryvel'-suppression cha.",.b r vacuum breaker valve is exercised through en opening-closing cycle the position indicating lights in t,hc control room are designed to function as specified belov:
Init.inl and Final
" Condition Check - On Green On
)tcd
- Off (Ful?y close<1)
Opening Cycle Check
<< Off Green - Off Red
- On (Cracked open)
(> Go'pen)
(> 3 Open)
Closin): Cycle Check On Green On Red
- Ofi'Fu1Iy Closed)
(< SOo Open)
< 3 Open)
The valve position indicnt;ing lirhto consist of cne check light on the.
check lig)>t panel vhich confirms full cIooure, ore green light next to th<. )>and switch vhich confirms 80 of full opcnirg nnd one red Lijht next.
t.o t,h<
hn>>d owi:.i.!< vhi<'h cnnfi>-..o "nc>>r r]oo<>rc" (within 3" nf full
<'lo<<><'( ).
Vach 1)>',l>t io o<> n ocp'<rate
! wi Lch.
1 f the
< hock light <'ircui!.
i" oper e when t.hc v<>lv<. is exercise<)
hy tts <<ir oprrntor there cxi"..t.:<
<<infi>v.nti<><> t?o<t.
),h<
v;<1 v~ v) I1 1'ul ly close.
11'>< ~ r<<)
.) if)>t ci> cui <. i.:
opcrnblc, thc.c exists n confirmat,ior> that the valv<: will ut. least "nc:<rly clone" (within 3 of full clos>>rc).
Thc preen light, circuit confirms thc valve vill fully open.
If none o> the lights ch><ngc indication during t,he cyc.le, the air operator must, be inoperable or the valve disc is stuck.
For this case, n check light nn and rcd light of.'onfirms the disc is in a nearly close<1 position even if one of thc indications is in error.
M t.hn>>:;h the valve mny be inoperable fnr full <il >sure, it does not const.i-tutc n safety threat.
~
If t.he red light circuit, alone is inoperable, the valve shall still be considered fully operable.
If the preen ar>d re<1 or the green light circuit, alon,", io inoperable the valve ohall be sonskdcrcd inoperable for Amendment No.
114 271
LIMITING CONDITIONS POR OPERATION SURVEILLANCE REQUIREMENTS C.
Mechanical Vacuum Pumps C. Mechanical Vacuum Pum s
1.
Each mechanical vacuum pump shell be capable of being
~utomatically isolated and secured on a signal of high radioactivity in the steam lines whenever the main steam isolation valves are open.
2.
If a vacuum pump cannot meet the limits of 3.8.C.1, that vacuum pump shall be iso-lated.
D.
Miscellaneous Radioactivh Materials'Sources Each sealed source contain-ing radioactive material in excess of those quantities of byproduct material listed in 10 CFR 30.71 Schedule B
and all other sources, in-cluding alpha emitters, in excess of 0.1 microcurie, shall be free of %0.005 ~ic-rocurie of removable contam-ination.
Each sealed source with removable contamination in excess of the above limit shall be inanediately with-drawn from use and (a) eithe decontaminated and (b) dis-posed of in accordance with Commission Regulations.
At least once during each operating cycle verify automatic securing and isolation of the mechanical vacuum pumps.
D. Miscellaneous Radioactive Materials Sources
- 1. Surveillance Re uirements Tests for leakage and or contamin-ation shall be performed by the licensee or by other persons specifically authori-sed by the Commission or an agreement
- State, as follows:
a.
Each sealed
- source, except startup sources sub)ect to core flux, con-taining radioactive material, other than Hydrogen 3, with a half-life greater than thirty davs and in any fohn-other than gas shall be tested for leakage and/or contamination at intervals not to exceed six months.
The leakage test shall be capable of detecting the presence of 0.005 microcurie of radioactive material on the test sample.
- b. The periodic leak test required does not apply to sealed sources that are stored and not being used.
The sources excepted from this test shall be tested for leakage prior to any Use or transfer to another user un-less they have been leak tested with>>
in six months prior to the date of use or transfer.
In the absence of a certification from a transferor in-dicating that a test has been made within six months prior to the trans-fer, sealed sources shall not be put into use until tested.
- c. Startup sources shall be leak tested prior to and following any repair or maintenance and before being sub)ect-ed to core flux.
286 Amendment No.,114
3 ~ 8 ~ C/4 ~ 8 C
echani al Vacuum pum The purpose of isolating the mechanical vacuum pump lines is to limit the release of activity from the main condenser.
During an
- accident, fission products would be transported from the reactor through the main steam lines to the condenser The fission product radioactivity would be sensed by the main steam line radioactivity monitors vhich initiate isolation.
4.8.A a d 0.8.B BASES The surveillance requirements given under Specification 4
8 A and 4.8.B provide assurance that liquid and gaseous vastes are properly controlled and monitored during any release of radioactive materials in the liquid and gaseous effluents These surveillance requirements provide the data for the licensee and the commission to evaluate the station's perfonaance relative to radioactive Mastes released to the environment.
Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specifications.
on the basis of such reports and any additional information the Commission may obtain from the licensee or others, the Commission may from time to time require the licensee to take such actions as +e Commission deems appropriate.
3.8 D and O.B.D BASES The objective of this. specification is to assure that leakage from byproduct,
- source, and special nuclear radioactive material sources does not exceed allowable Limits Amendment No. 114 291
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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. 90 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 December 21, 1984, 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.
90, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
2 3.
This license amendment is effective within 90 days of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
Ju]y Q
l9Q5 Domenic B. Vassallo, Chief Operating Reactors Branch 82 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO. 90 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.
307 315 2.
The marginal lines on these pages denote the area being changed.
LZHITZNG CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3 ~ $
RADIOACTIVE MAT ALS 0 ~ 8 Oh ZVE TER S
the stack or radwaste monitor, the reactors shall be in the hot, shutdown condition within 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> for the stack and 10 days for the radwaste vent.
Zf these requirements are not satisfied for the reactor and turbine building
- vents, the affected reactor shall be in hot shutdown condition within 10 days C,
Hecha ic V
+Ques.'.
Each mechanical vacuum pump shall be capable of being automatically isolated and secured on a signal of high radioactivity in the steam lines whenever the main steam isolation valves are open.
Ce ht least once during each operating cycle verify automatic securing and isolation of the mechanical vacuum p~.
2.
If a vacuum pump cannot meet the limits of 3.8.C.l, that vacuum pump shall be iso-lated.
Amendment No.
90
a 3 ~ 8 C/0.8.C Meehan a
Vacuum pum The purpose of isolating the mechanical vacuum pump lines is to limit the xelease of activity from the main condenser.
During an accident, fission products would be transported from the reactor through the main steam lines to the condenser The fissian product radioactivity would be sensed by.the main steam line radioactivity monitors which initiate isolation.
0.8.A a d 0.8.B BASES The surveillance requirements given undex'pecification 0 8.K and 0.8.B provide assurance that. liquid. and gaseous wastes are properly controlled and monitored duxing any release of radioactive materi.als in the liquid and gaseous effluents These surveillance requirements provide the data for the licensee and the commission to evaluate the stationers perfeanance relative to radioactive wastes released to the environment.
Reports on the quantities of radioactive materials released in effluents shall be furnished to the Commission on the basis of Section 6 of these technical specificatians.
On the basis of such reports and any additional information the Commission may abtain from the licensee or others, the Commission may from time to time xequixe the licensee to take such actions as the Commission deems appxopxiate.
~ 7 3 B.D aaS A.B.D BASES The objective of this specification is to assure that leakage fram byproduct,
- souxce, and special nuclear radioactive material'ources does not exceed allowable limits Amendment No.
90