ML20247H880
| ML20247H880 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/19/1989 |
| From: | Black S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247H885 | List: |
| References | |
| GL-88-01, GL-88-1, NUDOCS 8905310358 | |
| Download: ML20247H880 (21) | |
Text
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'0, UNITED STATES
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NUCLEAR REGULATORY COMMISSION j-WASHING TON. D. C. 20$55
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TENNESSEE VALLEY AUTHORITY y
DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 166 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 9,1988, 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.
1 Commission; 1
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 Commission's regulations; i
= 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.
P 1
r i..
_. l 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendnent and paragraph 2.C.(2) of Facility Operating License No. DPR-33 is hereby amended to read as follows:
(2) Technical Specifications y.
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.166, 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 60 days from the date of issuance..
FOR THE NUCLEAR REGULATORY COMMISSION
(
% suc_.
Suzanne ack, Assistant Director for Projects i
TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical 3
/
Specifications Date of Issuance: May 19, 1989 1
1
~ c ATTACHMENT T0 LICENSE AMENDMENT NO.166 FACILITY OPERATING LICENSE NO. DPR-3S DOCKET NO. 50-259 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages I
are identified by the captioned amenament number and contain marginal l
lines indicating the area of change. Overleaf page* is provided to maintain l
document completeness.
J REMOVE INSERT i
1.0-11 1.0-11*
1.0-12 1.0-12 l
g
e 1.0 DEFINITIONS (Cont'd) 1
- 1. -
l
. GG.. = Site Boundarv - Shall be thtt line beycnd which the land is not
)
owned, leased, or?otherwise controlled by TVA.
[
HE.
Unrestricted Arga - Any area at or beyond the site boundary to which access-is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used i
for industrial, commercial, institutional, or recreational i
purposes.
1 II.
Dose Eaufvalent T-131 - The DOSE EQUIVALENT I-131 shall be the i
concentration of.I-131 (in mci /gm) which alone would' produce the same thyroid dose as the quantity and isotopic mixture of-1 I-131, I-132, I-133, I-134, and 1-135 actually present. The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844 " Calculation of Distance Factors for Power and Test Reactor Sites".
JJ..
Gaseous Waste Treatment System - The charcoal adsorber vessels insta13ed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.
KK.
Members of the Public - Shall include all individuals who by virtue of their occupational status have no formal association p
with the plant. This category shall include non-employees of t
the licensee who are permitted to use portions of the site for recreational, occupational., or other purposes not associated with plant functions. This category shall ngt include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.
LL.
Surveillance - Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each surveillance Requirement shall be performed within the specified time interval with, (1)
A maximum allowable extention not to exceed 25% of the surveillance interval, but (2)
The combined time entered for any 3 consecutive surveillance intervals shall not axceed 3.25 times the specified surveillance interval i
Performance of 'a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these
+-
specifications. Surveillance requirements do not have to be performed on inoperable equipment.
BFN 1.0-11 Unit 1 L
i~
1.0 DEFINITIONS (Cont'd)
MM. Surveillance requirements for ASME Sect $on XI Pumo and Valve' Pronram - Surveillance requirements for Inservice Testing of ASME Code Class 1, 2, and 3 components shall be applicable as follows:
1.
Inservice testing of ASMZ Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
2.
Surveillance intervals specified in Section XI of the ASMI Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these technical specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice testint activities testinn activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 2/6 days Yearly or annually At least once per 366 days 3.
The provisions of Specification 1.0.LL are applicable to the above required frequencies for performing inservice testing activities.
4.
Performance of the above inservice testing activities shall be in addition to other specified surveillance requirements.
5.
Nothing in *he ASME Boiler and Pressure Vessel Code shall be construed to aupersede the requirements of any technical specification.
6.
The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods, personnel, and sample expansion included in this generic letter, l
BFN 1.0-12 Amendment No. '59, 166 Unit 1 6
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g UNITED STATES
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NUCLEAR REGULATORY COMMISSION q
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WASHINGTON. D. C. 20555
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i TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 165 License No. DPR-52 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated December 9,1988, 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 confonnity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorizedby 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 connon 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.
t 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.165, 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION W
4C Suzanne ack, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 19, 1989 i
l h
l ATTACH [ENT TO LICENSE AMENDMENT NO. 165 FACILITY OPERATING LICENSE NO. DPR-52 i
DOCKET NO. 50-260 i
Re<ise 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. The asterisked (*) pages are provided
- for document integrity.
Note change bar on each page at page number..
REMOVE INSERT 1.0-7 1.0-7*
1.0.8 1.0-8*
1.0-9 1.0-9*
1.0-10 1.0-10*
1.0-11 1.0-11*
1.0-12 1.0-12*
1.0-13*
1.0-13a*
._.____m__._.-________.-__
...__.__mm_
m
_.m
'1.0 DEFINITIONS (Cont'd)
Q.
Ooeratina Cvele - Interyc1 betwacn the end of ona refueling outage for a particular unit and the end of the next subsequent refueling outage for the same unit.
R.
Refuelina Outare - Refueling outage is the period of time between the shutdown of the unit prior to a refueling and the startup of the unit after that refueling. For the purpose of designating frequency of testing and surveillance, a refueling outage shall mean a regularly scheduled outage; however, where such outages occur within 8 months of the completion of the previous refueling outage, the required surveillance testing need not be performed until the next regularly scheduled outage.
S.
CORE ALTERATION - The addition, removal, relocation, or movement of fuel, sources, incore instruments, or reactivity controls within the reactor pressure vessel with the head removed and fuel in the vessel. Normal control rod movement with the control rod drive hydraulic system is not defined as a Core Alteration. Normal movement of in-core instrumentation and the traversing in-core probe is not defined as a Core Alteration. Suspension of Core Alterations g
shall not preclude completion of the movement of a component to a t
safe conservative position.
T.
Reactor Vessel Pressure - Unless otherwise indicated, reactor vessel pressures listed in the Technical Specifications are those measured by the reactor vessel steam space detectors.
U.
Thermal Parameters 1.
Minimum Critical Power Ratio (MCPR) - Minimum Critical Power Ratio (MCPR) is the value of the critical power ratio associated with the most limiting assembly in the reactor core.
Critical Power Ratio (CPR) is the ratio of that power in a fuel assembly, which is calculated to cause some point in the assembly to experience boiling transition, to the actual assembly operating power.
2.
Transition Boilina - Transition boiling means the boiling regime between nucleate and film boiling. Transition boiling is the regime in which both nucleate and film boiling occur intermittently with neither type being completely stable.
3.
Core Maximum Fraction of Limitina Power Density (CMTLPD) - The highest ratio, for all fuel types in the core, of the maximum fuel rod power density (kW/ft) for a given fuel type to the limiting fuel rod power density (kW/ft) for that fuel type.
4.
Averaae Planar Linear Heat Generation Rate (APLHCR) - The Average Planar Heat Generation Rate is applicable to a specific
{
planar height and is equal to the sum of the linear heat
{
generation rates for all the fuel rods in the specified bundle i
at the specified height divided by the number of fuel rods in I
the fuel bundle.
I BFN 1.0-7 Amendment No. 154 l
Unit 2
)
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g u.
~ - = = -----
~
-1.0 DEFINITIONS (Cont'd)
L'
.V.-
Inserumentatian
'l 1.
Instrument Calibration - An instrument calibration means the 4-adjustment of an instrument signal output so that.it corresponds, within acceptable range, and accuracy,.to.a known value(s) of the parameter which the instrument monitors.-
- 2.. Channel'- A channel ie an arrangement of the sensor (s)'ana
- associated components used to evaluate plent variables and E
-*oduce discrete outputs used in logic. A channel terminates cA loses its identity where individual channel outputs are comoined in logic.
3..
Instrument Functional Test - An instrument functional test means the injection of a simulated signa 1Linto the instrument' primary sensor.to verify the. proper instrument channel response, alarm and/or initiating. action.
4.
Instrument Check -'An instrument check is qualitative 4 -
determination of acceptable operability by observation of instrument behavior during operation. This determination shall
' include,'where possible, comparison of the instrument with other independent instruments measuring the'some variable.
5.
Logic System Functional' Test - A logic system functional test means a test =of all relays and contacts of a logic circuit to insure all. components are operable _per design intent. Where
. practicable, action will go to completion; i.e., pumps will be started and valves operated.
6.
Trio System - A-trip system means an arrangement of instrument
' channel trip signals and auxiliary equipment required to initiate action to accomplish a protective trip function.
.A trip system may require one_.or more. instrument, channel trip signals related to one or more plant parameters in order to initiate trip system action.. Initiation of protective action may require the tripping of a single trip system or the coincident tripping of two trip systems.
7.
Protective Action - An action initiated by the protection system when a limit is reached. A protective action can be at a channel or system level..
8.
Protective Function - A system protective action which results from the protective action of the channels monitoring a particular plant condition.
9, Simulated Auta== tic Actuation - Sluulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit in question.
I 1
I BFN 1.0-8 Amendment No. 165 Unit 2 1
l
, = 1. 0, DErfNITION3 (Cont'd)
- 10. L2 gig - A logic is an arrangement of relays, contacts, and other components that produces a decision output.
l-(a) Initiatina - A logic that receives signals from channels and produces decision outputs to the actuation logic.
(
(b) Actuation - A logic that receives signals (either from I
initiation logic or channels) and produces decision outputs to accomplish a protective action.
- 11. Channel Calibration - Shall be the adjustment, as necessary, of the channel output such that it responds with necessary range and accuracy to known values of the parameters which the channel monitors. The channel celebration shall encompaso the entire channel including alarm and/or trip functions and shall include the channel functional test.- The channel calibration may be performed by any series of sequential, overlapping or total channel steps such that the entire channel is calibrated. Non-calibratable components shall be excluded from this requirement, but will be included in channel functional test and source check.
- 12. Channel Functional Test - Shall be:
a.
Analog Channels - the injection of a simulated signal into the channel as close to tb, sensor as practicable to verify OPERABILITY including alarm and/or trip functions.
b.
Bistable Channels - the injection of a simulated signal into the sensor to verify OPERABILITY including alarm and/or trip functions.
- 13.. Source Check - Shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source or multiple of sources.
BFN 1.0-9 Unit 2 knendment No. 165
" l '. 0 DEFINITIONS (Cont'd).
W.
Functional Tests - A functionsi test is the mrnual operatiohnor initiation of a system, subsystem, or component to verify th'at it functions within design tolerances (e.g., the manual start of a core spray pump to verify that it runs and that it pumps'the required volume of water).
X.
Shutdown - The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and no core alterations are being performed.
Y.
Engineered Safeauard - An engineered safeguard is a safety system the actions of which are essential to a safety action required in response to accidents.
Z.
.Recortable Event - A reportable ev=nt shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
AA. Solidification - Shall be the conversion of radioactive vastes into a form that meets shipping and burial ground requirements.
BB Offsite Dose Calculation Manual (ODCM) - Shall be a manual describing the environmental monitoring program and the methodology and parameters used in the calculation of release rate limits and offsite doses due to radioactive gaseous and liquid effluents. The ODCM will also provide the plant with guidance for establishing alarm / trip setpoints to ensure technical specifications sections 3.8.A.1 and 3.8.B.1 are not exceeded.
CC. Purae or curaina - The controlled process.of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is required to purify the containment.
DD. Process Control Pronram - Shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.
EE. Radiological Effluent Manual (REM) - Shall be a manual containing the site and environmental sampling and analysis programs for measurements of radiation and radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radiation exposure to individuals from station operation. It shall also specify operating guidelines for radioactive waste treatment systems t.ad report content.
j' FF. Ventina - The controlled proccas of discharging air or gas from the primary containment to maintain temperature, pressure, humidity, concentration, or other operating condition in such a manner that replacement air or gas is not provided or required.
Vent, used in system names, does not imply a venting process.
BFN 1.0-10 Amendment No. 165 Unit 2
'1.0~ DEFINITIONS'(Cont'd)-
/*
GG.
Site Boundarv - Shc11: be that lina bsyond which the-lend is not owned, leased, or otherwise controlled by TVA.
HH. Unrestricted Area - Any area at or beyond.the site boundary to
)
which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and j
radioactive materials or any area within the site boundary'used i
for industrial, commercial, institutional, or recreational purposes.
II.
Dose Eauivalent I-131 - The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in mci /gm) which alone would produce the same-thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factor used for this calculation shall-be those listed.in Table III of TID-14844 " Calculation of Distance Factors for Power and Test Reactor Sites".
JJ.
Gaseous Waste Treatment System - The charcoal adsorber vessels ir. stalled on the discharge of the steam jet air ejector to provide delay to.a unit's offgas activity prior to release.
KK.
Members of the Public - Shall include all individuals who by virtue of their occupational status have no formal association with the plant.- This category shall include non-employees of the' licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall nat include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.
LL.
Surveillance - Surveillance Requirements shi.11 be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each surveillance Requirement shall be performed within the specified time interval with, (1)
A maximum allowable extention not to exceed 25% of the surveillance interval, but (2)
The combined time entered fer any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and as;ociated action statements unless otherwise required by these specifications.
Surveillance requirements do not have to be performed on inoperable equipment.
BFN 1.0-11 Unit 2 Amendment No. 165
ez.
i 1.0: DEFINITTC115 (Cont'd).
i s
- MM. Surveillance requirements for ASME Section XI'Pumn and Valve' Program - Surveillance requirements for Inservice Testing of g
ASME Code Class 1, 2, and 3 components shall be applicable as
-follows:
1 1.
Inservice testing of ASME Code Class 1, 2, and 3. pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Code and applicable Addenda as required by.10 CFR 50, Section 50.55a(g), except where j
specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).
2.
Surveillance intervals specified in Section XI of the ASME.
Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the ASME
]
Eoiler and Pressure Vessel' Code and applicable Addenda
{
shall be applicable as follows in these technical specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservJee terminology for inservice testina activities testina activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once.per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least-once per 276 days Yearly or annually At least once per 366 days 3.
The provisions of Specification 1.0.LL are. applicable to the above required frequencies for performing inservice-testing activities.
4.
Performance of the above inservice testing activities shall-be in addition to other specified surveillance requirements.
5.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any technical specification.
6.
The inservice inspection program for piping identified in 1
NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods, personnel, and sample expansion included in this generic letter.
BFN 1.0-12 knendment No. 165.
. Unit 2
._ J
Table 1.1 SURVEILLANCE FREOUENCY NOTATION NOTATION IREQUENCY S
(Shift)
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
D (Daily)
At least once per normal calendar 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> day (midnight to midnight).
W (Weekly)
At least once per 7 days.
M (Monthly)
At least once per 31 days.
Q (Quarterly)
At least once per 3 months or 92 days.
SA (Semi-Annually)
At least once per 6 months or 184 days.
Y (Yearly)
At least once per year or 366 days.
R (Refueling)
At least once per operating cycle.
S/U (Start-Up)
Prior to each reactor startup.
N.A.
Not applicable.
P (Prior)
Completed prior to each release.
BFN 1.0-13 Amendment No. 165 Unit 2
7-____-._-.-
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l THIS PAGE INTENTIONALLY LEFT BLANK BFN 1.0-13a Amendment No. 165 Unit 2
'ff
,'o, UNITED STATES y.
g NUCLEAR REGULATORY COMMISSION Q
.]j WASHINGTON, C. C. 20555 l
TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE i
Amendment No.137 License No. DPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the license'e) dated December 9, 1988, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
I and the Comission'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 Comission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorizedby 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, I
l 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 Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.137, 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 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION ACN
,v >tA,
Suzann'( Black, Assistant Director for Projects TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issu&nce: May 19, 1989
ATTACHMENT TO LICENSE AMENDMENT N0. 137 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the peges 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 page* is provided to I
naintain document completeness.
REMOVE INSERT 1.0-11 1.0-11*
1.0-12 1.0-12 L-______________
n!
,1. 0 DEFINITIONS (Cont'd)
GG.
Site Boundarv - Shall be that line beyond which the land is not owned, leased, or otherwir,e controlled by TVA.
EH.
Unrestricted Area - Any area at or beyond the site boundary to which access is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials or any area within the site boundary used for industrial, commercial, institutional, or recreational purposes.
l II.
Dose Eauivalent I-131 - The DOSE EQUIVALENT I-131 shall be the concentration of I-131 (in mci /gm) which alone would produce the same thyroid dose as the quantity and isotopic mixture of i
l I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factor used for this calculation shall be those listed in Table III of TID-14844 " Calculation of Distance Factors for Power and Test Reactor Sites".
JJ.
Gaseous Waste Treatment System - The charcoal adsorber vessels installed on the discharge of the steam jet air ejector to provide delay to a unit's offgas activity prior to release.
KK.
Members of the Public - Shall include all individuals who by virtue of their occupational status have no formal association with the plant. This category shall include non-employees of the licensee who are permitted to use portions of the site for recreational, occupational, or other purposes not associated with plant functions. This category shall agt include non-employees such as vending machine servicemen or postmen who, as part of their formal job function, occasionally enter restricted areas.
LL.
furvelliance - Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual limiting conditions for operation unless otherwise stated in an individual Surveillance Requirements. Each l
surveillance Requirement shall be performed within the specified time interval with, (1)
A maximum allowable extention not to exceed 25% of the surveillance interval, but (2)
The combined time entered for any 3 consecutive surveillance intervals shall not exceed 3.25 times the specified surveillance interval Performance of a Surveillance Requirement within the specified time interval shall constitute compliance and OPERABILITY requirements for a limiting condition for operation and associated action statements unless otherwise required by these specifications. Surveillance requirements do not have to be performed on inoperable equipment.
BFN 1.0-11 Unit 3
1~. 0 -
DEF2NITIONS (C@nt'd)
MM. Surveillance reautrements for ASME Section XI Pumn and Valvec
?rogram - Surveillance requirements for Inservice Testing of ASME Code' Class 1, 2, and 3 components shall be applicable as follows:
1.
Inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI of the ASME Boiler and Pressure Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(s)(6)(i).
2.
Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice testing activities required by the ASME Boiler and. Pressure Vessel Code and applicable Addenda shall be applicable as follows in these technical specifications:
ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice
- terminology for inservice testina activities testina activities Weekly At least once per 7 days-Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually.or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days 3.
The provisions of Specification 1.0.LL are applicable to the above required frequencies for performing inservice testing activities.
4.
Performance of the above inservice testing activities shall be in addition to other specified sut7eillance requirements.
5.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any technical specification.
6.
The inservice inspection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the staff positions on schedule, methods, personnel, and sample expansion included in this generic letter.
1 BFN 1.0-12 Amendment No.
130, 137 Unit 3 J