ML20149L132
| ML20149L132 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/12/1988 |
| From: | Zech G NRC OFFICE OF SPECIAL PROJECTS |
| To: | |
| Shared Package | |
| ML20149L135 | List: |
| References | |
| TAC-R00098, TAC-R00099, TAC-R00100, TAC-R100, TAC-R98, TAC-R99, NUDOCS 8802240124 | |
| Download: ML20149L132 (21) | |
Text
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UNITED STATES
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT, UNIT 1 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 142 License No. DPR-33 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 4, 1987, complies with the standards and 1
requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR j
Chapter I; j
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and i
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 comon 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.
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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 ard paragraph P.C.(2) of Fccility Operating License No. DPR-33 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and 8, as revised through Amendment No. 142, are hereby incorperated in the l
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 CCMMISSION zwg ;
AL-
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Gary G. Tech, Assistant Director for Projects TVA Projects Division Office of Special Projects i
Attachment:
Changes to the Technical Specifications Date of Issuance: February 12, 1988 b
-r e
,- - - -w
s ATTACHMENT TO LICENSE AMENDMENT NO.142 FACILITY CPERATING LICENSE NO. OPR-33 DOCKET NO. 50-259 Revise the App'endix A Technical Specifications by removing the pages icentified below and inserting the enclosed pages.
The revised pages are identified. by the captioned amendment number and contain marginal lines indicati'ng the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE INSERT 3.7/4.7-9 3.7/4.7-9*
3.7/4.7-10 3.7/4.7-10 3.7/4.7-11 3.7/4.7-11 3.7/4.7-12 3.7/4.7-12*
i l
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- 3. 7/4. 7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A.
Primary Containment 4.7.A.2. (Cont'd)
- j. Continuous Leak Rate Monitor When the primary containment is inerted the containment shall be continuously monitored for gross leakage by review of the inerting system makeup requirements. This monitoring system may be taken out of service for maintenance but shall be returned to service as soon as practicable, k.
Drywell and Tordu Surfaces The interior surfaces of the drywell and torus above the level one foot below the normal water line and outside surf aces of the torus below the water line shall be visually inspected each operating cycle for deterioration and any signs of structural damage with particular attention to piping connections and supports and for signs of distress or displacement.
BFN 3.7/4.7-9 Unit 1
3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SUR'{EILLANCE REOUIREMENTS 3.7.A PPIMARY CONTAINMENT 4.7.A PRIMARY CONTAINMENT 3.
Preseure Suppression Chamber -
- 3. Pressure Suppression Chamber-Reactor Building Vacuum Dreakers Reactor Buildint Vacuum Breakers
- a. Except as specified in
- a. The pressure suppression 3.7.A.3.b below, two pressure chamber-reactor building suppression chamber-reactor vacuum breakers shall be building vacuum breakers shall exercised and the associated be OPERABLE at all times when instrumentation including primary containment integrity setpoint shall be functionally is required.
The setpoint tested for proper operation of the differential pressure each three months.
instrumentation which actuates the pressure suppression chamber-reactor building vacuum breakers shall be 0.5 psid.
- b. From and after the date
- b. A visual examination and that one of the pressure determination that the suppression chamber-reactor force required to open each building vacuum breakers is vacuum breaker (check valve) made or found to be INOPERABLE does not exceed 0.5 psid for any reason, reactor will be made each refueling operation is permissible only
- outage, during the succeeding seven days, provided that the repair procedure does not violate primary containment integrity.
4.
Drywell-Pressure Suppression 4 Drywell-Pressure Suppression Chsmber Vacuum Breakers Chamber Vacuum Breakers
- a. When primary containment is
- a. Each drywell-suppression required, all drywell-chamber vacuum breaker suppression chamber vacuum shall be exercised through breakers shall be OPERABLE an opening-closing cycle and positioned in the fully every month.
closed position (except during testing) except as
- b. When it is determined that specified in 3.7.A.4.b and two vacuum breakers are 3.7.A.4.c., below.
INOPERABLE for opening at a time when operability is
- b. One drywell-suppression required, all other vacuum chamber vacuum breaker may bresker valves shall be be nonfully closed so long exercised immediately and as it is determined to be not every 15 days thereafter until more than 3* open as indicated the INOPERABLE valve has been by the position lights.
returned to normal service.
BFN 3.7/4.7-10 Amendment flo.142 Unit 1
3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment 4.7.A Primary Containment l
3.7.A.4 (Cunt'd) 4.7.A.4 (Cont'd)
- c. Two drywell-suppression
- c. Once each operating cycle chamber vacuum breakers each vacuum breaker valve may be determined to be chall be inspected for INOPERABLE for opening, proper operation of the valve and limit switches.
)
- d. If Specifications 3.7.A.4.a.
- d. A leak test of the drywell 3.7.A.4.b. or 3.7.A.4.c.
to suppression chamber 4tnnot be met, the structure shall be conducted unit shall be placci in a during each operating cycle.
Cold Shutdown condition in Acceptable leak rate is an orderly manner within 0.09 lb/sec of primery 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
containment atmosphere with 1 psi differential.
5.
Oxygen Concentration
- 5. Oxygen Concentration a.
Containment atmosphere shall be
- a. The primary containment reduced to less than 4% oxygen oxygen concentration shall cita nitrogen gas during reactor be measured and recorded power operation with reactor daily.
The oxygen coolant pressure above 100 psi 4, measurement shall be adjusted except as specified in 3.7.A.5.b.
to account for the uncertainty of the method used by adding a predetermined error function.
b.
Within the 24-hour period
- b. The methods used to measure subsequent to placing the reactor the primary containment in the RUN mode following a shut-oxygen concentration shall down, the containment atmosphere be calibrated once every oxy 5en concentration shall be refueling cycle.
i reduced to less than d% by volume and maintained in this condition.
Deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
c.
If plant control air is being used
- c. Tn Onntrol air supply valve to supply the pneumatic control for the pneumatic control system inside prirary containment, system inside the primary the reactor shall not be started, containment shall be verified or if at ower, the reactor shall closed prior to reactor startup
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be brous
.o a Cr 3.d Shutdown and monthly thereafter.
conditi n sithin Tc ' ves.
d.
If S
.a and 3.
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' n e-or shall be in
.o c* W 'i.o condition nithin 24 hJutt BF" 3.7/4.7-11 nmendment No.142 Un.*
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a 3.7/4.7 CONTAIRMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCd REQUIREMENTS 3.7.A.
Primary Containment 4.7.A.
Primary Contcinment 6.
Drywell-Suppression Chamber
- 6. Drywell-Suppression Chamber Differential Pressure Differential pressure
- a. Differential pressure between
- a. The pressure differential the.drywell and suppression between the drywell and chahbor shall be maintained suppression chamber shall at equal to or greater than be recorded at least once 1.1 psid except as specified each shift, in (1) and (2) bolow:
(1) This differential shall be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of achieving operating temperature and pressure. The differential pressure may be reduced to less than 1.1 psid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.
(2) This differential may be decreased to less than 1.1 psid for a maximum of four hours during required operability testing of the HPCI system, RCIC system and the drywell-presrure suppression chamber vacuum breakers,
- b. If the differential pressure of Specification 3.7.A.6.a cannot be maintained and the differential pressure cannot be restored within the subsequent six-hour period, an orderly shutdown shall be initiated and the reactor shall be in the Culd Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
a BFN 3.7/4 I-12 Unit 1
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UNITED STATES y
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g NUCLEAR REGULATORY COMMISSION j
W ASHING TO N, D. C. 20S$5
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TENNESSEEVALLEYAUTHORIE DOCXET NO. 50-260 P'10WNS FERRY NUCLEAR PLAN.', UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 138 License No. DPR-52 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 4,1987, complies with the standards arid requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations wt 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.
There is reasonable assurance (1) that the activities authorized by this amendment can be cor. ducted 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 cf this amendwnt will not be inimical to the comon oefense and security or to the health and safety of the public; and E.
The issuance of this ameridment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable recuiremeits have been satisfied.
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.(?) of Facility Operating License No. DPR-52 is hereby amended to read as follows:
(2) lechnical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment.Mo.138, 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 COMilSS10N t
6A.~--
Ga ry G.
ch, Ass ant Director for Projects TVA Projects Division Office of Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: February 12, 1988
ATTACPMENT TO LICENSE AMENCMENT !40.138 FACILITY 0?! RATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise the Aco2ndix 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 indicati'ng the area of change. Overleaf pages* are provided to naintain document completeness.
REMOVE INSERT 3.7/4.7-9 3.7/4.7-9*
3.7/4.7-10 3.7/4.7-10 3.7/4.7-11 3.7/4.7-11 3.7/4.7-12 3.7/4.7-12*
i i
s 3.P/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 4.7.A.
primary Containment 4.7.A.2. (Cont'd)
J.
Continuous Leak Rate Monitor When the primary 1
containment is inerted the containment shall be continuously monitored for gross leakage by review of the inerting system makeup requirements. This monitoring system may be taken out of service for maintenance but shall be returned to service as soon as practicable, k.
Drywell and Torus Surfaces The interior surfaces of the drywell and torus above the level one foot below the normal water line and outside surf aces of the torus below the water line shall be visually inspected each operating cycle for deterioration and any signs of structural damage with particular attention to piping connections and supports and for signs i
of distress or j
displacement, BFN 3.7/4.1-9 Unit 2
"3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment 4.7.A Primary Containment 3.
Preseure suppression Chamber -
- 3. Pressure Suppression Chamber-Reactor Buildinz Vacuum Briggers Reactor Buildina Vacuum Breakers
- a. Except as specifie0 in
- a. The pressure suppression 3.7.A.3.b below, two pressure chamber-reactor building suppression chamber-reactor vacuum breakers shall be building vacuum broakers shall exercised and the associated be OPERABLE at all times when instrumentation including primary containment integrity setpoint shall be functionally is required. The setpoint tested for proper operation of the differential pressure each three months.
Instrumentation which actuates the pressure suppression chamber-reactor building vacuum breakers shall be 0.5 psid.
- b. From and after the date
- b. A visual examination and that one of the pressure determination that the suppression chamber-reactor force required to open each building vacuum breakers is vacuum breaker (check valve) made or found to be INOPERABLE does not exceed 0.5 psid for any reason, raactor will be made each refueling operation is permissible only outage.
during the succeeding seven days, provided that the repair procedure does not violate primary containment integrity.
4.
Drywell-Pressure Suppression
- 4. Drywell-Pressure Suppression Chamber Vaerum Breakers Chamber Vacuum Breakers
- a. When primary containment is
- a. Each drywell-suppression required, all drywell-chamber vacuum breaker suppression chamber vacuum shall be exercised through breakers shall be OPERABLE an opening-closing cycle and positioned in the fully every month, closed position (except during testing) except as
- b. When it is determined that specified in 3.7.A.4.b and two vacuum breakers are 3.1.A.4.c., below.
INOPERABLE for opening at a time when operability is
- b. One drywell-suppression required, all other vacuum
]
chamber vacuum breaker may breaker valves shall be
)
be nonfully closed so long exercised immediately and as it is determined to be not every 15 days thereafter until more than 3* open as indicated the 7NOPERABLE valve has been by the position lights, returned to normal service.
1 BFN 3.7/4.7-10 Amendment No.138 Unit 2 l
1
3.7/4.7 CONTAIRMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary Containment 4.7.A Primary Containment 3.7.A.4 (Cont'd) 4.7.A.4 (Cont'd)
- c. Two drywell-suppression
- c. Once each operating cycle chamber vacuum breakers each vacuum breaker valve may be determined to be shall be inspected for INOPERABLE for opening.
proper operation of the valve and limit switches.
- d. If Specifications 3.7 A.4.a.
- d. A leak test of the drywell
.b or.c cannot be met, the to suppression chamber unit shall be placed in a structure shall be conducted l
Cold Shutdown condition in during each operating cycle.
an orderly manner within Accepu ble leak rate is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
0.09.J/Sec of primary I
containment atmosphere with l
1 psi differential.
5.
Oxygen Concentration
- 5. Oxygen Concentration n.
Containment atmosphere shall be
- a. The primary containment reduced to less than 4% oxygen oxygen concentration shall l
with nitrogen gas during reactor be measured and recorded l
power operation with reactor daily.
The oxygen coolant pressure above 100/psis, measurement shall be adjusted arcept as specified in 3.7.A.S.b.
to account for the uncertainty of the method used by adding a predetermined error function.
b.
Within the 24-hour period
- b. The methods used to measure subsequent to placing the reactor the primary containm6nt in the RUN mode following a shut-oxygen concentration shall i
down, the containment atmosphere be calibrated once every oxygen concentration shall be refueling cycle, reduced to less than 4% by volume and maintained in this condition.
Deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown, c.
If plant control air is being used
- c. The control air supply valve to supply the pneumatic control for the pneumatic control system inside primary containment, system inside the primary the reactor shall not be started, containment shall be verified or if at power, the reactor shall closed prior to reactor startup i
be brought to a Cold Shutdown and monthly thereafter.
condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l d.
If Specifie.ation 3.7.A.5.a and 1.7.A.5.b cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
BFN 3.7/4.7-11 Amendment No.138 Unit 2 l
l l
3.7/4.7 CONTAIMMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A.
Primary Containment 4.7.A.
Drywell-Suppression Chamber
- 6. Drywell-Suppression Chambar Differential Pressure Differential Pressure
- a. Differential pressure between
- a. The pressure differential' the drywell and suppression between the drywell and chahbor shall be maintained suppression chamber shall at equal to or greater than be recorded at least once 1.1 psid except as specified each shift.
in (1) and (2) below:
(1) This differential shall be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of achieving operating temperature and pressure. The differential pressure may be reduced to less than 1.1 psid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.
(2) This differential may be decreased to less than 1.1 psid for a maximum of four hours during required operability testing of the HPCI system. RCIC system and the drywell-pressure suppression chamber vacuum breakers,
- b. If the differential pressure of Specification 3.7.A.6.a cannot be maintained and the differential pressure cannot be restored within the subsequent six-hour period, an orderly shutdown shall be initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
BFN 3.7/4.7-12 Unit 2
,(penea h, UNITED STATES uq
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v.(
q NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C. 20555
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BriOWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No.113 License No. DPR-68 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated June 4, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
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.
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 Comission's regulations; D.
The issuance of this amendment will r.ct be inimical te the comon defense and security or to the health and safety of the public; and J
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.
' 1 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license arrendment 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. 113, 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 cf its date of issuance and shall be implecented within 60 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Ll-
\\
Gary G.
- h. Assistant Directer for Projects TVA Projects Division Office of Special Projects Attachinent:
Changes to the Technical Specifications Dr.te of Issuance: February 12, 1988 4
1
ATTACHMENT TO LICENSE AMENDMENT NO.ll3 FACILITY OPF. RATING LICENCE NO. DPR-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 indicati'ng the area of change. Overleaf pages* are provided to maintain document completeness.
i REMOVE INSERT 3.7/4.7-9 3.7/4.7-9*
3.7/4.7-10 3.7/4.7-10 3.7/4.7-11 3.7/4.7-11 3.7/4.7-12 3.7/4.7-12*
4 4
1
o 3.7/4.7 CONTAIMMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION
____SURVr1LLANCE REQUIREMENTS l
4.7.A.
Primary Containment 4.7.A.2. (Cont'd) j.
Continuous Leak Rate Monitorint When the primary contair11nt is inerted the cotitainment shall be continuously monitored for groer leakegn by review of the inerting system makeup requirementh. This monitoring system may be taken out of service for maintenance but shall be returned to service as soon as practicable.
k.
The interior surfaces of the drywell and torus above the level one foot below the normal water line and outside surfaces of the torus below the water line shall be visually inspected each operating cycle for deterioration and any signs of structural damage with particular attention to piping connections and supports and for signs of distress or displacement.
BFN 3,7/4,7_g Unit 3
t e
4 3.7/4.7 CONTAIRM2NT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE MECUIECMEhrS 3.7.A PPIKARY CONTAIKKENT 4.7.A PRIMARY CONTAINMENT 3.
Pressure Suppression Chr.mber -
- 3. Pressure Suppression _ Chamber-Reactor Building Vacuum Breakers Reactor Bui(sica.ig=uum Ereakers
- a. Except as specified in
- a. The pressure suppresolon 3.'/'A.3.b below, two pressure chamber-reactor building suppression chamber-reactor vacuum breakers shall be building vacuum breakers shall oxercised and *he associated be OPERABLE st all times when instrumentation including primary :ontainment integrity setpoint shall be checked i
is required.
The setpoint for proper operation of the differential pressure sach three months.
instrumentation which actucten the pressure suppression chamber-reactor building vacuum breakers shall be N
0.5 psid.
- b. From and after the date
- b. A visual examination and 4
that one of the preseure determinacion that the supprsssion chamber-rer.ctor force required to open each building vacuum breakers is vacuum breake'. (check valve) made or found to be INOFERABLE does not exceed 0.5 psid for any reason, reacter will be made each refueling operation is permissible only c.tage, during the succeeding seven days, pecvided that the repair procedure does not violate primary containment integrity.
4.
Drywell-Pressure Suportssion
- 4. Drywell-Pressure Suppression Chamber Vacuum Breakers Char.ber Vacuum Breakers
- a. When primary containment it
- a. Each drywell-suppression required, all drywell-chamber va:uum breaker suppression chamber vacuum shall be exercised through breakers cha'.1 be OPERABLE als opening-closing cycle and positicaed in the fully evary month, closed posttion (except durir.g testing) except as
- b. When it is determined that specified in 3.7.A.4.b and two vacuum breakers are 3.7.A.4.c below.
INOPERABLT for opening at a tira when operability is
- b. One drywell-suppression required, all other vacuum chamber vacuum breaker may breaker valves shall be be nonfully closed so long exercised inmediately and as it is determined to bc not eve y 15 days thereafter until more thar. 3' open as indicated the INOPERABLE valve has been by the position lights.
retu rned to normal service.
BFN Unit 3 3.7/4.1-10 Amendment No. 113
s
- 3. 7/4. 7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A Primary containpent 4.7.A Primary Containment
- 3. 7. A.4 (Cont'd) 4.7.A.4 (Cent'd)
- c. Two drywell-suppression
- c. Onco each operating cycle, chamber vacuum breakers each vacuum breaker valve may be determined to be shall be inspected for INOPERABLE for opening.
Proper operati)n of the valve and limit switches, a
- d. If Specification; 3.7.A.4.a.
- d. A leak test of the drywell 3.7.A.4.b or 3.7.A.4.c.
to suppression chamber cannot be met, the structure shall be conducted unit shall be placed during each operating cycle, in a Cold Shutdown Acceptable leak rate is condition in an orderly 0.09 lb/sec of primary manner within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, containment atmosphere with I psi differential.
5.
Oxyaen concentration
- 5. Oxyaen Concentrat*on a.
Containment atmosphere shall be
- a. The primary containment reduced t0 less than 4% oxygen oxygen concentration shall with nitrogen Sr.s during reactor be measured and recorded powcr operation with reactor daily. The oxygen coolant pressure above 100/psig, measurement shall be adjusted except as specified in *.7.A.S.b.
to account for the uncertalaty of the method used by adding a predetermined error function.
b.
Within the 24-hour period
- b. The methods used to measure subsequent to placing the reactor the primary containment in the RUN mode following a shut-oxygen concentration shall down, the contair. ment atmosphare be calibrated once every oxygen concentration shall be rofueling cycle, reduced to less than 4% by volume and maintained in this condition.
Deinerting may commence 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a shutdown.
c.
If plant control air is being used
- c. The control air supply valve to supply the pneumatic control for the pneumatic control syt tan inside primary containmer.t, system inside the primary the coactor shall not be started, containment shall be verified og if at power, the reactor shall closed prior to reactor startup be brought to a Cold Shutdown ano monthly thereafter.
condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
l d.
If the specifications of 3.7.A.S.a through 3.7.A.S.b cannot be met, an orderly shutdown shall be initiated and the reactor : hall be in a Cold Shutdown condition Dend9ent No.113 BFN 3.7/g.1-11 Unit 3
e 3.7/4.7 CONTAINMENT SYSTEMS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7.A.
Primary Containment 4.7.A.
Drywell-Suppression Chamber
- 6. Drywell-Suppression Chamber Differential Pressure Differential Pressure
- a. Differential pressure between
- a. The pressure differential the drywell and suppression between the drywell and chamber shall be maintained suppression chamber shall at equal to or greater than be recorded at least once 1.1 paid except as specified each shift.
in (1) and (2) below:
(1) This differential shall be established within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of achieving operating tamperature and pressure. The differential pressure may be reduced to lete.
than 1.1 psid 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to a scheduled shutdown.
(2) This differential may be decreased to less than 1.1 psid for a maximum of four hours during required operability testing of the HpCI system, RCIC system and the drywell-pressure suppression chamber vacuum breakars.
- b. If the differential pressure j
of Specificatinn 3.7.A.6.a i
cannot be maintained and the differential pecssure cannot be restored within the i
subseq'sent six-hour period, an orderly shutdown shall bo initiated and the reactor shall be in the Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
2 BFN 3.7/4.7-12 Unit 3 i
J
.