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{{#Wiki_filter:*, 1 e ENCLOSURE 413 293 79072663\.  
{{#Wiki_filter:,
'...Revised 1-10-78 LIMITING CONDITIONS FOR OPERATION SURVEI LI.ANCE REQUIREMENTS
* 1 e
'. 6['Bitiq1_ ,S_12T EM DO_Ulygfly 4.6 PMPAi1Y LYSTF.ti POUNDARY v 5.St eady sta te operation with both G.Structural Integrity recirculation puipr, out of ser-vice for up to 12 hr*, is per-1. Inservice inspection of ASME mitted.During sorh interval Code Class 1, class 2, and restart of the recin.ulation Class 3 components shall be per-pumps is permitted, provided the formed in accordance with lcn? din.harge tcnT.rature is Section XI of the ASME Boiler Within 750F of the saturation and Pressure Vessel Code and tn.:pera'.ure of the relctor applicable Addenda as required vessel va ter as determined by by 10 CFR 50, Section 50.55a(g), done pressure. The total except where specific written elopced time in natural circula-relief bn.s been granted by NRC tion 3r.d one pu+p cpercition li.ust Pursuant to 10 CFR 50, Section be ne greater than b1 hrs.
ENCLOSURE 413 293         79072663\
: 50. 55a (g) (6) (1) .
                            .
G.structural Integrity 1.The structural integrity of the primary s ystem shall be maintained at the level required by the original acceptance standards throughout the life of the plant.The reactor shall be maintained in a cold shutdowa conditicn until cach .
 
Indication of a gross def ect ,which could adversely afface +he structural integrity of the reactor coolant prassure boundary, has 4.Additional bv .1 investigated and inspections shall be evaluated.
            '
perf ormed on certain circunf erentia1 pipe welds as listed to provide additional protection against pipe whip, which could damage auxiliary and control systems.Feedwater- GIV-9, m4-13, GIN-12, GFW-26, KFv-31, GiU-21, r[E F~,i- 3 9 , CPrl- 15, KIH- 3 0, and GIM-3/  
  .                   .
--SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION
.
_.4.6 PRIMARY SYSTEM BOUNDARY 3.b PRIMARY SYSTEM DOUliDARY Main steam-GMS-6, KMS-24, GMS-32, KMS-104, GMS-15, and GMS-24
Revised 1-10-78 LIMITING CONDITIONS FOR OPERATION                 SURVEI LI.ANCE REQUIREMENTS
_RHR- DSR HR- 6, DSRHR-7, and DSRER-L!
    '. 6     ['Bitiq1_ ,S_12T EM DO_Ulygfly             4.6 PMPAi1Y LYSTF.ti POUNDARY v
Core Spray-DSCS-12, DSC S- 11, DSCS- 5, and DSCS-4 Reactor Cleanup-DSRWC-4, DSRWC-3, DSRWC-6, and DSFWC-5 HPCI-TIG'C I- 7 0 THPCI-70A THPCI-71, and THF C I-7 2 R EFERENCE 1.Plant dafety Analycis (BFNT PSAR subsection 4 . 1,~. )
: 5. St eady sta te operation with both       G. Structural Integrity recirculation puipr, out of ser-vice for up to 12 hr*, is per-                 1. Inservice inspection of ASME mitted. During sorh interval                       Code Class 1, class 2, and restart of the recin.ulation                       Class 3 components shall be per-pumps is permitted, provided the                   formed in accordance with lcn? din.harge tcnT.rature is                     Section XI of the ASME Boiler Within 750F of the saturation                       and Pressure Vessel Code and tn.:pera'.ure of the relctor                       applicable Addenda as required vessel va ter as determined by                     by 10 CFR 50, Section 50.55a(g),
/~f ['7 197 295  
done pressure. The total                           except where specific written elopced time in natural circula-                   relief bn.s been granted by NRC tion 3r.d one pu+p cpercition li.ust             Pursuant to 10 CFR 50, Section be ne greater than b1 hrs.                         50. 55a (g) (6) (1) .
....Page 228 The requested char.ge to BASES uction 3.6.G/4.6.G is being withdrawn.
G.       structural Integrity
: 1. The structural integrity of the primary s ystem shall be maintained at the level required by the original acceptance standards throughout the life of the plant. The reactor shall be maintained in a cold shutdowa conditicn until cach .
Indication of a gross def ect ,which could adversely afface +he structural integrity of the reactor coolant prassure boundary, has                   4.     Additional bv .1 investigated and                           inspections shall be evaluated.                                       perf ormed on certain circunf erentia1 pipe welds as listed to provide additional protection against pipe whip, which could damage auxiliary and control systems.
Feedwater- GIV-9, m4-13, GIN-12, GFW-26, KFv-31, GiU-21, r[                               E F~,i- 3 9 , CPrl- 15, KIH- 3 0, and GIM-3/
 
      -
-
SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION                                                       _
  .
4.6 PRIMARY SYSTEM BOUNDARY 3.b PRIMARY SYSTEM DOUliDARY Main steam-GMS-6, KMS-24, GMS-32, KMS-104, GMS-15, and GMS-24
_
RHR          - DSR HR- 6, DSRHR-7, and DSRER-L!
Core Spray-DSCS-12, DSC S- 11, DSCS- 5, and DSCS-4 Reactor Cleanup       -DSRWC-4, DSRWC-3, DSRWC-6, and DSFWC-5 HPCI         -TIG'C I- 7 0 THPCI-70A THPCI-71, and THF C I-7 2 R EFERENCE
: 1. Plant dafety Analycis (BFNT PSAR subsection 4 . 1,~. )
/~
197 f ['7 295
 
  .. .
.
Page 228 The requested char.ge to BASES uction 3.6.G/4.6.G is being withdrawn.
No changes are proposed to Browns Ferry unit 3 technical specifications page 228 in connection with the inservice inspection program.
No changes are proposed to Browns Ferry unit 3 technical specifications page 228 in connection with the inservice inspection program.
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296}}

Revision as of 00:29, 8 October 2019

Revised Tech Specs Re Inservice Insp Program
ML19225C178
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 07/20/1979
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML19225C174 List:
References
NUDOCS 7907260631
Download: ML19225C178 (4)
v • d • e


Text

,

  • 1 e

ENCLOSURE 413 293 79072663\

.

'

. .

.

Revised 1-10-78 LIMITING CONDITIONS FOR OPERATION SURVEI LI.ANCE REQUIREMENTS

'. 6 ['Bitiq1_ ,S_12T EM DO_Ulygfly 4.6 PMPAi1Y LYSTF.ti POUNDARY v

5. St eady sta te operation with both G. Structural Integrity recirculation puipr, out of ser-vice for up to 12 hr*, is per- 1. Inservice inspection of ASME mitted. During sorh interval Code Class 1, class 2, and restart of the recin.ulation Class 3 components shall be per-pumps is permitted, provided the formed in accordance with lcn? din.harge tcnT.rature is Section XI of the ASME Boiler Within 750F of the saturation and Pressure Vessel Code and tn.:pera'.ure of the relctor applicable Addenda as required vessel va ter as determined by by 10 CFR 50, Section 50.55a(g),

done pressure. The total except where specific written elopced time in natural circula- relief bn.s been granted by NRC tion 3r.d one pu+p cpercition li.ust Pursuant to 10 CFR 50, Section be ne greater than b1 hrs. 50. 55a (g) (6) (1) .

G. structural Integrity

1. The structural integrity of the primary s ystem shall be maintained at the level required by the original acceptance standards throughout the life of the plant. The reactor shall be maintained in a cold shutdowa conditicn until cach .

Indication of a gross def ect ,which could adversely afface +he structural integrity of the reactor coolant prassure boundary, has 4. Additional bv .1 investigated and inspections shall be evaluated. perf ormed on certain circunf erentia1 pipe welds as listed to provide additional protection against pipe whip, which could damage auxiliary and control systems.

Feedwater- GIV-9, m4-13, GIN-12, GFW-26, KFv-31, GiU-21, r[ E F~,i- 3 9 , CPrl- 15, KIH- 3 0, and GIM-3/

-

-

SURVEILLANCE REQUIREMENTS LIMITING CONDITIONS FOR OPERATION _

.

4.6 PRIMARY SYSTEM BOUNDARY 3.b PRIMARY SYSTEM DOUliDARY Main steam-GMS-6, KMS-24, GMS-32, KMS-104, GMS-15, and GMS-24

_

RHR - DSR HR- 6, DSRHR-7, and DSRER-L!

Core Spray-DSCS-12, DSC S- 11, DSCS- 5, and DSCS-4 Reactor Cleanup -DSRWC-4, DSRWC-3, DSRWC-6, and DSFWC-5 HPCI -TIG'C I- 7 0 THPCI-70A THPCI-71, and THF C I-7 2 R EFERENCE

1. Plant dafety Analycis (BFNT PSAR subsection 4 . 1,~. )

/~

197 f ['7 295

.. .

.

Page 228 The requested char.ge to BASES uction 3.6.G/4.6.G is being withdrawn.

No changes are proposed to Browns Ferry unit 3 technical specifications page 228 in connection with the inservice inspection program.

41'%

296

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