ML17333A715: Difference between revisions

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{{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1245 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 96i2270ii2 96i220 PDR ADQCK 050003i5 (I P PDR REACTOR CCOLAHT SYS~c.3'l4;4.IQ;STRUCTURAL LhTEGRITY ASHE CODE CLASS I 2 and 3 CCHPOHEHTS LIHITIHG COHDITIOH FOR OPERATIOH 3.4.10.1 The struc-.ural integrity of BSHE Code Class 1, 2 and 3 camoonents shall be maintained in acŽ"roance with Speci, icatian 4.4.10.1~APPLICABILITY:
{{#Wiki_filter:ATTACHMENT 2 TO AEP:NRC:1245 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 96i2270ii2 96i220 PDR ADQCK 050003i5     (I P             PDR
Af L BODES ACT.QM:)I I a.b.Vith the structural integrity af any ASHE Cade Class 1 comoonent(s) not conforming ta the abave requirements, resmre the struc:ural integri-y af the affected component,'s) ta within its limit or isolate the affec=ed camoonent(s) prior ta ncreasing the Reac.or Coolant System temoerature mor.han 50'F aoave we minimum temperature required by HGT c"nsiderat cns.Mith".e str=-.ral integri:y af anv ASH=Cade Class 2 conoonent(s) not conforming a:..e above recui rements, restore the str ctural integri y of:he af..ed c"moonent',s)
 
=-within i w limit ar isclate the affec=ed c"moonent(s}
REACTOR CCOLAHT SYS~c.
or.'cr:":ncrzas ng the Re ctor Ccolant System temoerature
3'l4;4. IQ; STRUCTURAL LhTEGRITY ASHE CODE CLASS     I 2 and 3 CCHPOHEHTS LIHITIHG COHDITIOH     FOR OPERATIOH 3.4.10.1 The struc-.ural integrity of BSHE Code Class 1, 2 and             3 camoonents shall be maintained in ac'"roance with Speci, icatian 4.4.10.1           ~
~"ove 2CC."-.Vith the s".ru~ural integri.y c, any'SHc not confoming ta the abcve recuirements, integrity of t,.".e af,e'cted c"moonent',s)
APPLICABILITY: Af L       BODES ACT.QM:
:=the.affec-ad c"mpcnent(s) fr.m service.'."ce C'iass 3 c";.,cc,.en,'s)ros ore the str c:ural i thi n i ts 1 imi: or isolate d.The provisions of Soecificat-on 3.0.4 ar not applicable.
: a. Vith the structural integrity af       any ASHE Cade Class     1 comoonent(s) not conforming ta the abave requirements, resmre the struc:ural integri-y af the affected component,'s) ta within its limit or isolate the affec=ed camoonent(s) prior ta ncreasing the Reac.or Coolant System temoerature mor .han 50'F aoave we minimum temperature
SlRV'EILANCc RcQUIRPBYS 4.4.10.1 In addition w the requir ments of Soecif'.cation 4.0.5, each reactor coolant pump fi~neel shall be inspec=ed D.C.COOK-UNXT 1 3/4 4-33 Amendment No.98 insert A by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
)                required by HGT c"nsiderat cns.
Pc&CHlR CCOU8T SY~3.4.10~iUCTURAL IHTcGRI7f ASHY CQQE CLASS 1.2 and 3 CQHPQHBlTS L~H6 CQHOITZOH FOR OPHATTOH L/3.4.10.1 The s~wraI fn~~ri.g of AM hda Class I, 2 and 3 c~onenw sha11 be mafntained in accords with Specificat',on 4.4.10.1.Appuua>I.an:
I I
Au.mam~iONi Vith~%a strucmra1<ntegrity of any ASIDE Ccc!e C1ass 1 c~onen (s)not conforming to the above mq'uirments, res-"m the strururaI integ.ity of Ne affec~ct ccamonent(s}
: b. Mith ".e str =-. ral integri:y af anv ASH=     Cade Class     2 conoonent(s) not conforming a :..e above recui rements,     restore the str ctural integri y of :he af.. ed c"moonent',s) =-       within i w limit ar isclate the affec=ed c"moonent(s} or .'cr :" :ncrzas     ng the Re     ctor Ccolant System temoerature ~"ove 2CC ."-.
M w$'Min i~I'mt or fsQIaM~e af ected ceaccnent,'s) prior ts incr asian"e Reac"r Coolant Sys~~erasure mre~SO~7 above"~mini~~eratu~~unbred by NOT considerations.
Vith the s".ru~ural integri     .y c, any 'SHc       C'iass  3 c";.,cc, .en,'s) not confoming ta the abcve recuirements, ros ore the str c:ural service.'."ce integrity of t,.".e af,e'cted c"moonent',s) := i thi n i ts imi: or isolate 1
8th~~a st.W~ra1 fntagrfty of any ASIDE C"Ce Class 2 cwonent(s) not c"nforaing to Ale above requirements, answer tM st.~-raI fntegri y of the affected cccconent(s) w wi~5fn fts I'.sit or isoIata the af ec~caeyonent(s) prior to increasing Ne Rear"'r Coo1an: Sys~tennerztura above 8lQ~F.c 0th".e s~-.ac-"raI inta~i~g of any APE no-c"nforaing to Ne move~ufrmnts, integri.o.C..e a, ared anent(s)--
the. affec-ad c"mpcnent(s) fr.m
t0e af i ac~~onent(5)fr<<2 service.Cede Class 3 c~onent(s) res"w e v~'retral wit:,in ia lid"".isoIa->i,e provisions of Spec";fcaticn 3.0.'r not acpI',cable.
: d. The  provisions of Soecificat-on 3.0.4 ar      not applicable.
RPgE:~re:-
SlRV'EILANCc RcQUIRPBYS 4.4.10.1    In addition w the requir ments of Soecif'.cation 4.0.5, each reactor coolant   pump fi~neel shall   be inspec=ed D. C. COOK   - UNXT 1                 3/4 4-33             Amendment No. 98
R U R~PPi5<.4.10.1 ln add'.ion a the requireena of Specifiat'.cn 4.0."-, each~ac-"r coolan pa=lywnee1 shall be insaec~+~5c~P Insert B by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
 
0 ATTACHMENT 3 TO AEP:NRC:1245 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES 3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 Gild 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.APPLICABILITY:
insert A by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
ALL MODES ACTION: With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of th affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
 
With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.The provisions of Specification 3.0.4 are not applicable.
Pc&CHlR CCOU8T       SY~
SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.COOK NUCLEAR PLANT-UNIT I Page 3/4 4-33  
3.4. 10 ~iUCTURAL IHTcGRI7f ASHY CQQE CLASS       1. 2 and 3 CQHPQHBlTS L~H6 CQHOITZOH FOR             OPHATTOH L/
~"'/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 gild 3 COMPONENTS LIMITING CONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.APPLICABILITY:
3.4.10.1   The s     ~wraI fn~~ri.g         of AM hda Class I, 2 and       3 c~onenw sha11 be mafntained         in accords     with Specificat',on 4.4.10.1.
ALL MODES ACTION: ao With the structural integrity of any ASME Code Class 1 c"mponent(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
Appuua>I.an:         Au. mam
b.With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.c.With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.d.-The provisions of Specification 3.0.4 are not applicable.
~iONi Vith     ~%a strucmra1     <ntegrity of any ASIDE Ccc!e C1ass 1 c~onen (s) not conforming to the above mq'uirments, res-"m the strururaI integ.ity of Ne affec~ct ccamonent(s} M w$ 'Min i~ I'mt or fsQIaM
SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over.the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing)of exposed surfaces defined by the volume of..e disassembled flywheels once every 10 years.COOK NUCLEAR PLANT-UNIT 2 Page 3/4 4-31}}
            ~e af ected ceaccnent,'s) prior ts incr asian           "e Reac "r Coolant Sys~ ~erasure mre
          ~unbred by NOT considerations.
                                            ~  SO~7 above   "~ mini~ ~eratu~
8th     ~~a st. W~ra1 fntagrfty of any ASIDE C"Ce Class 2 cwonent(s) not c"nforaing to Ale above requirements, answer tM st. ~-raI fntegri y of the affected cccconent(s) w wi~5fn fts I'.sit or isoIata the af ec~ caeyonent(s) prior to increasing Ne Rear "'r Coo1an:
Sys~ tennerztura above 8lQ~F.
c   0th       ".e s~-.ac-"raI inta~i~g of any APE       Cede Class  3  c~onent(s) no- c"nforaing to           Ne move ~ufrmnts,       res  "w    e  v~'retral integri.       o. C..e a, ared   anent(s)--       wit:,in ia lid      "". isoIa-t0e af i ac~       ~onent(5) fr<<2       service.
          >i,e   provisions of     Spec"; fcaticn 3.0.'r     not acpI',cable.
RPgE:~re:-     R   U   R~PPi5
<.4.10.1   ln add'. ion   a the requireena     of Specifiat'.cn 4.0."-,   each   ~ac-"r coolan   pa=     lywnee1 shall be insaec~
    +~5c ~ P
 
Insert B by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
 
0 ATTACHMENT 3 TO AEP:NRC:1245 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES
 
3/4     LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4   REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS       1 2 Gild 3 COMPONENTS LIMITINGCONDITION FOR OPERATION 3.4.10.1       The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.
APPLICABILITY:           ALL MODES ACTION:
With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of th affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.
With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.
The provisions   of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.10.1       In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.
COOK NUCLEAR PLANT-UNIT I                       Page 3/4 4-33
 
~
  " '/4         LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4     REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS       1 2 gild 3 COMPONENTS LIMITINGCONDITION FOR OPERATION 3.4.10.1       The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4. 10.1.
APPLICABILITY:           ALLMODES ACTION:
ao     With the structural integrity of any ASME Code Class 1 c"mponent(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.
: b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above   200'F.
: c. With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.
: d. -
The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.4.10.1       In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over. the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of ..e disassembled flywheels once every 10 years.
COOK NUCLEAR PLANT-UNIT2                        Page 3/4 4-31}}

Latest revision as of 13:12, 22 October 2019

Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys
ML17333A715
Person / Time
Site: Cook  American Electric Power icon.png
Issue date: 12/20/1996
From:
AMERICAN ELECTRIC POWER CO., INC.
To:
Shared Package
ML17333A714 List:
References
NUDOCS 9612270112
Download: ML17333A715 (9)


Text

ATTACHMENT 2 TO AEP:NRC:1245 EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 96i2270ii2 96i220 PDR ADQCK 050003i5 (I P PDR

REACTOR CCOLAHT SYS~c.

3'l4;4. IQ; STRUCTURAL LhTEGRITY ASHE CODE CLASS I 2 and 3 CCHPOHEHTS LIHITIHG COHDITIOH FOR OPERATIOH 3.4.10.1 The struc-.ural integrity of BSHE Code Class 1, 2 and 3 camoonents shall be maintained in ac'"roance with Speci, icatian 4.4.10.1 ~

APPLICABILITY: Af L BODES ACT.QM:

a. Vith the structural integrity af any ASHE Cade Class 1 comoonent(s) not conforming ta the abave requirements, resmre the struc:ural integri-y af the affected component,'s) ta within its limit or isolate the affec=ed camoonent(s) prior ta ncreasing the Reac.or Coolant System temoerature mor .han 50'F aoave we minimum temperature

) required by HGT c"nsiderat cns.

I I

b. Mith ".e str =-. ral integri:y af anv ASH= Cade Class 2 conoonent(s) not conforming a :..e above recui rements, restore the str ctural integri y of :he af.. ed c"moonent',s) =- within i w limit ar isclate the affec=ed c"moonent(s} or .'cr :" :ncrzas ng the Re ctor Ccolant System temoerature ~"ove 2CC ."-.

Vith the s".ru~ural integri .y c, any 'SHc C'iass 3 c";.,cc, .en,'s) not confoming ta the abcve recuirements, ros ore the str c:ural service.'."ce integrity of t,.".e af,e'cted c"moonent',s)  := i thi n i ts imi: or isolate 1

the. affec-ad c"mpcnent(s) fr.m

d. The provisions of Soecificat-on 3.0.4 ar not applicable.

SlRV'EILANCc RcQUIRPBYS 4.4.10.1 In addition w the requir ments of Soecif'.cation 4.0.5, each reactor coolant pump fi~neel shall be inspec=ed D. C. COOK - UNXT 1 3/4 4-33 Amendment No. 98

insert A by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.

Pc&CHlR CCOU8T SY~

3.4. 10 ~iUCTURAL IHTcGRI7f ASHY CQQE CLASS 1. 2 and 3 CQHPQHBlTS L~H6 CQHOITZOH FOR OPHATTOH L/

3.4.10.1 The s ~wraI fn~~ri.g of AM hda Class I, 2 and 3 c~onenw sha11 be mafntained in accords with Specificat',on 4.4.10.1.

Appuua>I.an: Au. mam

~iONi Vith ~%a strucmra1 <ntegrity of any ASIDE Ccc!e C1ass 1 c~onen (s) not conforming to the above mq'uirments, res-"m the strururaI integ.ity of Ne affec~ct ccamonent(s} M w$ 'Min i~ I'mt or fsQIaM

~e af ected ceaccnent,'s) prior ts incr asian "e Reac "r Coolant Sys~ ~erasure mre

~unbred by NOT considerations.

~ SO~7 above "~ mini~ ~eratu~

8th ~~a st. W~ra1 fntagrfty of any ASIDE C"Ce Class 2 cwonent(s) not c"nforaing to Ale above requirements, answer tM st. ~-raI fntegri y of the affected cccconent(s) w wi~5fn fts I'.sit or isoIata the af ec~ caeyonent(s) prior to increasing Ne Rear "'r Coo1an:

Sys~ tennerztura above 8lQ~F.

c 0th ".e s~-.ac-"raI inta~i~g of any APE Cede Class 3 c~onent(s) no- c"nforaing to Ne move ~ufrmnts, res "w e v~'retral integri. o. C..e a, ared anent(s)-- wit:,in ia lid "". isoIa-t0e af i ac~ ~onent(5) fr<<2 service.

>i,e provisions of Spec"; fcaticn 3.0.'r not acpI',cable.

RPgE:~re:- R U R~PPi5

<.4.10.1 ln add'. ion a the requireena of Specifiat'.cn 4.0."-, each ~ac-"r coolan pa= lywnee1 shall be insaec~

+~5c ~ P

Insert B by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.

0 ATTACHMENT 3 TO AEP:NRC:1245 PROPOSED REVISED TECHNICAL SPECIFICATION PAGES

3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 Gild 3 COMPONENTS LIMITINGCONDITION FOR OPERATION 3.4.10.1 The structural integrity of the ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4.10.1.

APPLICABILITY: ALL MODES ACTION:

With the structural integrity of any ASME Code Class 1 component(s) not conforming to the above requirements, restore the structural integrity of th affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.

With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.

With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of the disassembled flywheels once every 10 years.

COOK NUCLEAR PLANT-UNIT I Page 3/4 4-33

~

" '/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.10 STRUCTURAL INTEGRITY ASME CODE CLASS 1 2 gild 3 COMPONENTS LIMITINGCONDITION FOR OPERATION 3.4.10.1 The structural integrity of ASME Code Class 1, 2 and 3 components shall be maintained in accordance with Specification 4.4. 10.1.

APPLICABILITY: ALLMODES ACTION:

ao With the structural integrity of any ASME Code Class 1 c"mponent(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.

b. With the structural integrity of any ASME Code Class 2 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) prior to increasing the Reactor Coolant System temperature above 200'F.
c. With the structural integrity of any ASME Code Class 3 component(s) not conforming to the above requirements, restore the structural integrity of the affected component(s) to within its limit or isolate the affected component(s) from service.
d. -

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.10.1 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected by either qualified in-place UT examination over. the volume from the inner bore of the flywheel to the circle of one-half the outer radius or a surface examination (magnetic particle testing and/or penetrant testing) of exposed surfaces defined by the volume of ..e disassembled flywheels once every 10 years.

COOK NUCLEAR PLANT-UNIT2 Page 3/4 4-31