|
|
(One intermediate revision by the same user not shown) |
Line 50: |
Line 50: |
| ! PROJECT MANAGEMEhT REACTOR SAFETY - | | ! PROJECT MANAGEMEhT REACTOR SAFETY - |
| -T'ISENI!UT SITE ANALYSIS BOYD ROSS Wi!AO VOLD:ER P. COLLINS NCVAK _ | | -T'ISENI!UT SITE ANALYSIS BOYD ROSS Wi!AO VOLD:ER P. COLLINS NCVAK _ |
| WAER BUNCH ll0USTON '- - h- COLLINS R0_SZTOCZY *CIR]]R!CI:R 1lETE,RSON Cl!ECK - | | WAER BUNCH ll0USTON '- - h- COLLINS R0_SZTOCZY *CIR))R!CI:R 1lETE,RSON Cl!ECK - |
| M IMES KREGER MM_LTZ IIELTEMMS AT & I i | | M IMES KREGER MM_LTZ IIELTEMMS AT & I i |
| SITE SAFETY & UNVIRC SKOVHOLT SAT.TZMAN . | | SITE SAFETY & UNVIRC SKOVHOLT SAT.TZMAN . |
Line 72: |
Line 72: |
| Not Applicab] | | Not Applicab] |
| 6.6 Integrally h'elded Not Applicabl ' | | 6.6 Integrally h'elded Not Applicabl ' |
| i Yalve Supports | | i Yalve Supports 4.2.3 |
| ;
| |
| 4.2.3 | |
| %e structural integrity of the reactor coolant system bout 'I shall be r,aintained at the level required by the original tance | | %e structural integrity of the reactor coolant system bout 'I shall be r,aintained at the level required by the original tance |
| ( andards throughout the life of the station. Any e-j as a result of the tests outlined in Tabic IS-261 of Sectic i j of the code, that defects have developed or grown, shall bt investigated. i 4.2.4-To assure the structural integrity of the reactor internals l t out the life of the unit, the two sets of nain internals bc I (connecting the core barrel to the core support shield and ' | | ( andards throughout the life of the station. Any e-j as a result of the tests outlined in Tabic IS-261 of Sectic i j of the code, that defects have developed or grown, shall bt investigated. i 4.2.4-To assure the structural integrity of the reactor internals l t out the life of the unit, the two sets of nain internals bc I (connecting the core barrel to the core support shield and ' |
|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs ML20197A8421997-12-12012 December 1997 Proposed Tech Specs Re Establishment of Alternate Repair Criteria for Outer Diameter Intergranular Attack in Upper Tubesheet of Unit 1 SGs ML20211C6441997-09-23023 September 1997 Proposed Tech Specs,Modifying RPS & ESFAS Trip Setpoint & Allowable Values for SG Low Pressure ML20211C8911997-09-23023 September 1997 Proposed Tech Specs Reducing Min Required Reactor Coolant Sys Flow Rate Requirements Until ANO-2 SGs Are Replaced ML20151J3371997-07-28028 July 1997 Proposed Tech Specs,Modifying Actions Associated W/Ts Table 3.3-1 for Reactor Protective Instrumentation & Table 3.3-3 for Esfa Sys Instrumentation ML20149K0551997-07-21021 July 1997 Proposed Tech Specs,Revising Surveillance Testing Requirements for Facility EFW Sys as Specified in Specification 4.7.1.2 ML20141C5641997-06-18018 June 1997 Proposed Tech Specs Changes Restoring Table 2 to Table II & Revision to One of Offsite Dose Calculation Manual, Pages Previously Submitted.Also Includes Amended Pages Modified to Amends Issued Since Change Request Submitted ML20141A8001997-05-0808 May 1997 Proposed Tech Specs 3/4.3.1 & 3/4.3.2 Requesting Removal of Reference to CE NPSD-576 ML20138H8521997-05-0202 May 1997 Proposed Tech Specs,Submitting Rev to Original TS Change Request to Reduce Limit Specified in Section 3.1.6.3.b for Leakage Through SG Tubes of Any One Sg,Per SG Tube Insp Surveillance Requirements ML20138D6411997-04-24024 April 1997 Proposed Tech Specs Revising Requirements for Sample Scope Initial Size & Expansion for Inservice Insp of Steam Generator Tube Sleeves ML20141H2621997-04-18018 April 1997 Proposed Tech Specs,Permitting Delay of Scheduled three-yr Inspections of Flywheels on All Four RCPs Until Completion of 2R13 Refueling Outage,Scheduled for Winter of 1998-99 1999-09-07
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217N3171999-10-19019 October 1999 Rev 1,change 024-01-0 to OP-1903.011, Emergency Response Notifications ML20217J7641999-10-0505 October 1999 Rev 1 to Unit 1 Technical Requirement Manual, Replacing Index Page ML20216G0881999-09-19019 September 1999 Proposed Tech Specs Pages,Changing TS 4.18.5.a.9 & Associated Bases for One Cycle of Operation Through End of Cycle 16 for Suppl Use of OTSG Repair Roll Technology ML20212F5851999-09-17017 September 1999 Proposed Tech Specs Pages,Changing TS by Revising Curie Limits for Radioactive Gas Storage Tanks ML20216G0721999-09-17017 September 1999 Proposed Tech Specs,Revising Once Through SG Tubing Surveillance Requirements to Provide Alternate Repair Criteria for Volumetric Integranular Attack ML20211P0061999-09-0707 September 1999 Proposed TS in Support of SG Outer Diameter Intergranular Attack Alternate Repair Criteria ML20211B3291999-08-19019 August 1999 Proposed TS 4.18.3.a.4 Clarification Supporting Tube End Cracking Alternative Repair Criteria ML20211C4101999-08-18018 August 1999 Proposed Tech Specs Removing Requiremets for Tube Repair (Sleeving) & Clarifying Requirements for Preservice & ISI of Tubes to Facilitate Replacement of Original SGs ML20211C1701999-08-18018 August 1999 Proposed Tech Specs Revising ESAS Low RCS Pressure Setpoint to Ensure That TS Adequately Bounds Safety Analysis ML20210N5541999-08-0404 August 1999 Rev 28,Permanent Change 4 to OP-1903.061, Communication Equipment Test ML20210N5571999-08-0404 August 1999 Rev 23,Permanent Change 5 to OP-1903.011, Emergency Response/Notifications ML20210K5121999-07-29029 July 1999 Proposed Tech Specs,Revising Requirements Associated with Plant Station Batteries & DC Sources to 125 Vdc Switchyard Distribution Sys ML20210K3571999-07-29029 July 1999 Proposed Tech Specs Revising SRs Pertaining to ISI Requirements for SG Tube Circumferential Cracking at top-of-tubesheet During 2P99 Planned mid-cycle Outage ML20209H5811999-07-14014 July 1999 Proposed Tech Specs Revising RB Structural Integrity Requirements Re ISI Reporting for Containment Structures, Tendons & Anchorages ML20209H8701999-07-14014 July 1999 Proposed Tech Specs 6.2.2 & 6.2.2.h,replacing Functional Description of Operations Staff Middle Manager with Ref to Functional Description Assistant Operations Manager & Revising TS Table 6.2-1 Item 5 & TS 6.2.2.f ML20209H9721999-07-14014 July 1999 Proposed Tech Specs Changes for Elimination of Programmatic Requirements Associated with PASS & Regulatory Relief from PASS Requirements of NUREG-0737 & RG 1.97 ML20195D2371999-06-0101 June 1999 Proposed Tech Specs Re Surveillance Requirements & Applicable Bases Relevant to ISI Requirements for Portions of once-through SG (OTSG) Tubes Adjacent to Primary Cladding Region of tube-to Tubesheet Roll ML20206T2651999-05-14014 May 1999 Proposed Tech Specs Revising SG Tubing SRs ML20206Q1281999-05-10010 May 1999 Proposed Tech Specs Bases,Page B 2-2,discussing Guidance to Be Used When Applying Later Editions & Addendas of ASME Code to RCS Components ML20206J8021999-05-0404 May 1999 PC-03 to Procedure/Work Plan 1904-002, Offsite Dose Projections Rdacs Computer Method ML20205P6931999-04-0909 April 1999 Proposed Tech Specs Change,Adding Specification 3.0.6 & Associated Bases to ANO-2 ML20205P3731999-04-0909 April 1999 Revised Proposed TS Page 5-1 Re Design Features Conversion ML20205P6431999-04-0909 April 1999 Revised Proposed Technical Requirement Manual Pages ML20205P4081999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Reactor Bldg Structural Integrity Requirements ML20205P6291999-04-0909 April 1999 Proposed Tech Specs Changes,Revising Battery Requirements ML20207C0631999-02-25025 February 1999 Proposed Tech Specs Change Revising Action 2 Associated with Table 3.3-1, Reactor Protective Instrumentation. Change Adds Footnote to Action 2 Allowing Startup with Functional Units Associated with Channel D Excore Inoperable ML20207M7561999-02-24024 February 1999 Proposed Tech Specs,Allowing Startup & Continued Operation of Plant with Channel D Detector Until New Detector Is Installed During mid-cycle Outage Scheduled for Nov 1999 ML20198K1341998-12-17017 December 1998 Corrected Tech Specs Pages to 980629 Application for Amend to License NPF-6 ML20198A3661998-12-0808 December 1998 Proposed Tech Specs B3/4 6-3 & B3/4 6-4,deleting All Requirements Associated with Sodium H Addition Sys & Adding New Requirements for Trisodium Phosphate to Be Stored in Containers Located on Floor of Cb ML20196B4381998-11-24024 November 1998 Proposed Tech Specs Pages,Changing Administrative Controls Section to Implement Consolidated QA Plan Manual & Clarifying Responsibilities on STA Position on Shift ML20196C9761998-11-24024 November 1998 Rev 1 to Unit 2 Technical Requirements Manual ML20154D6681998-10-0101 October 1998 Rev 28 to Procedure/Work Plan 1904.002, Offsite Dose Projections Rdacs Computer Method ML20153D8491998-09-17017 September 1998 Proposed Tech Specs 2.2.1,3.3.1.1 & 3.3.2.1 Re Operating Bypass Setpoint ML20153H1651998-08-12012 August 1998 Rev 0 to ANO Units 1 & 2 Technical Requirements Manual ML20236Y5251998-08-0606 August 1998 Proposed Tech Specs Section 3.1.3.2,revising Action Requirements for CEA Position Indicator Channels ML20236Y5081998-08-0606 August 1998 Proposed Tech Specs Section 3.3.4.B Re Sodium Hydroxide Tank Limits ML20236Y5951998-08-0606 August 1998 Proposed Tech Specs,Revising Requirements Associated W/Units 1 & 2 Control Room Emergency Ventilation Sys ML20236Q2781998-07-13013 July 1998 Proposed Tech Specs Re Safety Limits & Limiting Safety Settings ML20236G6921998-06-29029 June 1998 Proposed Tech Specs,Revising TS 3.4.2 & TS 3.4.12 Re Reactor Coolant Sys Safety Valves & Low Temp Overpressure Protection ML20236G5421998-06-29029 June 1998 Proposed Tech Specs,Revising Surveillance Testing Requirements for Unit 2 Direct Current Electrical Distribution Sys ML20236G5631998-06-29029 June 1998 Proposed Tech Specs,Revising Table 3.3-4 to Provide Range of Acceptable Values for 4160 Volt Bus Loss of Voltage Values ML20236G4911998-06-29029 June 1998 Proposed Tech Specs Re MSSVs & Pressurizer Safety Valves ML20199F7211998-05-22022 May 1998 Rev 8 to Simulator Mod Control,Training Desk Guide 6.3 ML20217N6141998-04-30030 April 1998 Proposed Tech Specs 1.6.1,revising Definition of Quadrant Power Tilt ML20217M2621998-04-30030 April 1998 Proposed Tech Specs Re DG Load Rejection Testing ML20217M4871998-04-28028 April 1998 Proposed Tech Specs Changing Order of Channel Rotation During Outage for Scheduling Flexibility,While Still Requiring Rotation Schedule to Be Established for Operating Cycle ML20217P8141998-04-0101 April 1998 Proposed Tech Specs Re Upper Tubesheet Volumetric Indications to Remain in Svc for Cycle 15 ML20216J7841998-03-17017 March 1998 Proposed Tech Specs Bases Change Concerning Plant Protection Sys Matrix Logic Testing ML20203D1061998-02-18018 February 1998 Proposed Tech Specs Revising Surveillance Testing Requirements for Emergency Feedwater Sys ML20202G9771998-02-0909 February 1998 Proposed Tech Specs Pages,Allowing Use of Repair Roll Technology (Reroll) for Upper Tubesheet Region of SGs 1999-09-07
[Table view] |
Text
- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
fJ;gCs Onm 105 .
. U.S. NUCU. An HECULA T On"OMM10310N DOCF.CT NUMnt:H u.res ,
.
- an_717 NRC DISTRIBUTION rOn PART 50 DOCKET MATERIAL 1
1TO: D.L. Ziemann Fl(OM: Arkansas Power & Ligth Co. DATE OF DOCUMENT Little Rock, Arkansas 5-19-76 )
2.. . J.D. Phillips OATE nECEivEO
_. 5-20-76 '
lDlLETTER , .C NO TO RIZ E O PROP INPUT FORM NUMUEn OF COPIES RECEIVED l DonlGINAL O UNC LASSIF 4 E O ['
QCOPy ,
1
'LC fi'?"981 the following. . . . . . . f 6 ?S$8Ec. Change Request, regarding the remov- l l*
al of the surveillance specimens for the balance of cycle I operation and.requirres their reinser-tion prior t6 Cyc M II.......
~
(1 Twix Cy. Received) -
\ ' ACKNOWLEDGED
, N. *~
DO NOT Rm..fo m y3 -
J .
I PLANT NAME: Arkansas # 1 . -
p& q g - -
o o Ju. .b :'
SAFETY FOR ACTION /INFOR?.!ATIO.J Eh?IRO 5AB b-25-/6 l ASSIGMED AD : ,
ASSIG::ED AD :
MRANCH CHIEF : i t.1emann W / 6 BRANCH CHIEF :
FROJECT ::ANAGER: PROJECT MANAGER :
v4C. ASST. :
vi995 LIC. ASST. :
INTERNAL DISTRIEUTION v d PG FILE) Sy_$ d 3_gApg7y l pian 7 gyg7 peg
' NRC PDR :.mn et rn HETNEMAN l Tmvsco ERNST WI & E (111 SCHRnEnr3 BENAROYA BALT,ARD
' OELD LAIT lLS SPANGLER COSSICK & STAFF ENGINEERIITG IPPCLITO M,IPC MACCARy SITE TET:ll CASE KNIGHT OPERATING REACTORS GADtILL Ik%AUER SIINEIL STELLO STEPP
!LuLEss PAWLICKI HUU!AN OPERATI?!G TECH
! PROJECT MANAGEMEhT REACTOR SAFETY -
-T'ISENI!UT SITE ANALYSIS BOYD ROSS Wi!AO VOLD:ER P. COLLINS NCVAK _
WAER BUNCH ll0USTON '- - h- COLLINS R0_SZTOCZY *CIR))R!CI:R 1lETE,RSON Cl!ECK -
M IMES KREGER MM_LTZ IIELTEMMS AT & I i
SITE SAFETY & UNVIRC SKOVHOLT SAT.TZMAN .
A?IALYSIS lillTI5E'!U',
MhTn ! A MITT.T. Eft I EX I Elt!J AL DI:;l lllHU TION CONTitOL NU?.tBEli
'* ' I.I'DR : Deicenilvillo n ,. IfATL 1.AB !!ROOKilAV,EN llATL LAli it --T IC REG. V-IE ULRIKSON(URNL) ,
. LS-diC li.EPDR_ 5125 i
ASr.n dens /GP.~ ec/Sigt CONsur.TANTS ROO4' :
10 g f g
c
F.-
gt - # ,
~
e iW QQ%e_,~. _ y d,QtE. , f*O 'j; k.Vi 4.c.
%p . . %
~ _ f _ e .v. pG r&m'gyjkk"&&.
- ~ p.,
l 15-261 lten Component Excention 6.4 Rolting 20 l
Not Applicab]
6.6 Integrally h'elded Not Applicabl '
i Yalve Supports 4.2.3
%e structural integrity of the reactor coolant system bout 'I shall be r,aintained at the level required by the original tance
( andards throughout the life of the station. Any e-j as a result of the tests outlined in Tabic IS-261 of Sectic i j of the code, that defects have developed or grown, shall bt investigated. i 4.2.4-To assure the structural integrity of the reactor internals l t out the life of the unit, the two sets of nain internals bc I (connecting the core barrel to the core support shield and '
lower grid cylinder) shall remain in place and under tensio will be verified by visual inspection to determine that the bolt loc. king caps remain in place. All locking caps will b cd after hot functional testing and whenever the internals renoved from the vessel during a refueling or naintenance a The coteshutdown.
refueling barrel to core support shield caps will be inspect 4.2.5 p Sufficient records of each inspection shall be kept to allo, comparison and evaluation of future inspections, a
4.2.6 y Cowpicte surface and volte::ctric examination of the reactor t ~
- p cp flywheels will be conducted coincident with refueling 1 naintenance shutdowns such that within a 10 year period aft:
i.
up all four reactor coolant ptmp flywheels will be exanined.
i 4.2.7 Reactor vessel spccinens shall be removed and examined, to d eine changes in caterial properties, at specinen exposures (
-l equivalent to 3, 9.5,16 and 22.5 Effective Full Power Years of operation.
j his withdrawal schedule may be modified to c with those refueling outages or plant shutdowns, when the re head is renoved, nost closely approaching the withdrawal sch Results of these exaninations shall be used to update Techni l Specification 3.1.2. Specirsens not subjected to destrt.ctivo testing after the first 0.93 EFpY of Cycle 1 asy be removed stored during the renainder of Cycle 1, but shall be re-inst.
y prior to (.'ycle 2.
1 RaSn I
%e surveillance ASMI: progran has been developed to couply with Section XI
- l Boller Coolant Systens. 1971. includingand Pressurc Vessel Code Inservice Inspection of Nuclear Rf 1971 Winter Addenda Edition p l f' De ntu:ber of reactor vessel specimens and the frequencies for renovin; and testing these spccicens are provided to assure compliance with the l requirements of Appendix 11 to 10CFR Part 50.
D *
\
. . .s e
, .,g p } , 4 U )] h 1 . 'p ,
- = _ -- -
-