|
---|
Category:Letter type:L
MONTHYEARL-2024-122, Core Operating Limits Report2024-08-12012 August 2024 Core Operating Limits Report L-2024-106, Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-022024-08-12012 August 2024 Fifth and Sixth 10-Year Inservice Testing Interval Relief Request No. VR-02 L-2024-089, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-07-25025 July 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP- 17 451-P. Revision 1. Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update L-2024-100, Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project2024-06-19019 June 2024 Withdrawal of License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation System Replacement Project L-2024-076, Reply to Notice of Violation; NOV 05000250, 05000251/2024010-052024-05-29029 May 2024 Reply to Notice of Violation; NOV 05000250, 05000251/2024010-05 L-2024-082, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report L-2024-060, 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report2024-05-0909 May 2024 10 CFR 50.59(d)(2) Evaluation and 10 CFR 50.71(e)(2) Technical Specification Bases Summaries Report L-2024-073, Cycle 34 Core Operating Limits Report2024-05-0101 May 2024 Cycle 34 Core Operating Limits Report L-2024-072, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report L-2024-048, Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision2024-04-30030 April 2024 Divider Plate Assemblies Bounding Analysis Evaluation for Subsequent License Renewal Commitment Revision L-2024-069, Radiological Emergency Plan Revision 762024-04-22022 April 2024 Radiological Emergency Plan Revision 76 L-2024-066, Sixth 10-Year Inservice Testing Interval Relief Request No. PR-022024-04-17017 April 2024 Sixth 10-Year Inservice Testing Interval Relief Request No. PR-02 L-2024-047, Proposed Use of a Subsequent ASME Code Edition and Addenda2024-03-28028 March 2024 Proposed Use of a Subsequent ASME Code Edition and Addenda L-2024-040, Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections2024-03-28028 March 2024 Notification of Deviation from Pressurized Water Owners Group (PWROG) Report WCAP-17451-P, Revision 1, Reactor Internals Guide Tube Wear - Westinghouse Domestic Fleet Operational Projections L-2024-013, Submittal of Periodic Reports2024-03-28028 March 2024 Submittal of Periodic Reports L-2024-044, Revised Steam Generator Tube Inspection Reports2024-03-19019 March 2024 Revised Steam Generator Tube Inspection Reports L-2024-011, and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 and Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications L-2024-014, Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report2024-02-29029 February 2024 Turkey Points, Units 3 and 4 - 2023 Annual Radioactive Effluent Release Report L-2024-025, Notification of Improved Standard Technical Specifications (ITS) Implementation2024-02-22022 February 2024 Notification of Improved Standard Technical Specifications (ITS) Implementation L-2024-008, Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2024-02-0909 February 2024 Supplement to License Amendment Request 278. Incorporate Advanced Fuel Products. Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2024-010, Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3)2024-01-25025 January 2024 Point Units 3 and 4, Seabrook, Duane Arnold, and Point Beach Units 1 and 2, Nuclear Property Insurance - 10 CFR 50.54(w)(3) L-2024-007, Inservice Inspection Program Owner'S Activity Report (OAR-1)2024-01-18018 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-173, Quality Assurance Topical Report (FPL-1) Revision 30 Update2023-12-15015 December 2023 Quality Assurance Topical Report (FPL-1) Revision 30 Update L-2023-166, Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report2023-12-0606 December 2023 Turkey Points Units 3 and 4, Correction to the 2022 Annual Radioactive Effluent Release Report L-2023-172, Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule2023-11-29029 November 2023 Supplement to Exemption Request Regarding Enhanced Weapons. Firearms Background Checks. and Security Event Notifications Final Rule L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-2023-146, Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule2023-11-16016 November 2023 Part 73 Exemption Request Regarding Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Final Rule L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles2023-11-15015 November 2023 License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles L-2023-077, License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis2023-10-11011 October 2023 License Amendment Request 277 Updated Spent Fuel Pool Criticality Analysis L-2023-110, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-08-25025 August 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-115, Inservice Inspection Program Owner'S Activity Report (OAR-1)2023-08-21021 August 2023 Inservice Inspection Program Owner'S Activity Report (OAR-1) L-2023-114, Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update2023-08-17017 August 2023 Proposed Turkey Point Units 6 and 7; Seabrook Station; Point Beach Units 1 and 2 - Official Service List Update L-2023-098, and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 22023-08-0707 August 2023 and Point Beach Units 1 and 2 - Response to Request for Additional Information Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, Revision 2 L-2023-094, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-07-27027 July 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-087, Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452)2023-06-29029 June 2023 Florida Power & Light/Nextera Energy, Results of the Safety Culture Program Effectiveness Review, March 20, 2023 (ADAMS Accession No. ML22340A452) L-2023-086, Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation.2023-06-28028 June 2023 Request Temporary Suspension of Turkey Point License Amendment Request 274, Reactor Protection System, Engineered Safety Features Actuation System, and Nuclear Instrumentation. L-2023-074, Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update2023-06-0202 June 2023 Addendum to 2021 Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation Ctsfsi) Financial Assurance Update L-2023-069, Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project2023-05-31031 May 2023 Response to Requests for Additional Information Regarding License Amendment Request No. 276, Revise Fire Protection Program in Support of Reactor Coolant Pump Seal Replacement Project L-2023-072, Preparation and Scheduling of Operator Licensing Examinations2023-05-22022 May 2023 Preparation and Scheduling of Operator Licensing Examinations L-2023-071, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal2023-05-22022 May 2023 NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 29 and Florida Power and Light Company Quality Assurance Program Description for 10 CFR Part 52 Licenses (FPL-2) Revision 11, Annual Submittal L-2023-061, 2022 Annual Radiological Environmental Operating Report2023-05-12012 May 2023 2022 Annual Radiological Environmental Operating Report L-2023-062, Cycle 33 Core Operating Limits Report2023-04-27027 April 2023 Cycle 33 Core Operating Limits Report L-2023-060, Radiological Emergency Plan, Revision 752023-04-26026 April 2023 Radiological Emergency Plan, Revision 75 L-2023-054, Submittal of Periodic Reports2023-04-12012 April 2023 Submittal of Periodic Reports L-2023-049, Correction to U4R33 Steam Generator Tube Inspection Report2023-03-30030 March 2023 Correction to U4R33 Steam Generator Tube Inspection Report L-2023-021, Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update2023-03-28028 March 2023 Units, 1 and 2, Turkey Point, Units 3 and 4, Seabrook Station and Point Beach, Units 1 and 2 - Decommissioning Funding Status Reports / Independent Spent Fuel Storage Installation (ISFSI) Financial Assurance Update L-2023-028, and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2023-03-27027 March 2023 and Point Beach Units 1 and 2, 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications 2024-08-12
[Table view] |
Text
Wr)C DISTISII3UTIOW I-On PAIS I .SO Doc):ET r~iATrnlAI
('I L'I/il'Of'3AAYI=Of'IM)
CON COOL NO: j>~~
S FILE' fgOM. Florida Pwr 6 Light Co DA1 E OF DOC DATf= I) EC'D 1wx OTIOSE).
)fiamis Fla R E Uliri 9-30-75 10-9-75 XXX TO: ORIG CC OTHER SEhlf 33RC Pf>R~X Hr Lear one signed SENT LOCAL I'DB CI ASS UNCLASS PROP INf:0 INPUT NO CYS REC'f3 DOCKL= I'O:
XXXXX l, 50-250~3 DESCnlP rlON: ENCLOSURES:
Ltr trans the following: Information concerning Generator Mater Chemistry Control" conversion from. phospha treatment to AVT....(40 c'ys encl: rec'd)
NOTE: DELAY XN DISTRIBUTlON OF THIS.ITElf DUE TO NECESSITY OF HAVING 'TO A'WAIT THE ENCLOSURE TO THE LETTER. ENCLOSURES REt'."D ON 2-2-76.
. P LANT NAME: Turkey Point 3 &
.4'AFrTY
? '?<<'? ?<< '?
ASS XC)llED /LD ASSXGAISED BRANC)1 ClllEF
~33RANC33 0331PLP P~~u/~ 4 I'I'OJECT lfANAGER
~ PR033'CT Nfi?3AGHR +?? ?? 8 LlC ASST. M/ ACR S LXC. ASST. eb'b as A M/N Cy'S ACRS
+
RE SYSTE)fS S'A} ETY PI.ANT SYS'1'Ea~fS SXTE SA1'ETY 6 ENV'JRO 'NALYSIS
,, ~NRC PDR HEXNEI)AN TEDESCO DENTON 1 iUL).ER.
'LD sc~m.oEDER BENAROXA OSSlCK/STAI'1' LAXNAS rNV).)ko TECH. 8 lTE ANAI.YSIS
~ME (2) HNOLNEL?RLNG IPPOLXTO ERNST VO).LHER
)41kSC lIACCARY BALLARD BUNG) 1
)'I<XGS) 1T, OPERATING REACTORS SPANGLER J . COLI.INS Pl OJECT )'fANAGE~IENT SXHMEXL STEL1.0 KREG)'.R,
)30YD P AM).IC)iX SXTI'ECH' P. COI.LXNS OPERATI)>G TECH. JDMXLL ATaI
))OUSTON REACTOR SA)P)".)'Y HIS)'.NHUT STEP.P. SALTZHAN PET)'.RSON ROSS SI)AO )lULHAN RUTBERG
)5ELTZ NOVAK 13A)'.R HELT)";)IES Pg~P7 /g ROSETOCZY C) IEC)i .
S C) iMENCER GRlHES 1 flSCEI.I.ANFOUS EXT)=nNAL DISl BII3UTION
~MCAL P3333~I h ???? /?fi NAT303xAL I,hll 33/ CPS. )3)<00:())AVEli NAT. I.AB z TXC 'PRG30N 3?'-lf C-(3330.NOr CRr;Rf) UL)<1KSON (0!iNL).
NSlC I.A PnR ASI.B CONSULTAN'fS 3?2 3
P.O. IIOX 3103 lhlhl.II, FLOIIIOA 33101 xi~Iil~/r FLORIDA POISLR 5 LIGHT CO,'APAMV September 30, 1975 L-75-475 Director of Nuclear Reactor Regulation ATTN. Nr>> George Learn Chief OgI.
Operating Reactors Branch No'. 3 U. S. Nuclear Regulatory Commission 0, s
/9$ >>>> 8
Ãashington, D. C. 20555 I e ~ski 'C~y
>>>> yg Deax'~ir. Lear s Re~ Xntegrity of Steam Generator Tubes Turkey Point Units 3 and 4 Docket Nos. 50.-250 0 50-251 Turkey Point Units 3 and 4 steam generator >rater chemistry control has been converted from phosphate treatment to AVE.
version seas accomplished in October, 1974, and Unit 4 conversion
'nit 3 con-mao accomplished in August, 1974. Your lettor of September stated that the Nuclear Regulatory ConImission staff is 22'975, particularly interested in the operating experience of such "conversion" plants and, therefore, you requested that. ve provide certain information concerning our, chemiatry conversion and steam generator tube inspections. The follceiing input is proM.dad.
- l. Steam Genexator (S/6 Tube Xns ections (ChronoloLTicall )
A>> S/G 4Ai 4D.~ 4C DATE: Fobruary, 1973 REASON: Preservico and Baseline Eddy Current (EC)
Xnspection TUB=S XNSPECTED: 100 percent of the tubes in the inlet sideof each steam generator at a frequency of 400 K!lz up to the first support. Additionally, a nominal l0
>> percent of the inlet..tubes in each generator mere examined at 400 KHz completely around tho U-bend to the top support on the outlet side. See Appendix A to this xapox't for tubesheet plan indicating those tubes examined
<.-,".vq completely around the U-bend.
HI:.LPING 0UILO I'LORIUA
Hx'.,George Lear September 30, 1975 4
DEFECT XNDXCATXONSs "None othe'han minor scxatches on the ins9.de of the tubes and minor local9.zed denting of the tube wall.
A comple'te listing of those tubes exhibiting. the above mentioned indications 9.s given. in AppenQix A.
KUBES PLUGGEDs None B. S/Gs 38 DATE: December, 1973 RBASONs Planned Un9. 3 maintenance outage provideQ opportunity to gather baseline HC.data on one steam generator. Also prov9.Qed opportunity fox assessment. of reg9.ons ~ihere evidence of tube wall deterioration had been detected in the steam generators of other PT7R's installed by'our NSSS vendor. Xn addition, infonaation was to, be obtained fox coxrelation studies, of the prosence of deposits on tube exteriors and on possible low lovel wall thinning in the region immediately above i:he tubesheet.
TUBED XNSPECTEDs See AppendiX 8 for tubesheet plans indicating wh9.ch tubes were 9.nspected.
DEFECT XNDXCATXONSs Disto ted tub sheet signals at 100 and,400 HiIz in the inlet side between rows 10 and 30 suggest shally. tv~e wall tie.nning (<<204~) 9.n the region adjacent to the top of the tubesheet.
The e was no ev9dence of th9nning in any other reg9.on ~ See Appendix 8 for EC data on the pres=nce of s3.udge deposits.
TUBES PLUGGEDs Mone C, S/Gs 4A DATEs January, .1974 HBASONs Planned Unit 4 maintenance outage prov9.ded opportunity to.gather baseline EC data for use in evaluating a new secondaxy chemistry contxol .
program. Also pxoviQed opportunity to. gather information for correlation studies of the presence of deposits on tube exterioxs and on th>>. phenomena of low level tube wall th9.nning.
i
?*?r. george Lear September 30, 1975 TUBES XNSPZCTEDr 61 tubes vere ZC tested at lOOK15s in both the inlet and out3at side up to the first support. See Appendix C for tubesheet-plan indicating srhich tubes vere 9.nspected ~
DLFHCT XNDXCATXO?JS: Distorted tubesheet. signalo at 100 RHz in all 9.nlet tubas exam9.nod suggest shallower tube vali th9nn9.ng
(<<20l").-in the region ad)acent to the top of the tubesheet. There vas no ev9.dence of th9.nning 9.n any other region+
TUBES PLUGGED! None D. S/Qr 4Ap 49~ 4C DATRIL August " September, 1974 RHi>DON: Planned Unit 4 maintenance outage to find and plug leaking tube(s) in 4A, and perform minimal HC. inspect9ons of tubes surrounding leaking tube(s). The laaking tube vas found 9.n Pocr 16, Column 58 on the inlet side. At this time, Florida Power E L9.ght Company elected to convert to AVT
~
chomistrj, therefore, a full scale HC inspection of all three steam gene..ators vas 9.nitiated to provide examinations'f reg9.ons whore evidence of tube va3.1 thinning'had boen detocted in similar
. generators of other oper"ting j3.ant's. Xn add9.t"on, tube lancing was conducted to romove sludge from the top of the tubeaheets. An estimated 30,000 gallons of eater vore used during the sludge lancing QffoJ TOMS XNSPL'CTED~
t 2024 at 400 KHz in 4A 9.nlet.
463 at 400 KH- in 4A'outlet.
2142 at. 400 KHz in 4B inlet..
24 at 400 ZHz in 48 outlet.
2104 at 400 KE4" 9.n 4C inlet.
38 at 400 KHz 9.n 4C outlet.
See Append9.x D for tubesheot plans indicating vhich tubes vere'nspected.
DEFECT XNDXCATXONS: 34 tubes 9.n the 4A, 9.nlet, 43 tubes in the 48 inlet, and 8 tub s in the 4C inlet shoved greater than 50 percent Chinning. Several other inlet tubes shoved betveen 20 and 49 percent thinning. Of'll the outlet tubes inspected, only 6 tubes 9.n 4A shoved greater than 20 percent thinning.
See Appendix D data sheets for defect locations and degree of tuba thinning.
e
,~ ~-Nx..George Lear September 30, l975 TUBES PLUGGED'nlet tubes with greater than 508 thinning.
Sae Appendix D data.
PLUGGXNQ LXECXT: 50 percent wal3. thinning.
E. S/Qx 3A DATE: Septembez',
. 3.974 REASON< Planned Unit 3 maintenance outage to find and plug laa)ring tube (s), and perform minimal EC inspections of tubes surrounding leaMng tube(v).
The leaking tubo was found in How 43, Colunn 34 on the inlet side.
TUBES XNSPECTEDi 5 tubes were HC tasted at 400 KHz in the inlet side. They wexe the leaking tube and the fouz Cubes surrounding DEFECT XNDXCATXONS: The tube in How 43, Column 34 in the it.
inlet sido -bowed l00 percent, tuba wall thinning. See Appendix E for
,tubaaheet diagram shovring this
'location.
TUBE PXUGGED: R43< C34 inlet siie.
PLUGGXNG LXHXT: 50. percent wall thinning.
S/C: 3A, 3B, 3C DATE: September, l974
~PQQN g Unit 3 steam generator tubeshee4 cleaning vgao performed in preparation.for changeover to AVT
~
chemistry. Ji high prcssure water'ancing technique was used. Approximata3y l0,000 gallons of watax wore flushed through ecch genoratox. See Append& P for tube sheet lancing schematic, TUBES XNSPECTEDs Due to the short shutdown, EC tosting was not attemptod.
DEFECT XNDXCATXONSi Hot applicable.
TUBES PLUGGED< None Go 8/6: 3Ap 38'C-DATE: October November, 1974 REASON: Unit 3 refueling outage px'ovided opportunity to gathex-EC data in regions where evidonce of tube wall deterioration had bean detected, in similar steam generators of other operating plants.
TUBES XNSPECTEDs beany tubes were inspected at 400.;100, and 25 KHz. See Appendix G for tubesheet plans indicating which tubes were inspected.
Hr. George Lear September 30, 1975 DHPECT XNDXCATXONS~ 19 Cubes in tha 3A inlet, 'in 7 tubes in the 3J3 inlet, and 6 tubes the 3C inlet shoved greater than 50 percent thinning. 'Z all the autlet tubes inspected; there vas no inimical:ian of thinning except in generator 33.
See Appendix 0 for ZC data.
TUBES PLUGGED> Z9 in 3A, 7 in 39, and 6 in 3C. A3.2. vere inlet tubes, the lacotion of vhich can be found in Appendix G data sheoto.
PLUGGXHG LXNXT: 50 percent vale. thinning.
H. S/Gi 4A, 48, 4C DATF: Pfayi 1975 HPNSOHi Unit 4 x'efueling outage provided oppoxtunity ta gather exten8ive EC data.
TUBES XNSPRCTED: Tho final report of this inspection has
'not. yet been received fram aux'SSS vendor, therefore, the data on tho number and lo ation of tD~ es inspected are approximate. Specific information identifying which tubes vere inspected vill be f:"on~ardod upon receipt o8 Che inspection report frail aur PSSG data are contained in Yendox'ppro.:inate Appendix F..
DLPHCT XNDXCA XOHSi 36 tubes in, the 4A inlet, 48 tubes in the 49 inlet, end 3 tubas.in the 4C inlet shaved greatex than 40 percent thinning. Xn addition, 27 tuboa in the 4A outlet, 18 tubal in the 48 outlet, and 93 Cube5 in the 4C outlot shoved greater than 40 percent thinning. Specific information on defect locations will be fonrarded upan receipt of the inspection report from oul NSSS vondoz' TUMS PLUGGED: Xnlet Outlet 36 Tn 4A 2~7n 4A 48 in 4a 48 in 4a 3 in 4C 93 in 4C A total of 225 tubes crore plugged.
PLUQCXNQ LXf4XTi 40 percent stall thinning.
X. S/Qt 49 Date: August> 1975 REASONS Planned Unit 4 maintenance outage to find and plug leaking tuba(s).
r~ g lIr George Lear Specific information on Cubes inspected and defect indications ~r3.11 be foxvarded upon receipt. of the inspection report from aur HSSS vendor.
S/Gi 4a nmz: September, 1975 REASON: Planned Unit 4 maintenance outage to find and plug leaking tube.(s).
Specific information on tuboo inspected and defect indications vill be faxwarded .upon receipt of the inopection report fxom our NSSS vendor.
- 2. Beconda 1'later Chemistry A. Current steady-state and. transient limits fox AVT aro contained in Appendix X to this letter.
B. Ximits for phosphate= treatment during the time prior to Z~VT canversian are a3.so contained in Appendix X ta this letter.
C. Appendix J contains general guidelines for transition from phosphate troatment ta iXVT.
"e uro una'e to provide secondary eater chemistry graphs D
'or the si>>: months prio- to termination of phosphate treatment and fo'r the time fxom the'onset of AVT'to the pxesent. This information io avai3.ab3.e anly in numhrica3.;.-
iorm and comprises several hundred data sh'eels; Hovever, if the information would be useful to you in .this form, vo vi11 provide capies upon request.
Very truly youxs, Vice President RBU!nch attachments ccrc Jack R..Newman, Esquire ,