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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092K5471995-09-20020 September 1995 Revised Tech Spec Pages 4-31,4-32 & 4-33,incorporating Change in TS Section 4.4.1.5 ML20091L2911995-08-23023 August 1995 Proposed Tech Specs Page 6-11a,incorporating Ref to 10CFR20.1302 ML20087F4921995-08-11011 August 1995 Proposed TS Section 3.2 Re Makeup,Purification & Chemical Addition Sys Requirements ML20085N1601995-06-22022 June 1995 Proposed Tech Specs Revising Replacement Pages in Package & Remove Outdated Pages,In Response to NRC Request for Addl Info ML20084L4351995-06-0101 June 1995 Proposed TS 5.3.1.1,describing Use of Advanced Clad Assemblies ML20084N3501995-06-0101 June 1995 Proposed Tech Specs,Deleting RETS & Relocating TSs Per Guidance in GL 89-01 & NUREG-1430 ML20084B3361995-05-24024 May 1995 Proposed Tech Specs Re Change in Surveillance Test Requirements for source-range Nuclear Instrumentation ML20083N7841995-05-17017 May 1995 Proposed Tech Specs,Consisting of Change Requests 252, Removing Chemical Addition Sys Requirements from TS to COLR ML20079A7811994-12-23023 December 1994 Proposed Tech Specs Page 3-32a ML20069A6781994-05-20020 May 1994 Proposed Tech Specs,Supporting Cycle 10 Control Rod Trip Insertion Time Testing ML20065M6831994-04-19019 April 1994 Proposed Tech Specs,Reflecting Deletion of Audit Program Frequency Requirements ML20065K0451994-04-11011 April 1994 Proposed Tech Specs Reflecting Relocation of Detailed Insp Criteria,Methods & Frequencies of Containment Tendon Surveillance Program to FSAR & Providing Direct Ref to Existing Tendon Surveillance Program ML20073C7731994-03-22022 March 1994 Proposed Tech Specs Re Control Rod Trip Insertion Time Testing 1999-09-01
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211M6651999-09-0101 September 1999 Errata Page 4-45,reflecting Proposed Changes Requested in ML20211D1551999-08-20020 August 1999 Proposed Tech Specs Pages,Revising Degraded Voltage Relay as-left Setpoint Tolerances ML20210S7691999-08-12012 August 1999 Rev 10 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual ML20210J1261999-07-29029 July 1999 Proposed Tech Specs Revising ESF Sys Leakage Limits in post-accident Recirculation Surveillance TSs ML20195E6201999-06-0404 June 1999 Proposed Tech Specs,Modifying Conditions Which Allow Reduction in Number of Means for Maintaining Decay Heat Removal Capability During Shutdown Conditions ML20206R1171999-05-13013 May 1999 Proposed Tech Specs Section 3.1.1,incorporating Administrative Updating & Changing Bases Statement ML20206R6531999-05-13013 May 1999 Rev 39 to TMI Modified Amended Physical Security Plan ML20205H0781999-04-0101 April 1999 Proposed Tech Specs Adding LCO Action Statements,Making SRs More Consistent with NUREG-1430,correcting Conflicts or Inconsistencies Caused by Earlier TS Revs & Revising SFP Sampling ML20204B5291999-03-12012 March 1999 Rev 9 to 6610-PLN-4200.02, TMI Emergency Dose Calculation Manual (Edcm) ML20203B0511999-02-0202 February 1999 Proposed Tech Specs Expanding Scope of Systems & Test Requirements for post-accident RB Sump Recirculation ESF Systems & Increasing Max Allowable Leakage of TS 4.5.4 for Applicable Portions of ESF Systems Outside of Containment ML20196G4861998-12-0303 December 1998 Non-proprietary Proposed Tech Specs,Consenting to Transfer & Authorization for Amergen to Possess,Use & Operate TMI-1 Under Essentially Same Conditions & Authorizations Included in Existing License ML20196H5361998-12-0303 December 1998 Proposed Tech Specs Reflecting Decrease in RCS Flow Resulting from Revised Analysis to Allow Operation of Plant with 20% Average Level of SG Tubes Plugged Per SG ML20196F8661998-11-25025 November 1998 Proposed Tech Specs Revised Pages for TS Change 277 Changing Surveillances Specs for OTSG ISI for TMI Cycle 13 RFO Exams Which Would Be Applicable for One Cycle of Operation Only. with Certificate of Svc ML20154P8661998-10-19019 October 1998 Proposed Tech Specs,Providing Allowable RCS Specific Activity Limit Based on OTSG Insp Results Performed Each Refueling Outage ML20154Q6271998-10-19019 October 1998 Proposed Tech Specs Adding Operability & SRs for Remote Shutdown Sys Similar to Requirements in NUREG-1430, Std Tech Specs - B&W Plants, Section 3.3.18 ML20154D5491998-10-0101 October 1998 Cancellation Notification of Temporary Change Notice 1-98-0066 to Procedure 6610-PLN-4200.02 ML20206C0911998-09-0101 September 1998 Rev 17 to Odcm ML20249B2421998-06-11011 June 1998 Proposed Tech Specs Re Alternate High Radiation Area Control ML20216E9751998-04-13013 April 1998 Emergency Dose Assessment Users Manual, for Insertion Into Rev 7 of Edcm ML20216E9491998-04-0909 April 1998 Rev 7,Temporary Change Notice 1-98-003 to 6610-PLN-4200.02, Edcm, Changing Pages 2 & 57 & Adding New Emergency Dose Assessment Users Manual ML20217J8201998-03-25025 March 1998 Proposed Tech Specs Page 6-1,reflecting Change in Trade Name of Owners & Operator of TMI-1 & Correcting Typo ML20217E5311998-03-23023 March 1998 Proposed Tech Specs Pages for Section 3.1.2 to Incorporate New Pressure Limits for Reactor Vessel IAW 10CFR50,App G for Period of Applicability Through 17.7 EFPY ML20202B2061998-01-30030 January 1998 Rev 7,Temporary Change Notice 1-98-0013 to 6610-PLN-4200.02, Edcm ML20198T4721997-12-31031 December 1997 TMI-1 Cycle 12 Startup Rept ML20217G0201997-10-0303 October 1997 Proposed Tech Specs Re Revised Pages 4-80 & 4-81 Previously Submitted ML20211F3781997-09-24024 September 1997 Proposed Tech Specs Revising Steam Line Break Accident Dose Consequence ML20211C2431997-09-19019 September 1997 Proposed Tech Specs Re Decay Heat Removal Sys Leakage ML20211C3421997-09-19019 September 1997 Proposed Tech Specs Pages 3.8-3.9b to TS Section 3.1.4 Providing More Restrictive Limit of 0.35 Uci/Gram Dose Equivalent I-131 & Clarifying UFSAR Analysis ML20210K0011997-08-14014 August 1997 Proposed Tech Specs Revising TMI-1 UFSAR Section 14.1.2.9 Environ Dose Consequences for TMI-1 Steam Line Break Analysis ML20141J4051997-08-12012 August 1997 Proposed Tech Specs Revising Surveillance Specification for Once Through Steam Generator Inservice Insp for TMI-1 Cycle 12 Refueling (12R) Exams Applicable to TMI-1 Cycle 12 Operation ML20198E7941997-07-30030 July 1997 Proposed Tech Specs Incorporating Addl Sys Leakage Limits & Leak Test Requirements for Systems Outside Containment Which Were Not Previously Contained in TS 4.5.4 Nor Considered in TMI-1 UFSAR DBA Analysis Dose Calculations for 2568 Mwt ML20151K2071997-07-25025 July 1997 Revised TS Page 6-19 Replacing Corresponding Page Contained in 970508 Transmittal of TS Change Request 264 ML20217M7251997-06-22022 June 1997 Rev 16 to Procedure 6610-PLN-4200.01, Odcm ML20141E1491997-05-0808 May 1997 Proposed Tech Specs,Consisting of Change Request 264, Incorporating Addl NRC-approved Analytical Methods Used to Determine TMI-1 Core Operating Limits ML20140E2471997-04-21021 April 1997 Proposed Tech Specs 3.3.1.2,changing Required Borated Water in Each Core Flood Tank to 940 ft,4.5.2.1.b,lowering Surveillance Acceptance Criteria for ECCS HPI Flow to 431 Gpm & 3.3.1.1.f Re Operability of Decay Heat Valves ML20134M1211997-02-0707 February 1997 Proposed Tech Specs,Incorporating Certain Improvements from Revised STS for B&W plants,NUREG-1430 ML20133D2821996-12-24024 December 1996 Proposed Tech Specs 3.15.3 Re Auxiliary & Fuel Handling Bldg Air Treatment Sys ML20132F3301996-12-16016 December 1996 Proposed Tech Specs,Reflecting Change in Legal Name of Operator of Plant from Gpu Corp to Gpu Inc & Reflecting Plant License & TS Registered Trade Name of Gpu Energy ML20135D0991996-12-0303 December 1996 Proposed Tech Specs Incorporating Certain Requirements from Revised B&W Std TS,NUREG-1430 ML20135C5321996-12-0202 December 1996 Proposed Tech Specs Re Relocation of Audit Frequency Requirements ML20128H4121996-10-0303 October 1996 Errata to Proposed Ts,Adding Revised Table of Contents & Making Minor Editorial Corrections ML20117H0451996-08-29029 August 1996 Proposed Tech Specs,Consisting of Change Request 257, Incorporating Certain Improvements from STS for B&W Plants (NUREG-1430) ML20113D1971996-06-28028 June 1996 Proposed Tech Specs,Consisting of Change Request 259, Allowing Implementation of Recently Approved Option B to 10CFR50,App J ML20112C8791996-05-24024 May 1996 Proposed Tech Specs Re Pages for App A.Certificate of Svc Encl ML20138B4641996-05-0606 May 1996 Rev 14 to Procedure 6610-PLN-4200.01, Odcm ML20101R1571996-04-10010 April 1996 Proposed Tech Specs,Revising Addl Group of Surveillances in Which Justification Has Been Completed ML20100J6931996-02-22022 February 1996 Proposed Tech Specs,Consisting of Change Request 254, Revising Proposed TS Page 4-46 on Paragraph 4.6.2 That Provides Addl Testing Requirements in Case Battery Cell Parameters Not Met ML20096F0521995-12-31031 December 1995 TMI-1 Cycle 11,Startup Rept ML20095J2311995-12-21021 December 1995 Proposed Tech Specs,Raising Low Voltage Action Level to 105 Volts DC ML20092M1941995-09-21021 September 1995 TMI-1 Pump & Valve IST Program 1999-09-01
[Table view] |
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Chanste Recuest No. ho This Technical Specification Change Request is submitted in support of Licensee's request to chan,e e Appendix A to Operating License No. DPR-50 for Tnree Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.
METROPOLITAN EDISON COMPANY By -
71ce President Sworn and subscribed to me this f day of 977 J'
e4/
Notar/' Pu W e VCer I ,
3910290 $
1479 003
UIIITED STATES OF AMERICA IiUCLEAR REGULATORY COMMISSI0IT III THE MATTER OF DOCKET 1i0 50-289 LICEfISE I!0. DPR-50 METROPOLITAII EDISOII COMPANY This is to certify that a copy of Technical Specification Change Request Iio. h9 to Appendix A of +N Operating License for Three Mile Island Iluelear Station Unit 1, has, on the date given below, been filed with the U. S. Iluclear Regulatory Ccmission and been served er the chief executives of Londonderr/ Township, Da1phin County, Pv.nsylvania and Dauphin County, Pennsylvania by deposit in the United States :: ail, addressed as follows:
Mr. Weldon B. Arthart Mr. Harry B. Reese, Jr.
Board of Supervisors of Board of County Co=issioners Londonderr-/ Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAIT EDISOII COMPAIIY k
By rY Vice' President Dated: _Februarr 18, 1077 1479 004
Three Mile Is.'and Nuclear Station Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Reauest No. h9 The licensee requests that the attached revised pages replace pages 4-17, h-19 and h-21 of 'che existing Technical Specifications, Appendix A.
Reasons for Proposed Change The reason for this revision is to delete the vessel cladding inspection requirements from the TMI-l Technical Specifications. The requirement to inspect vessel cladding was included in the 197h Edition of Sectior C of the ASME Code as Examination Categories B-I-1 and B-I-2. Both of these categories were deleted by the Summer 1976 Addenda.
Safety Analysis Justifying Change The high radi ation exposure involved in these inspections should be avoided now that the ASME, a competent authority, no longer feels that they are necessary from a technical point of view. Deleting these requirements will not adversely affect the health and safety of the public and will, on the other hand, reduce the amount of exposure incurred during inservice inspections. The proposed change does not involve any unreviewed safety questions in that the basis for the deleted inspection requirements wasSection XI of the I.SME Ccde which, as revised by the 1976 Summer Addenda, no longer requires these inspections.
1479 005
~
TA512 4.21 (Contiswed) Sheet b or 13 Item Examination Dtamination IS - 261 Category-YS - 051 Areas to be 2xanined Methode Inspection Schedule and Extent Remarks d
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e G \
V l
Y Interior surfacae Visual Normally accessible areas will be 1.15 N and internals aM visually insg,ected st the first re-fuelins and every third refueling (W
c CR integrally velded internal supports thereafter. The cere barrel vill C~~O cot be removed soley to permit in-spections. If the core barrel is Eh
$-p removed for other reasons, addi- tr C tional *nspections or the inter- 6C nals and vessel interior vill be T performed. Once every 10 year in-spection interval. the region below
- the reactor core vill be inspected to the extent feasible through the access holes in the internals.
Pressurteer 2.1 B longitwiinal and cir- Visus 1 and '.humGstive of 100% of the circum- This veld is subjected to a cunferential velde Volumetric ferential veld from the outside at much higher stress range the lower head to shell juncture. than any other shell veld in
- -
- vith 1/3 of this weld beins in- the pressuriter'.
specte4 about every 3-1/3 yests.
4 Also, one foot or each lon6 1tudinal q veld which intersects this weld will D be inspected during the 10 year in-spection interval.
O O ~
ON
TAst2 4.2-1 (Continued) sheet $ or 13 Ites lisasirsstom Zzaninstice IS - 261 Category-IS - 2 g Areas to be S erineq Nthods Ist reetion Schedule and htent Rema-ks 2.2 D Nostle to wwoesi veldr Volumet*ie Toe erge netz*e veld vill be The nrge nozzle veld le vol':Tttrically inspected from subjected to a much higher the ostelde esce about every usage factor than any other 3-1/3 years. weld in the pressurtser.
The surg- notale is r.ot accessitie from inetz- the pressuriter.
23 E-1 Rester coinectiera rvat Reo -evarkn See ressarke Heatere meet esclueicat nesting exclueton criteria of IS - 121'.
criteria 2.b E-2 Mester and ir.strument flami A v!wal examination for 1-s2mge conrectione vil'. te perfermed during hydro-e statte tests.
I
$ 2.5 0-1 Pressure retaining tvait-ing 2 inches me.d greater Visual and volur.etric or The bolting for the zapvay e.nd one beater tundle vill be inspec-Note 2 lo diameter sw face ted Suring the 10 year inspection interval. T:: place visual dr. spec-tion w!!! be performed on all the bulting during the 10 year inspee-tion intervel with 1/3 being checkeJ about every 3-1/3 yearn.
2.6 0-2 Ivessure retalning bolt- Yleual Thie t.olting vill be visually in-ing less than 2 inches spe:ted at Icast once during the in diameter 10 year interval. The inspectione vill '.,e done in place unless break-the :onnection is required for cther r.asors. 1/3 of these in-spe:tions util be done about every 3-1/3 years.
s k
! e This persgraph of the #Svr Code for Inservice Inspetion gives rulee which sselude evall y else peaetartione, etc., frts. the fM11 requirements of the Code.
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4 7tBLE 4.2-1 (Contfaued) Swet 6 of 13 Item Examinatiot Enemination TS - M1 Category-IS _- 2$1 Arees to be Psamined Methods gepection Schedule and Extent Remarks 2.7 11 Integrally we'ted vessek Visual and Visual su veys of the supports The ultrasonic inspection euroorts volumetric will be performed at the first technique is developmental.
refueling and every third re- These inspections will be fueling thereafter. A thorough done on a "best effort" visual inspection will be per- basis.
formed on all the supports near the end of the 10 year inspection interval. An ultramonte inspec-tion will be performed of the weld on one of the supports about evrry 3-1/3 years.
c~
l Steen Generators (S.C.) and Let-down Coolers (L.C.?
H m tongitudinal or ctrewa- Visual and 8.0. - The sly welds in this The urper head to tubesheet 3.1 a rarential welds in pri- volumetrie category are the tube-sheet to welds are subjected to more mary side shell head welds. Five percent of severe stress conditions the upper head to tubesheet veld than the lower head to tube-on one steem generater will be sheet velds.
inspected near the end of the inspectica interval.
L.C. - A portion of the longitud- ne inlet manifold is sub-inal sess welds on each primary jected to much more severe b ) manifold is accessible at the reni- temperature transients than the outlet manifold.
fold te ylpe joint. The eccessible
{ g Portion will be inspected near the end of the inspection interval on 10] the inlet manifold of the cooler which is used the most.
D- 3) The pressurtser surge nozzle 3.2 t-Mib D */rtmary nor.sle to head Visual ~ S.C. - No volumetric inspections c~d velds and nozzle *.nsid, are planned. Visual inspection and reactor vessel outlet 99 radiused section of the inside radiused section nossle velds are subjected
-* .- CFJ vill be performed cmce during the to more severe stress con-
.b (AH) 20 year inspection interval if the ditions than the S.C. nozzle g C primary heada are opened for other' welds. Since the pres-
- y C-j - reasons, surizer surge and reactor
@ kbi vessel outlet nozzle welds will be inspected, inspec-CJ tion of the S.G. no: ale g b .
welds is not warranted.
6 CD t.C. - There sere no L.C. welds in this category
. . ~ . . . - - . -
- - . _ . ,-.... y _ ~ - - ,,
- a ... .__
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-w D yK bL es b > \
d TAE12 4.2-1 (Contioned) Sheet 7 of 13 Enemination D'.sistnettos Item Fethods Inspeetten Schedule and Extent ytemarks
- S - XI Category-IS - 2$1 [ ween to be Enam!ned_
Nimrry noule to safe- See remarks See :.emarks S.C. and 1..C. - There are 3.3 F no welds in this entegory.
end welds (dissimila-metal)
Pressure retaini.sg bolt- Vis.tal ar.d 0.0. - The boating for Ce pri- note 2 3.6 0-1 mary head manway vill be in ing 2 inches dad over voltssetric in diameter o surface spected during the 10 year interval. This inspection will be performed without disas-sembly of tbs connection unless disassembly is res. aired for other reasons. In place visual inspec-tion will be perfereed on e11 the bolting during the 10 year inspec-tion interval with 1/3 being 4:- checked about every 3-1/3 years.
I r0 o L.C. - There is no 1:olting in this category.
?renru-o retaining wit- Visue.1 S.C. - Thic bolting will be vise-3.5 0-2 ally inspected at 1 cast once ing less than 2 ine'.es in durir.c the 10 year inspection ,
diameter in '.e rv al . The inspections vill be done i'i place unless breaking the connection is r quired for other reasone. 1/3 of these checke will be done about overy 3-1/3 years.
L.C. - There is no bohlrg in this catesory.
Inte8va33y we3ded m . Vism1 anQ S.C. - Ten perceat of the 3ength Ti se are some of the more 3.6 N eel supporte volumetric of this veld on each steam highly st.essed velds in
-* generator will be inepected during the plant.
the 10 year inspection interval f .f.:=. with 3-1/35 of each veld being
- 3 q inspected about every 3-1/3 ywars. ,
H 1.C. - There are :w supports in thle category.
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TABLE 4.2-1 (Contlaued) Sheet 6 of 13 ften Isaminatios Examinatics Areas to be haalped Methods Inspeettom Schedule and hteet Remarks IS - 261_ Category-IS - 2 Q O
Psptog 2005 of the binatallic wetos or pote: The stress evaluations F Safe-end welde Visual,sur-4.1 face and tuo safe-ends in the main reac- are tentative and selected (dissimilar metal) tor coolant piping will be in- welds may be revised.
volumetric f
su spected during the 10 year in.
H spection interval. One safe-end will be at a pump outlet and the other at a pump inlet.
For smaller site safe-ends, the nossie safe-end welds in each site rangs esposed to the most severe stress condittor.s will be inspected during the 10 yeas in-spection interval. This means t.%t one or more weld of each of y the following groups of safe-G end velds will be inspected as kJ in 31cate d :
- a. Ik" pipe - 2 reactor vessel core flooding nottle dissi-d milar metal welds (see Item
- $' 1.T).
~ q;1 1 O h; rzh b. 12" and 10" pipe - One decay heat 09tlet and one surge line N D $1ssim11ar metal weld to the Q ,
3 reactor coolant (DC) piping, g 7M and one surge line dissimilar metal weld to the pressuriter.
~ The s rge linc connections to the reactor coolant pipe and Q - to the pressuriser both see relatively severe stresses and will be inspected.
-_ -...- -.:. u. n s . . a m :. . _ + uns c - - a----.-
Sheet 9 of 13 TAht.E 4.2-1 (Continued)
Essainatloc Exasiinattoa Remarks Item Methods insoeetion Schedule and Extent IS - 261 Cateporv-!S - Q Areme to be Enestned
- c. b" cr.d under pipe - Four high b.1 (Continued) pressure injection. wee letdown, three 4 ain an1 one spray line disristlar metal velds to the RC piping, and three a elief and one spray tiissimilar metal velds to the pressurizer. Of these the spray line cozzles t.o the reactor coolar.t pipe and to the prea-suriser see relatively higher stresses and are selected for inspection.
One third of these taspections vill be perforsed about every 3-1/3 years.
Circumferential and Y1sual and Circumferential and tonnitudinal velas
%.2 J-1 volumetric The most severely stressed welds Note: The stress evalusta.
y longitudinal pipe eelde tions are tentativ: and g
and branch pipe ccn- (exclusive of dissisilar metal selected velds muy be re-N nection velds grer.ter velits which are covered in Item k.1) in each site range in each wised than b inchen in diameter syste ,will be inspected. The -
follovirs velds vill be inspected during the 10 year inspection interval:
' Resctor enolant System Itote 1 applies to the
- n. In the 36 I.D. reactor ecolant pipe, one of the volds between reactor vessel nozzle to the 1000 elbow at the top of the pipe veld.
stenn generator and the vertical l
D D
@' i/( ' ? I .@j,J I
t
'"" "' " = * r***' ' "''
vill be inspected t'6 ether with $
one foot of each !atersectins L LJ D b' uk 3 lonsitudinni veld. In addition, ,
one reactor vessel outlet nozzle to pipe veld will be in-spected. -
- b. In the 28* 2,D. reactor cool-ant pipe, one of the velas at 4~ the dovnetream ends of the elbows
" m at the uischarges o* reacto:-
e coolant purope 1A1 and 1B2 vill D be inepected together with one f
P N foot of each intersectin6 1M81-C tudinni veld.
7.) c. The met sever:1y ' stressed veld O in the surgr lina. .
m.
.