ML17262A474
| ML17262A474 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/06/1991 |
| From: | MECREDY R C ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9105150104 | |
| Download: ML17262A474 (60) | |
Text
ACCELERATED DISTRIBUTION DEMONSTPATION SYSTEM t t REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9105150104 DOC.DATE: 91/05/06 NOTARIZED:
NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas 6 Electric Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Provides notification of revs to plant QA manual App B 6 Attachment A re inservice insp program for third interval 1990-99,dtd 900720.DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
Inservice Inspection/Testing/Relic from ASME NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET g 05000244 Di S Code 05000244 A RECIPIENT ID CODE/NAME PD1-3 LA JOHNSON,A INTERNAL: AEOD/DSP/TPAB NRR/DET/EMEB 7E OCJ-EG 1 EXTERNAL EGGG BROWN i B NRC PDR COPIES LTTR ENCL 1 0 2 2 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD1-3 PD NRR/DET/ECMB 9H NUDOCS-ABSTRACT OGC/HDS 1 RES/DS IR/EIB EGGG RANSOME,C NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 0 1 1 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:
D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISP)FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13 C 0 g)/
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//S/,r/IZIEikl'OCHESTER GAS AND ELECTRIC CORPORATION o 0'4Nr ON I i%rrrlr f'g.TORK 89 EAST AVENUE, ROCHESTER N.Y.14649.0001 ROBERTs: MECREDY Vice President Ctnna Nudear Production May 6, 1991 TEt.EPHONE AREA CDOE7te 546-2700 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Allen R.Johnson Project Directorate I-3 Washington, D.C.20555
Subject:
Quality Assurance Manual Revision, Appendix B Ginna Nuclear Power Plant Inservice Inspection Program for the 1990-1999 Interval R.E.Ginna Nuclear Power Plant Docket No.50-244
Dear Mr.Johnson:
The purpose of this letter is to provide notification of revisions to the R.E.Ginna Station Quality Assurance Manual Appendix B and Attachment A concerning the Inservice Inspection Program for the.Third Interval (1990-1999), dated July'0, 1990.This letter also provides information concerning our policy with the Nuclear Regula;tory Commission on revisions that are editorial.
in nature to the Quality Assurance Manual Appendix B Program and.its Attachments.
Further, Rochester Gas and Electric, (RG&E)respectfully requests the Commission to rescind Relief.Request No.4, described in the Commission's response.dated August 6,.1990, inasmuch as the provision of the exemption granted prohibits adequate.planning for conduct of the examination.
A detailed discussion is provided.in Attachment I.Attachment II identifies and.summarizes revisions to the existing Quality Assurance Manual Appendix B Inservice Inspection Program for the Third Interval (1990-1999) of R.E.Ginna Station dated July 20, 1990 other than editorial changes.On this and future revisions to the Quality Assurance Manual, Appendix B Program and Attachments, it is our belief that it is not the intent, nor is it required to notify your office on changes to our program that are editorial in nature.These editorial changes include items such as typographic errors, modifications to and the rearrangements of existing paragraphs as well as any format changes to the present, structure of our program that do not change or lower our level of commitment to the Nuclear Regulatory Commission.
9105150104 910506 PDR ADOCK 05000244 G.','DR rtr O57 fp p,$f h II~&, M 1l i,(
v'e would like to be advised to the Commission's position regarding the changes described in the attachments or acceptance thereof.It is the opinion of RG&E that these changes do not constitute a reduction to RG&E's commitments.
within the Inservice Inspection Program.Very truly yours, Robert C.Mecre y GAL/149 Attachments h zc: Mr.Allen R.Johnson (Mail Stop 14D1)Project Directorate I-3 Washington, D.C.20555 U.S.Nuclear Regulatory Commission Region I 475 Allendale Road.King of Prussia, PA 19406 Ginna Senior Resident Inspector ATTACHMENT I Rochester Gas and Electric (RG&E)would like to remove from the R.E.Ginna Nuclear Power Station Third 10-Year Inservice, Inspection Program, Relief Request 4, Examination Category B-L-1 and B-L-2, Items 3 B12.10 and B12.20, Class 1 Pump Casing Welds and Pump Casing, and revert back to following the rules as*defined, in the 1986 Edition of Section XI Table IWB 2500-1.RG&E believes that it is impractical to follow the requirements defined in Relief Request 4 as it was modified by the Commission.
The modification requires RG&E to perform a volumetric examination if the pump were open due to maintenance, whereas it was RG&E's desire to eliminate the requirement.
altogether based on the justifications and alternative examinations referenced.
in the submitted request for relief.It is also RG&E.'s understanding that other Nuclear Units with the same Model 93 Pump were allowed the full relief requested by RG&E, without the limitations, imposed with the relief request.RG&E's concern stems from the fact that if Ginna Station Maintenance were to open the.pump as an unscheduled or unplanned activity, then RG&E would be required to perform this examination.
The degree of planning and scheduling for the MINAC Radiographic.
equipment and personnel would prohibit any reasonable.
response.to perform the volumetric examination.
There.is also the possibility of significantly increasing the duration of the plant, outage with such an enormous: unscheduled activity.Section XI Code Committees over the past.few years had developed and approved a Code Case.No.N481 (March 5, 1990), implementing the same alternative requirements as had.appeared in the request.for relief that RG&E has submitted.
Having representation on those.code committees it was RG&E's understanding that the code case: was.sanctioned.
by the Commission representatives.
on those committees:
to eliminate the many requests for relief being submitted.
to the Commission and to establish acceptable alternative-requirements for the Code.This Code case is presently being reviewed by the Commission for inclusion into the next issuance.of Reg.Guide 1.147."Inservice Inspection Code Case Acceptability., ASME Section XI Division 1." Once this code case has been approved by the Commission, RG&E would.then adopt that code case for inclusion into.the Ginna, Third 10-Year Inservice Inspection Program.
REFERENCE:
Ginna Station Safety Evaluation Report (TAC No.74099)Paragraph 3.1.5 Pump Pressure Boundary 3.1.5.1 Request for Relief No.4, Examination Category B-L-1 and B-L-2, Items B12.10 and B12.20, Class 1 Pump Casing Welds.and Pump Casings.
ATTACHMENT II Page 1 The following identifies and summarizes revisions to the R.E.Ginna Station Quality Assurance Manual Appendix B and.Attachment A concerning the Inservice Inspection Program for the Third Interval (1990-1999), dated July 20, 1990.Paragraph 1.2.3.1 (addition)
This paragraph reads: Code Case N-446,"Recertification of Visual Examination Personnel" was added to the Program.Justification:
Guide 1.147 as This Code Case was approved under USNRC Regulatory of July 1989.Paragraph 1.6.1 (addition)
This paragraph reads: An Inservice Inspection Report shall be generated to document applicable Inservice Inspection and associated.
Repair and.Replacement activities, as applicable, in lieu of the NIS-1 and, NIS-2 Forms." Justification This new paragraph was added to provide.clarifica-tion of use of an alternative reporting method in conjunction with approved.Relief Request Number 3.Paragraph 1.7.5.1 (modified)
This paragraph now reads: The evaluation of nondestructive examination results shall be in accordance with Article IWA-3000 of Section XI.All report-able indications will be subject to comparison with previous.data to aid in characterization and determination of origin.Class 1 and.Class 3 components containing relevant conditions will be considered acceptable for continued, service providing an analytical evaluation performed demonstrates the.component.'s acceptability and is subsequently examined in accordance with the requirements of IWB-3132.4, IWB-3142.4, and IWB-3144(b).
Successive inspections for Class 1 shall comply with the re-quirements of IWB-2420 (b)and (c).For Class 3, successive inspections shall comply with the requirements of IWC-2420 (b)and (c).Class 2 and High Energy Program components containing relevant conditions will be considered acceptable for continued service providing an evaluation performed demonstrates the component's acceptability and.is subsequently examined in accordance with A Page 2 the requirements of IWC-3122.4, IWC-3132.3 and IWC-3134(b).
For Class 2 and High Energy Program components, successive inspections shall comply with the requirements of IWC-2420(b) and (c).I Class 1, Class 2, Class 3, and High Energy Program Supports containing relevant conditions will be considered acceptable for continued service providing an evaluation or test is performed that demonstrates the component's acceptability and is subsequently examined in accordance with the requirements of IWF-3122.4 and IWC-3134(b).
Successive inspections on these supports shall comply with the requirements of IWF-2420(b) and (c).Justification:.The modifications to this paragraph were made to provide greater clarification and guidance to the acceptance of examination results by evaluation and successive inspection requirements that the Code specify.Successive inspection requirements for Class 3 to IWC-2420 (b)and.(c)were adopted to provide guidance since the Code does not currently provide rules concerning this issue.Paragraph 1.8.2.1 (modified.)
This paragraph now reads: Applicable examination requirements of the Construction Code shall be met.If the repair is performed on an existing weld.that requires the complete removal of the original weld.metal within that joint before rewelding, the following additional NDE requirements are required: (a)Pressure retaining components greater than 2 inches.in diameter shall require both surface and 100%volumetric examinations to be performed on the new weld.or (b)Pressure retaining components 2 inches or less in diameter shall require a surface examination to be performed on the new weld,.Examinations and testing of snubbers and supports that have been repaired shall be performed in accordance with 1.11 and 5 of this program.Justification:
This paragraph was modified to provide greater clarification of the requirements for"new welds" in the context of a"Repair".This is an additional requirement beyond.the code requirements, a policy RG&E has had since inception of the, ISI Program for Ginna Station.
Page 3 Paragraph 1.10.1.2 (modified)
This paragraph now reads: Pressure Tests are conducted from normal operating pressure, to a pressure up to 25%above system pressure.The degree of pressurization and the test boundary depends upon the type of test being performed.
A visual examination (VT-2)is performed in concert with the pressure test on pressure retaining components under test pressure.Specific exceptions from achieving Section XI requirements are detailed in the Relief Request Section of this document.Justification:
This paragraph was modified to provide clarification of the pressure ranges required for Leakage, Functional, Inservice, Hydrostatic, and Pneumatic Pressure Tests.Paragraph 1.10.2.4 (modified)
This paragraph now reads: This test is performed once each inspection interval.The boundary subject to test pressurization and the associated VT-2 examination during a system hydrostatic pressure test includes all Class 1, 2, and.3 components and piping except as exempted.Justification:
This paragraph was modified for programmatic consistency.
Paragraph 1.10.2.5 (modified)
This paragraph now reads: This test is limited to Class 2 and Class 3 systems.The boundary limits subject to test pressurization and the associated VT-2 examination during a system pneumatic pressure test are the same as a hydrostatic pressure test.Justification:
This paragraph was modified.for programmatic consistency.
Paragraph 1.10.4.1.2 (modified)
This paragraph now reads: For Leakage, Functional, Inservice and.Hydrostatic tests, the level of system pressure and temperature indicated or recorded by normal operating system instrumentation, or alternatively by test instrumentation is acceptable.
For hydrostatic tests, the instrument requirements of IWA-5260 and applicable Code Case N-437 must be met.
Page 4 Justification:
This paragraph was modified.to provide clarification of the instrumentation requirements during pressure testing.Paragraph 1.10.4.5.2 (modified)
This paragraph now reads: The hydrostatic test pressure, including static head, will not exceed.106-o of the specified test pressure for the system anywhere within the test boundary.Justification:
This paragraph was modified to clarify the original policy on systems that have low design pressure, and high static head values.The Code presently does not provide guidance on this sub)ec't Paragraph 1.10.4.5.2.1 (addition)
This paragraph reads: In cases where the highest and lowest elevations can not be isolated by a shutoff valve, and the test pressure including static head, would exceed 106-o of the specified test pressure at the lowest point, the test pressure will be reduced.Justification:
This paragraph was added to provide additional guidance under paragraph 1.10.4.5.2.
Paragraph 1.10.4.5.2.2 (additional)
This paragraph reads: In cases where the high and low elevations result in unreasonably small differences between the test pressure including static head, and 106-o of the specified test pressure, the test pressure will be reduced.Justification:
This paragraph was added to provide additional guidance under paragraph 1.10.4.5.2; Paragraph 1.10.4.5.2.3 (additional)
This paragraph reads: The test pressure, as identified in sections 1.10.4.5.2.1 and 1.10.4.5.2.2, will be adjusted such that the test pressure, including static head, does not exceed 106%of the specified test pressure at the lowest point.The resulting pressure at the highest point will be considered acceptable.
Page 5 Justification:
This paragraph was added to provide additional guidance under paragraph 1.10.4.5.2 and.to clarify policy to prevent system overpressurization when performing Code required hydrostatic tests on systems of this type.Paragraph 1.10.4.5.3 (addition)
This paragraph reads: The hydrostatic test boundary will end at the transition between system piping and instrumentation tubing shown on P&ID drawings.When this transition occurs between isolation valves, the boundary will be extended to the first isolation valve after the transition.
Justification:
This paragraph as added, to provide guidance on hydrostatic boundary limits.Paragraph 1.10.4.6.1 (modified)
This paragraph now reads: Class 1 The system hydrostatic pressure test is conducted at the pressure calculated from the following table based on the test temperature:
Test Tem erature De.P.Test Pressure 1.10Po 1.08Po 1.06Po 1.04Po 1.02Po 100 or less 200 300 400 500 or greater"Po" is the nominal operating pressure corresponding with 100%rated reactor power.Linear interpolation will be used at intermediate test temperatures.
Technical Specification heatup/cooldown limits will be observed.Justification:
This paragraph was modified.to be consistent with Code requirements of INB-5222.Paragraph 1.10.4.6.2 (a)(modified)
This paragraph now reads: Class 2, 3, and High Energy:
Page 6 a.The test pressure will be at least 1.10 times the system pressure for systems with a design temperature of 200 deg.F.or less, and at least 1.25 times the system pressure for systems with a design temperature above 200 deg.F.The system pressure will be the lowest pressure setting among the number of safety or relief valves provided for overpressure protection within the boundary of the system to be tested.For systems (or portions of systems)not provided with safety or relief valves, the system design pressure will be substituted for the system pressure.Justification:
This paragraph was modified to be consistent with the Code requirements of IWC-5222, IWD-5223 and to substitute the system design pressure for relief valve setting for system not provided with relief valves.High Energy Piping was added to this paragraph ,to specifically state the Hydrostatic testing requirements.
All identified changes are editorial in nature.Paragraph 1.10.4.6.2 (e)(modified)
This paragraph now reads: e.For open ended portions of discharge lines beyond the last shutoff valve in nonclosed systems, a test that demonstrates unimpaired flow will be performed in lieu of a system hydrostatic pressure test.Unimpaired.
flow for Class 2 is defined as an"open flow path" and for Class 3 as"adequate flow during system operation".
Justification:
This paragraph was modified to define Class.2 and.Class 3 flow test requirements for open ended systems.Paragraph 1.12.2.1 (modified)
This paragraph now reads: Within 15 days following the completion of the evaluation of each inservice inspection of steam generator tubes, the number of tubes required by Paragraph 1.12.1 above to the plugged or sleeved in each steam generator shall be reported to the Nuclear Regulatory Commission in a Special Report.Justification:
This paragraph was modified to delete the reference to a Technical Specification that no longer exists.Paragraph 1.12.2.2 (modified)
This paragraph now reads: The complete results of the steam generator tube inservice inspection shall be submitted to the Nuclear Regulatory Page 7 Commission in a Speci'al Report within 12 months following the completion of the inspection.
This Special Report shall include: (a)Number and extent of tubes inspected.(b)Location and percent of wall-thickness penetration for each indication of an imperfection, and (c)Identification of tubes plugged or sleeved.Justification:
This paragraph was modified to delete the reference to a Technical Specification that no longer exists.Applicable Attachment A Line List revisions to the Quality Assurance Manual Appendix B Program have been enclosed and identified in Table 1.Revisions to applicable Lines appearing in Table 1 are identified by a revision bar located in the left hand margin.The Table 1 revisions are grouped into three areas: 1.Revisions concerning line exemption basis.(Example: deletion of code exemption basis, thus requiring examination).
2.Clarification of components not under the Boiler and Pressure Vessel Code, ASME Section ZI jurisdiction.
3.Class 3 Vessels, Pumps and Components that were inadvertently omitted from the original submittal.
The preceding information concludes"Revision 1" to the Quality Assurance Manual Appendix B and Attachment A concerning the Inservice Inspection Program for the Third Interval (1990-1999) of R.E.Ginna Station.
Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 12)Class: 2 System: CONTAINMENT SPRAY P&ID No.: 33013-1261 RC&E Line No.Cilbert Line No.SWRI Line No.ISI Fig.Matrl.Sire (in.)Thkns (in.)Exemption Basis NDE Method Po Temp Zn7 Line Description/Remarks 10-SI-151 10B-AC-601 8-SI-151 8A-SI-151 8B-SZ-151 8K-SI-151 6A-SI-151 6B-SZ-151 RHR-450 RHR-450 B-19 B-19 RHR-450 10-SZ-151R B-19 RHR-450 6-SI-151R B-19 RHR-450 10-SZ-151R B-19 RHR-450 10-SZ-2004 B-19 B-20 A312 A312 A312 A312 A312 A312 10.00 0.165 10.00 0.000 8.00 0.148 8.00 0.148 8.00 0.148 8.00 0.000 6.00 0.148 6.00 0.148 SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL SUR/VOL 30 70 30 70 30 70 30 70 30 70 30 70 RWST TO 1ST 10X8&10X6 RDCR.THIS LINE ACCOUNTED FOR ON 33013-1247.
ACCOUNTED IN 10-SI-151; ACTUALLY A TEE.6A-SZ-151 TO CS PUMP 6B-SZ-151 TO CS PUMP THIS LINE ACCOUNTED FOR ON 33013-1247.
10-SZ-151 TO RDCR PAST VALVE 858B.10-SZ-151 TO VALVE 858A.6C-SI-301 CS-500 B-46 A403 6.00 0.280 SUR/VOL 205 70 4A-SZ-151 TO 1ST 6X6X6 TEE.6D-SZ-301 CS-500 6E-SI-301 CS-500 6EE-SI-301 CS-500 6DD-SI-301 CS-500 B-46 B-46 B-46 B-46 A403 A403 A403 A403 6.00 0.280 6.00 0.280 IWC-1221(F) 6.00 0.280 F 00 0.280 IWC-1221(F)
SUR/VOL SUR/VOL 205 70 205 70 205 70 205 70 6C SZ 301 TO VALVE 860A.VALVE 860A TO 1ST 6 TEE BEFORE V 862A.1ST TEE ON LZNE 6C-SI-301 TO VALVE 860B.VALVE 860B TO VALVE 862A.6F-SI-301 6G-SZ-301 6H-SI-301 6I-SI-301 6J-SI-301 6K-SI-301 CS-500 CS-100, CS-150 CS-150 CS-150 CS-800 CS-800 B-46 B-48 B-47 B-47 A403 A312 A312 A312 A403 A403 6.00 0.280 IWC-1221(F) 6.00 0.281 IWC-1221(F) 6.00 0.281 ZWC-1221(F) 6.00 0-281 IWC-1221(F) 6.00 0.280 6.00 0.280 SUR/VOL SUR/VOL 205 70 205 70 205 70 205 70 205 70 205 70 TEE BEFORE VALVE 862A TO PElf 105.N PEN 105 TO CS SPRAY RING.6G-SI-301 TO 4B-SZ-301.
4C-SI-301 TO 6G-SZ-301.
4D-SI-301 TO 1ST 6X6X6 TEE.6X6X6 TEE ON 6J-SI-301 TO VALVE 860D.PAGE 1 OF 33
Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 12)class: 2 System: CONTAINMENT SPRAY PAID No.: 33013-1261 RUSE Line No.6KK-SI-301 6L-SZ-301 6LL-SZ-301 Gilbort Line No.CS-800 CS-800 CS-800 SWRI Line No.ISZ Fig.B-47 B-47 B-47 Matrl.A403 A403 A403 Sire (in.)6.00 6.00 6.00 Thkns (in-)Exemption Basis 0.280 IWC-1221(F) 0.280 0.280 IWC-1221(F)
NDE Method SUR/VOL Po 205 205 205 Temp In7 Line Description/Remarks 70 70 70 VALVE 860D TO 6" TEE BEFORE VALVE 862B.6X6X6 TEE ON 6J-SZ-301 TO VALVE 860C.VALVE 860C TO 6" TEE BEFORE VALVE 862B.6M-SZ-301 CS-800 B-47 A403 6.00 0.280 IWC-1221(F) 205 70 6X6X6 TEE BEFORE VALVE 862B TO PEN 109.6N-SZ-301 6P-SI-301 6Q-S1-301 4-CH-151 4A-SZ-301 4B-SZ-301 CS-200, CS-250 CS-250 CS-250 CVC-1200 CS-500 CS-150 B-46 A312 A312 A312 A312 A312 A312 6.00 6.00 6.00 4.00 4.00 4.00 0.280 IWC-1221(F) 0.281 IWC-1221(F) 0.281 IWC-1221(F) 0.120 0.000 ZWC-1221(A) 0.237 ZWC-1221(A) 205 205 205 30 205 205 70 70 70 70 70 70 PEN 109 TO 6 TEE ON LOWER CS RZNG.N 4F-SZ-301 TO 6N-SZ-301.
THIS LINE ACCOUNTED FOR ON 33013-1265.
PAGE 2 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 13)Classy 2 System: CONTAINMENT SPRAY PSID No.: 33013-1261 RGSE Line No.I 4C-SI-301 4D-SI-301 4E-SZ-301 4F-SI-301 3-SZ-151 3A-SZ-301 3B-SI-301 3C-SZ-301 2-SI-151 2A-SZ-151 2B-SZ-151 2C-SZ-151 2D-SZ-151 2E-SI-301 2F-SI-301 2G-SZ-301 2H-SZ-301 2Z-SI-301 Gilbert Line No.CS-150 CS-800 CS-250 CS-250 CS-150 CS-250 CS-520 CS-100 CS-100 CS-100 CS-100 CS-100 SWRI Line No.ZSZ Fig.B-47 Matrl.A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 A312 Size (in.)4.00 4.00 4.00 4.00 3.00 3.00 3.00 3.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 2.00 Thkns (in.)0.237 0.000 0.237 0.237 0.000 0.216 0.216 0.000 0.154 0.154 0.154 0.154 0.154 0.154 0.154 0.154 0.154 0.154 ExemPtion Basis IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
ZWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC<<1221(A)
IWC-1221(A)
NDE Method Po 205 205 205 205 30 205 205 30 30 30 30 30 205 205 205 205 205 Temp 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 70 Zn7 Line Description/Remarks N 3A-SZ-301 TO 6I-SI-301.
N 6X4 RDCR ON 3B-SI-301.
N 4X3 RDCR TO 6X4 RDCR ON 6P-SI-301.
RWST TO FIRST FLANGE.N 4B-SZ-301 TO 4C-SZ-301.
N 4X3 RDCR ON 4E-SZ-301 TO 4X3 RDCR.VALVE 863B TO SPRAY ADDITIVE TANK.RWST TO VALVE 893A.RWST TO VALVE 893B.RWST TO VALVE 894B.RWST TO VALVE 808'0-SZ-151 TO VALVE 873C.N 6G-SZ-301 TO 6N-SI-301.
N 2E-SZ-301 TO VALVE 875A.N 2E-SZ-301 TO VALVE 875B.N 2E-SZ-301 TO VALVE 876B.N 2E-SZ-301 TO VALVE 876A.2J-SI-151 2K-SI-301 CS-510 CS-510 B-19 A312 A312 2.00 2.00 0.154 0.154 ZWC-1221(A)
IWC-1221(A) 205 205 70 70 8B-SI-151 TO CS EDUCTOR.6C-SI-301 TO VALVE 859A.PAGE 3 OF 33
Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 13)Class: 2 System: CONTAINMENT SPRAY PAID No.: 33013-1261 RUSE Line No.Gilbert Line No.SWRI Line No.ISI Fig.Hatrl.Sixe (in.)Thkns (in.)Exemption Basis NDE Method Po Temp In7 Lino Description/Remarks 2L-SZ-151 2M-SI-301 CS-510 CS-510 2KK-SZ-301 CS-510 A312 A312 B-19 A312 2.00 2.00 2.00 0.154 0.154 0.154 IWC-1221(A)
IWC-1221(A)
IWC-1221(A) 205 205 205 70 70 70 CS EDUCTOR A TO 2K-SI-301.
CS EDUCTOR 1 TO CS EDUCTOR 2.8A-SZ-151 TO CS EDUCTOR.2N-SI-301 2P-SI-151 2Q-SI-301 CS-510 CS-510, CS-520 CS-510 A312 A312 A312 2.00 2.00 2.00 0.154 0.154 0.154 IWC-1221(A)
IWC-1221(A)
IWC-1221(A) 205 70 CS EDUCTOR 2 TO 2N-SI-301'L-SZ-151 TO VALVE 873B.6J-SZ-301 TO VALVE 859B.2QA-SZ-151 CS-520 A312 2.00 0.154 IWC-1221(A) 2P-SZ-151 BY VALVE 873B TO VALVE 873D.2R-SZ-151 2S-SI-151 CS-520 CS-520 A312 A312 2.00 2.00 0.154 0.154 IWC-1221(A)
IWC-1221(A) 2" TEE ON P-SZ-151 PAST VALVE.2P-SZ-151 PAST VALVE 836B TO 1ST 2 TEE.PAGE 4 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 15)class: 2 System: CVCS P&ID No.: 33013-1266 RUSE Line No.Gilbert Line No.SWRZ Lino No, ISZ Fig.Natrl.Sixo (in.)Thkns (in.)Exemption Basis NDE Nothod Po Temp In7 Line Description/Romarks 8A-SI-301B 8B-SZ-301A 3A-CH-151A 3B-CH-151B 2A-SZ-151B 2B-CH-151 B 2C-SZ-151A 2D-CH-151 2D-CH-151A 2E-CH-151 2F-CH-151 1A-CH-151B 1B-CH-151A lc-CH-151 1D-CH-151 SI-400 SZ-400 SI-400 SZ-400 SZ-400 SZ-400 SZ-400 SZ-400 SI-400 SZ-400 8-SZ-2001 8-SZ-2001 B-15 B-15 A312 A312 A312 A312 A312 A312 A312 A312 8.00 0.322 8.00 0.322 3.00 0.000 3.00 0-120 2.00 0.154 2.00 0.154 2.00 0.154 2.00 0.000 2.00 0.154 2.00 0.000 2.00 0.000 1.00 0.000 1.00 0.000 1.00 0.000 1.00 0.000 IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
ZWC-1221(A)
ZWC-1221 (A)ZWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221 (A)SUR/VOL 5 210 SUR/VOL 5 210 5 210 5 210 5 210 5 210 5 210 80 190 5 210 80 200 80 200 5 210 5 210 80 190 80 190 BORZC ACID TANK B TO SX8XS TEE-BORIC ACID TANK A TO 8XSXB TEE.BORIC ACID TANK A TO LOOP SEAL.BORIC ACZD TANK B TO LOOP SEAL.SXSX2 TEE ON 8A-SI-301B TO VALVE 345.BORIC ACID TANK B TO HCV 105.SXSX2 TEE ON 8B-SZ-301A TO VALVE 331.THIS LINE WILL CONT.ON 33013<<1265.
BORIC ACID TANK A TO HCV 104.THZS LINE ACCOUNTED FOR ON 33013-1265.
THIS LINE ACCOUNTED FOR ON 33013-1265.
BORZC ACID TANK TO VALVE 343.BORZC ACID TANK A TO VALVE 328.THIS LINE ACCOUNTED FOR ON 33013-1265.
THIS LINE ACCOUNTED FOR ON 33013-1265.
.75A-CH-151B SZ-400.75B-CH-151A
.75C-CH-151A
.75D-CH-151
.75E-SI-151B SI-400 A312 0.75 0.113 0.75 0.083 0.75 0.083 0.75 0.000 0.75 0.113 IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A)
IWC-1221(A) 5 210 5 210 5 210 80 190 5 210 2B-CH-151B TO VALVE 344.2D-CH-151A TO VALVE 2242.2D<<CH-151A TO VALVE 329.2D-CH-151 CONTINUE ON 33013-1265.
2A-SI-151B TO VALVE 3468.PAGE 5 OF 33
Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 15)Class: 2 System: CVCS P6ID No.: 33013-1266 RGSE Lino No..75F-SI-151A Gilbert Line No.SI-400 SWRI Lino No.ISI Fig.Matrl.A312 Sire (in.)Thkns (in.)Exemption Basis 0.75 0.113 INC-1221(A)
NDE Method Po Temp In?5 210 Y Lino Description/Remarks 2C-SI-151A TO VALVE 346A.PAGE 6 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 58)Class: 2 System: VESSELS PaID No.: 33013-1266 RGSE Line No.Gilbert Line No.SNRZ Line No.ISZ Fig.Matrl.size (in+)Thkns (in.)Exemption Basis NDE Method Po Temp In?Line Description/Remarks B A TANK A B A TANK B 1266 1266 0.00 0.000 0.00 0.000 5 210 5 210 NOT UNDER SECTION XI JURISDICTION, TANK NOT UNDER SECTZON XI JURISDICTIONi TANK PAGE 7 OF 33
~I Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 54)Class: 2 System: VESSELS P&ZD No.: 33013-1261 RGSE Line No.CS EDUCTOR CS EDUCTOR R W STOR TANK SPRAr ADD TANK Gilbert Line No.1261 1261 1261 1261 SWRI Line No.(SEE NOTE)ISZ Fig.Matrl.Sire (in.)Thkns (in.)Exemption Basis 0.00 0.000 IWD.1220.2 0.00 0.000 IWC-1221(A) 0.00 0.000 IWC-1221(A) 0.00 0 F 000 NDE Method Po Temp In?30 70<275<200 Line Description/Remarks NOT UNDER SECTZON XZ JURISDICTION, TANK NOT UNDER SECTION XZ JURISDZCTZON, TANK NOTE: COMPONENT CHANGED FROM CLASS 2 TO CLASS 3 IN LATEST REVISED DOCUMENTS PAGE 8 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 99)Class: 3 System: VESSELS PaID No.: 33013-1238 RCaE Lino No.Cilbort Linc No~SWRI Line No.ISI Fig.Hatrl.Siso (in.)Thkns (in.)Exemption Basis NDE Mothod Po Temp In?Line Description/Remarks STANDBY AUX'EED PUMPS COND TEST TANK 0.00 0.000 IWD-1220.2
<275<200 PAGE 9 OF 33
~1 4 Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 100)Class: 3 System: VESSFZ,S PAID No.: 33013-1239 RGAE Line No.DIESEL GEN.A DZESEI GEN B DIESEL GEN COOL DIESEL GEN COOL LUBE OZL HTEX A LUBE OIL HYTEX B Gilbert Line No.WATER JACKET WATER JACKET WATER EXPANSION WATER EXPANSION SWRI Line No.HEAT EXCHANGER HEAT EXCHANGER TANK B ISZ Fig.Matrl.SiLO (in.)0.00 0.00 0.00 0.00 0.00 0.00 Thkns (in.)0.000 0.000 0.000 0.000 0.000 0.000 Exemption Basis NDE Method VT-3 Po Temp Zn?Line Description/Remarks PAGE 10 OF 33
~l'H W Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 101)Class: 3 Systems VESSELS PAID No.: 33013-1245 RGSE Line No.Gilbert Line No.SWRI Line No.ISI Fig.Matrl.Sire (in.)Thkns (in.)Exemption Basis NDE Method Po In7 Line Description/Remarks B LOWDOWN SAMPLE BLOWDOWN SAMPLE CCW HT.EX.A CCW HT EX B CCW SURGE TANK FAIL FUEL RAD.FAIL FUEL RAD.SAMPLE HT.EX B SAMPLE HT.EX.A SAMPLE HT.EX.C HT.EX.A HT.EX.B MONITOR HEAT MONITOR HEAT EXCHANGER A EXCHANGER B 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0-000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 IWD-1220'IWD-1220.2 ZWD-1220.2 ZWD-1220.2 IWD-1220.2 ZWD-1220.2 IWD-1220.2 VT-3 VT-3<275<200<275<200<275<200<275<200<275<200<275<200<275<200 PAGE 11 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line Li.st Third Znspection Znterval (APP B ATT A PG 102)Class: 3 System: VESSELS PSID No.: 33013-1246 RGSE Line No.Gilbert Line No.SWRI Line No.ISZ Fig.Matrl.Sire (in.)Thkns (in.)Exemption Basis HDE Method Po Temp In?Line Description/Remarks EXCESS LETDOWN NON REGEN HTEX SEAL WATER HTEX W.G.COMP.SEAL W.G-COHP.SEAL HT.EX.WATER HT-EX~A WATER HT.EX.B 0.00 0.00 0.00 0.00 0.00 0.000 IWD-1220.2 0.000 0.000 IWD-1220-2 0.000 ZWD-1220.2 0.000 IWD-1220.2
<275<275<275<275<200<200<200<200 PAGE 12 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 103)Class: 3 System: VESSELS PAID No.: 33013-1248 RCSE Line No.Gilbert Lino No.SWRI Line No.ISI Fig.Matrl.Sino (in.)Thkns (in.)Exemption Basis NDE Hothod Po Temp In?Line Description/Romarks SPENT FDEL POOL SPENT FUEL POOL HT.EX.B 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2
<275<200<275<200 PAGE 13 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 104)Class: 3 System: VESSELS P&ID No.: 33013-1250 RGSE Line No.Gilbert Line No.SWRZ Line No ISI Fig.Matrl.Sire (in.)Thkns (in.)Exemption Basis NDE Method In?Line Description/Remarks CCW HT.EX.A CCW HT.EX.B DIESEL GEN.DIESEL GEN.DIESEL GEN.LUBE DIESEL GEN.LUBE SPENT FUEL POOL SPENT FUEL POOL SPENT FUEL POOL WATER JACKET WATER JACKET OZL HT.EX'OIL HT.EX.B HT.EX.A HT.EX.B STANDBY HT.EX.HT EX A HT.EX B 0 F 00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 IWD-1220.2 ZWD-1220.2.
IWD-1220.2 VT-3 VT-3 VT-3<275<200<275<200<275<200 PAGE 14 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 105)Class: 3 System: VESSELS PSID No.: 33013-1258 RCSE Line No.Gilbert Line No.SWRI Line No.ISI Fig.Matrl.Siso (in.)Thkns (in.)Exemption Basis NDE Method Po Temp In?Lino Description/Remarks PRESS.RELIEF TK 0.00 0.000 IWD-1220.2
<275<200 PAGE 15 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservico Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 106)Class: 3 System: VESSELS P&ID No.: 33013-1264 RG&E Line No.Gilbort Line No.SWRZ Line No.ISI Fig.Matrl.Sire (in.)Thkns (in.)Exemption Basis NDE Mothod Po Temp In?Line Description/Remarks CATION TANK DEMIN TANKS, A&B MIX BED (A&B)TANKS 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2
<275<200<275<200<275<200 NOT UNDER SECT.XI JURISDICTION (ZWD2500)NOT UNDER SECT.XI JURISDICTION (IWD2500)NOT UNDER SECT.XI JURISDICTION (IWD2500)PAGE 16 OF 33 r
Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 107)Class: 3 System: VESSELS PSID No.: 33013-1266 RGSE Line No.Gilbort Line No.SWRI Iino No.ISI Fig.Matrl.Sixo (in.)Thkns (in.)Exemption Basis NDE Method Po Temp In?Line Description/Remarks B.A.BLENDER 0.00 0.000 IWD-1220.2
<275<200 PAGE 17 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Znterval (APP B ATT A PG 108)Class: System: P&ZD No.: 3 VESSELS 33013-1267 RG&E Line No.BASE REMOVAL CATION EX.(A&B)CVCS HOLD UP Gilbert Line No.ZON EXCHANGER TANKS (A,Bi&C)SWRI Line No.(A&B)ISI Fig.Matrl.Sire (in.)0.00 0.00 0.00 Thkns (in.)0.000 0.000 0.000 Exemption Basis IWD-1220.2 IWD-1220.2 IWD-1220.2 NDE Method Po<275<275<275 Temp<200<200<200 In?Line Description/Remarks NOT UNDER SECT.XI JURISDICTION (IWD2500)NOT UNDER SECT.XZ JURISDICTION (IWD2500)NOT UNDER SECT.XI JURISDICTION (ZWD2500)PAGE 18 OF 33 Table 1R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 109)ass: System: i&ID No VESSELS 33013-1270 RG&E Line No.SPENT RESIN WASTE HOLDUP TK Gilbert Line No.TANKS (A&B)SWRI Line No.ISZ Fig.Matrl.Sire (in.)Thkns (in.)0.00 0.000 0.00 0.000 Exemption Basis ZWD-1220.2 ZWD-1220.2 NDE Method Po Temp<275<200 h<275<200 Zn?Line Description/Remarks NOT UNDER SECT.XI JURISDICTION (IWD2500)NOT UNDER SECT.XZ JURISDICTION (ZWD2500)PAGE 19 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Zine List Third Inspection Interval (APP B ATT A PG 110)Class: 3 System: VESSELS PaID No.: 33013-1273 RGaE Line No.Gilbert Line No.SWRI Line No.ZSZ Fig.Natrl.~Size (in.)Thkns (in.)Exemption Basis NDE Method Po Tamp In?Line Description/Remarks GAS DECAY TANKS SEAL WATER HT.(Ai Bi C Zi D)EXe (A Ei B)0.00 0.00 0.000 ZWD-1220.2 0.000 IWD-1220.2
<275<275<200<200 NOT UNDER SECT.XZ JURISDICTIO'N (IWD2500)NOT UNDER SECT.XI JURISDICTION (IWD2500)PAGE 20 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 80)class: 3 System: PUMPS 8 COMPONENTS P&ZD No.: 33013-1231 RCSE Line No.TDAFWP-TURBINE Gilbert Line No.SWRI Lino No.ZSI Fig.Hatrl, Bise (in.)0.00 Thkns (in.)0.000 Exemption Basis NDE Method VT-3 Po Temp In?Iine Description/Remarks PAGE 21 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Znterval (APP B ATT A PG 81)class: 3 System: PUMPS 6 COMPONENTS P&ID No.: 33013-1237 RGSE Lino No.Gilbert Line No.SWRI Line No.ZSI F J.g.Matrl.Sire (in.)Thkns (in.)Exemption Basis NDE Hothod Po In?Tine Description/Remarks AFW PUMP A LUBE AFW PUMP B LUBE AUX FW PUMP A AUX FW PUMP B TDAFW PUMP TDAFW PUMP LUBE OIL COOLER OZL COOLER OZL COOLER 0.00 0.000 0.00 0.000 0-00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 VT-3 VT-3 75 80 75 80 1250 100 1250 100 1250 100 75 80 PAGE 22 OF 33
~~
Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 82)Class: System: P&ID No.: 3 PUMPS&COMPONENTS 33013-1238 RG&E Line No.STANDBY AUX FW STANDBY AUX.FW Gilbert Line No.PUMP D PUMP C SWRI Line No.ISI Fig.Matrl.Sire (in.)0.00 0.00 Thkns (in.)0.000 0.000 Exemption Basis NDE Method VT-3 Po Temp In?Line Description/Remarks PAGE 23 OF 33
~4'I Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 83)class: 3 System: PUMPS&COMPONENTS P&ID No.: 33013-1239 RG&E Lino No DIESEL GEN.LUBE DIESEL GEN.LUBE DIESEL GEN.A DIESEL GEN.A DIESEL GEN.A DIESEL GEN.B FUEL OIL BOOST FUEL OIL BOOST FUEL OIL PRIHE FUEL OIZ PRIHE Gilbert Line No.OIL PUMP AND OIL PUMP AND FUEL OIL TRANS FUEL OZL TRANS STARTING AZR STARTING AIR PUMP A PUMP B PUMP B SWRI Line No.FZITER A FILTER B PUMP A PUMP B RECEIVER Al&A2 RECEIVER Al&A2 ISI Fig.Hatrl.sire (in.)0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Thkns (in.)Exemption Basis 0.000 IWD-1220.1 0.000 IWD-1220.1 0.000 IWD-1220.1 0.000 0.000 0.000 IWD-1220.1 0.000 IWD-1220.1 0.000 IWD-1220.1 0.000 IWD-1220.1 0.000 IWD-1220.1 NDE Hethod Po Temp In?Line Description/Remarks PAGE 24 OF 33
~~
Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 84)Class: 3 System: PUMPS&COMPONENTS PAID No.: 33013-1245 RGSE Line No@CCW PUMP A CCW PUMP B PASS COOLERS(4)
RHR PUMP COOL.A RHR PUMP COOL.B Gilbert Line No.SWRI Line No.ISI Fig.Matrl.Size (in.)0.00 0.00 0.00 0.00 0.00 Thkns (in.)0.000 0.000 0.000 0.000 0.000 Exemption Basis IWD-1220.2 NDE Method VT-3 Po<275<200 In?Line Description/Remarks PAGE 25 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Znterval (APP B ATT A PG 85)ass: System: PUMPS&COMPONENTS P&ID No.: 33013-1246 RG&E Line No.Gilbert Line No.SWRZ Line No.ISZ Fig.Hatrl.Sire (in.)Thkns (in.)Exemption Basis NDE Hethod Po Temp In?Line Description/Remarks B.A.CONDENSE B A CONDEN.B.A.CONDEN.CS PUMP COOL.A CS PUMP COOL B RCP UPPER BEAR.RCP UPPER BEAR.REACTOR SUPPORT REACTOR SUPPORT SZ PUMP COOL.-6 COOLERS'IST.
COOLERS, STEAM COOLERS, COND COOLER A COOLER B COOLER A COOLER B COOLER AIR EJ.CONe COOL UNIT 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2 0.00 0.000 ZWD-1220.2 0.00.0.000 0.00 0.000 0 F 00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220'0.00 0.000 IWD-1220.2 0.00 0.000 VT-3<275<200<275<200<275<200<275<200<275<200<275<200 r<275<200 PAGE 26 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 86)Class: 3 System: PUMPS 6 COMPONENTS PSZD No.: 33013-1248 RGae Line No.SPENT FUEL POOL Gilbert Line No.RECIRC PUMP B SWRZ Line No.ZSI Fig.Matrl.Sire (in.)Thkns (in.)exemption Basis 0-00 0.000 IWD-1220.2 NDE Method Po Temp In?<275<200 Line Description/Remarks PAGE 27 OF 33
~g ()i~
Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Iine List Third Inspection Znterval (APP B ATT A PG 87)Class: 3 System: PUMPS 6 COMPONENTS P&ID'No.: 33013-1250 RGSE Line No.CHARGING PUMP CHARGINE PUMP Gilbert Line No.COOLER A COOLER B SWRI Line No.ISZ Fig.Matrl.Sire (in.)Thkns (in.)0.00 0.000 0.00 0.000 Exemption Basis NDE Method VT-3 VT-3 Po Temp In?Line Description/Remarks CHILLER PACK.A CHILLER PACK B PEN COOLER RHR PUMP RHR PUMP SI PUMP COOL.A SI PUMP COOL.B SI PUMP COOL.C STANDBY AUX.STANDBY AUX.SW PUMP A SW PUMP B SW PUMP C SW PUMP D COOLER A COOLER B FW PUMP ROOM FW PUMP ROOM COOLING UNIT A COOLING UNIT B 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2 0.00 0.000 ZWD-1220.2 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2 0.00 0.000 0.00 0.000 0.00 0.000 0.00 0.000 VT-3 VT-3 VT 3 VT-3 VT-3 VT-3<275<200<275<200<275<200<275<200<275<200 PAGE 28 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 88)class: 3 System: PUMPS&COMPONENTS P&ID No.: 33013-1266 RGSE Line No.B.A.TRANSFER B.A.TRANSFER Gilbert Zino No.PUMP B PUMP A SWRZ Line No.ISZ Fig.Matrl.Sire (in.)0.00 0.00 Thkns (in.)Exemption Basis 0.000 IWD-1220.2 0.000 IWD>>1220.2 NDE Mothod Po<275<275 Temp Int Line Description/Remarks
<200<200 PAGE 29 OF 33 la ib Table 1 R.E.Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 89)class: 3 System: PUMPS&COMPONENTS P&ID No.: 33013-1267 RG&E Line No.Gilbert Line No.SWRZ Line No.ISI Fig.Matrl.Size (in.)Thkns (in.)Exemption Basis NDE Method Po Temp Zn?Line Description/Remarks GAS STRIPPER GAS STRIPPER ZON EX.FILTER RECIRC PUMP FEED PUMPS A&B PACKAGE 0.00 0.000 IWD-1220.2 0.00 0.000 IWD-1220.2 0.00 0.000 ZWD<<1220.2 0.00 0.000 IWD<<1220.2
<275<200<275<200<275<200<275<200 NOT UNDER SECT.XI JURISDICTION (IWD2500)NOT UNDER SECT XZ JURISDICTION (ZWD2500)NOT UNDER SECT-XZ JURISDICTION (IWD2500)NOT UNDER SECT XZ JURISDICTION (ZWD2500)PAGE 30 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 90)class: 3 System: PUMPS&COMPONENTS PAID No.: 33013-1270 ROSE Line No.ULTRA FILTRATIN WASTE EVAP.Gilbert Line No.SYSTEM FEED PUMP SWRI Line No.ZSZ Fig.Matrl.Sire (in)Thkns (in.)0.00 0.000 0.00 0.000 Exemption Basis IWD-1220.2 IWD-1220.2 NDE Method Po<275<200<275<200 Zn?Line Description/Remarks NOT UNDER SECT.XZ JURZSDICTION (ZWD2500)NOT UNDER SECT.XZ JURISDICTION (ZWD2500)PAGE 31 OF 33
'f 4 aa C (l cQ Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 91)Class: 3 System: PUMPS a COMPONENTS PAID No.: 33013-1271 RGSE Line No.WASTE EVAP.WASTE EVAP.Gilbert Line No.DISTILL COOLER SWRI Line No.ISI Fig.Matrl.Sire (in.)0.00 0.00 Thkns (in.)0.000 0.000 Exemption Basis IWD-1220'IWD-1220~2 NDE Method Po<275<275 Temp<200<200 In?Lino Description/Remarks PAGE 32 OF 33 Table 1 R.E.Ginna Nuclear Power Plant Inservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 92)class: 3 System: PUMPS&COMPONENTS P&ID No.: 33013-1273 RG&E Line No.Gilbert Line No.SWRZ Line No.ZSI Fig.Matrl.size (in.)Thkns (in.)Exemption Basis NDE Method Po In7 Zine Description/Remarks GAS COMP~(A&B)MOISTURE SEP.(A&B)0.00 0.000 0.00 0.000 IWD-1220.2 IWD-1220.2<275<200<275<200 NOT UNDER SECT.XI JURISDICTION (IWD2500)NOT UNDER SECTS XZ JURISDICTION (ZWD2500)PAGE 33 OF 33 0 ,4 y4'p iQ