ML17262A474
| ML17262A474 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/06/1991 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9105150104 | |
| Download: ML17262A474 (60) | |
Text
t ACCELERATED DISTRIBUTION DEMONSTPATION SYSTEM t
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9105150104 DOC.DATE: 91/05/06 NOTARIZED: NO DOCKET g FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 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. Di DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL SIZE: S TITLE: OR Submittal: Inservice Inspection/Testing/Relic from ASME Code NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72). 05000244 A
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD1-3 LA 1 0 PD1-3 PD 1 1 JOHNSON,A 2 2 D INTERNAL: AEOD/DSP/TPAB 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB 7E 1 1 NUDOCS-ABSTRACT 1 1 OCJ- 1 0 OGC/HDS 1 1 0 EG 1 1 1 RES/DS IR/EIB 1 1 EXTERNAL EGGG BROWN i B 1 1 EGGG RANSOME,C 1 1 NRC PDR 1 1 NSIC 1 1 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISP) FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 13
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//S/,r /IZIEikl'OCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.Y. 14649.0001 ROBERTs: MECREDY TEt.EPHONE Vice President AREA CDOE7te 546-2700 Ctnna Nudear Production May 6, 1991 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 Quality II Assurance identifies and. summarizes revisions to the existing 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.
this and future revisions to the Quality Assurance Manual, On Appendix B Program and Attachments, the intent, nor is it required to notify your office on changes to it is our belief that it is not 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 G .','DR ADOCK 05000244 rtr O57 fp
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v'e would like to be advised to the Commission's position regarding the changes described in the attachments or acceptance thereof.
is the opinion of RG&E that these changes do not constitute a It 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 desire to eliminate the requirement. altogether based on the was RG&E's 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: This Code Case was approved under USNRC Regulatory Guide 1.147 as 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 100 or less 1.10Po 200 1.08Po 300 1.06Po 400 1.04Po 500 or greater 1.02Po "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 Cilbert SWRI ISI Matrl. Sire Thkns Exemption NDE Po Temp Zn7 Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method 10-SI-151 RHR-450 10-SZ-2004 B-19 A312 10.00 0.165 SUR/VOL 30 70 RWST TO 1ST 10X8 & 10X6 RDCR.
10B-AC-601 B-20 10.00 0.000 THIS LINE ACCOUNTED FOR ON 33013-1247.
8-SI-151 RHR-450 B-19 A312 8.00 0.148 SUR/VOL 30 70 ACCOUNTED IN 10-SI-151; ACTUALLY A TEE.
8A-SI-151 RHR-450 B-19 A312 8.00 0.148 SUR/VOL 30 70 6A-SZ-151 TO CS PUMP 8B-SZ-151 RHR-450 10-SZ-151R B-19 A312 8.00 0.148 SUR/VOL 30 70 6B-SZ-151 TO CS PUMP 8K-SI-151 8.00 0.000 THIS LINE ACCOUNTED FOR ON 33013-1247.
6A-SI-151 RHR-450 6-SI-151R B-19 A312 6.00 0.148 SUR/VOL 30 70 10-SZ-151 TO RDCR PAST VALVE 858B.
6B-SZ-151 RHR-450 10-SZ-151R B-19 A312 6.00 0.148 SUR/VOL 30 70 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 B-46 A403 6.00 0.280 SUR/VOL 205 70 6C SZ 301 TO VALVE 860A.
6DD-SI-301 CS-500 B-46 A403 6.00 0.280 IWC-1221(F) 205 70 VALVE 860A TO 1ST 6 TEE BEFORE V 862A.
6E-SI-301 CS-500 B-46 A403 6.00 0.280 SUR/VOL 205 70 1ST TEE ON LZNE 6C-SI-301 TO VALVE 860B.
6EE-SI-301 CS-500 B-46 A403 F 00 0.280 IWC-1221(F) 205 70 VALVE 860B TO VALVE 862A.
6F-SI-301 CS-500 B-46 A403 6.00 0.280 IWC-1221(F) 205 70 TEE BEFORE VALVE 862A TO PElf 105.
6G-SZ-301 CS-100, B-48 A312 6.00 0.281 IWC-1221(F) 205 70 N PEN 105 TO CS SPRAY RING.
CS-150 6H-SI-301 CS-150 A312 6.00 0.281 ZWC-1221(F) 205 70 6G-SI-301 TO 4B-SZ-301.
6I-SI-301 CS-150 A312 6.00 0-281 IWC-1221(F) 205 70 4C-SI-301 TO 6G-SZ-301.
6J-SI-301 CS-800 B-47 A403 6.00 0.280 SUR/VOL 205 70 4D-SI-301 TO 1ST 6X6X6 TEE.
6K-SI-301 CS-800 B-47 A403 6.00 0.280 SUR/VOL 205 70 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 Gilbort SWRI ISZ Matrl. Sire Thkns Exemption NDE Po Temp In7 Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in-) Basis Method 6KK-SI-301 CS-800 B-47 A403 6.00 0.280 IWC-1221(F) 205 70 VALVE 860D TO 6" TEE BEFORE VALVE 862B.
6L-SZ-301 CS-800 B-47 A403 6.00 0.280 SUR/VOL 205 70 6X6X6 TEE ON 6J-SZ-301 TO VALVE 860C.
6LL-SZ-301 CS-800 B-47 A403 6.00 0.280 IWC-1221(F) 205 70 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 CS-200, A312 6.00 0.280 IWC-1221(F) 205 70 PEN 109 TO 6 TEE ON LOWER CS RZNG.
CS-250 6P-SI-301 CS-250 A312 6.00 0.281 IWC-1221(F) 205 70 N 4F-SZ-301 TO 6N-SZ-301.
6Q-S1-301 CS-250 A312 6.00 0.281 IWC-1221(F) 205 70 N 6N-SI-301 TO 4E-SZ-301.
4-CH-151 CVC-1200 A312 4.00 0.120 30 70 THIS LINE ACCOUNTED FOR ON 33013-1265.
4A-SZ-301 CS-500 B-46 A312 4.00 0. 000 ZWC-1221(A) 205 70 CS PUMP TO 6C-SZ-301.
4B-SZ-301 CS-150 A312 4.00 0.237 ZWC-1221(A) 205 70 N 6H-SZ-301 TO 3A-SZ-301.
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 Gilbert SWRI ZSZ Matrl. Size Thkns ExemPtion NDE Po Temp Zn7 Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method I 4C-SI-301 CS-150 A312 4.00 0.237 IWC-1221(A) 205 70 N 3A-SZ-301 TO 6I-SI-301.
4D-SI-301 CS-800 B-47 4.00 0.000 IWC-1221(A) 205 70 CS PUMP TO 6J-SZ-301.
4E-SZ-301 CS-250 A312 4.00 0.237 IWC-1221(A) 205 70 N 6X4 RDCR ON 3B-SI-301.
4F-SI-301 CS-250 A312 4.00 0.237 IWC-1221(A) 205 70 N 4X3 RDCR TO 6X4 RDCR ON 6P-SI-301.
3-SZ-151 3.00 0.000 IWC-1221(A) 30 70 RWST TO FIRST FLANGE.
3A-SZ-301 CS-150 A312 3.00 0.216 .IWC-1221(A) 205 70 N 4B-SZ-301 TO 4C-SZ-301.
3B-SI-301 CS-250 A312 3.00 0.216 ZWC-1221(A) 205 70 N 4X3 RDCR ON 4E-SZ-301 TO 4X3 RDCR.
3C-SZ-301 3.00 0.000 IWC-1221(A) VALVE 863B TO SPRAY ADDITIVE TANK.
2-SI-151 2.00 0.154 IWC-1221(A) 30 70 RWST TO VALVE 893A.
2A-SZ-151 2.00 0.154 IWC-1221(A) 30 70 RWST TO VALVE 893B.
2B-SZ-151 2.00 0.154 IWC-1221(A) 30 70 RWST TO VALVE 894B.
2C-SZ-151 2.00 0.154 IWC-1221(A) 30 70 RWST TO VALVE 808 2D-SZ-151 CS-520 A312 2.00 0.154 IWC-1221(A) 30 70 TO VALVE 873C.
'0-SZ-151 2E-SI-301 CS-100 A312 2.00 0.154 IWC-1221(A) 205 70 N 6G-SZ-301 TO 6N-SI-301.
2F-SI-301 CS-100 A312 2.00 0.154 IWC-1221(A) 205 70 N 2E-SZ-301 TO VALVE 875A.
2G-SZ-301 CS-100 A312 2.00 0.154 IWC-1221(A) 205 70 N 2E-SZ-301 TO VALVE 875B.
2H-SZ-301 CS-100 A312 2.00 0.154 IWC<<1221(A) 205 70 N 2E-SZ-301 TO VALVE 876B.
2Z-SI-301 CS-100 A312 2.00 0.154 IWC-1221(A) 205 70 N 2E-SZ-301 TO VALVE 876A.
2J-SI-151 CS-510 B-19 A312 2.00 0.154 ZWC-1221(A) 205 70 8B-SI-151 TO CS EDUCTOR.
2K-SI-301 CS-510 A312 2.00 0.154 IWC-1221(A) 205 70 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 Gilbert SWRI ISI Hatrl. Sixe Thkns Exemption NDE Po Temp In7 Lino Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method 2KK-SZ-301 CS-510 A312 2.00 0.154 IWC-1221(A) 205 70 CS EDUCTOR A TO 2K-SI-301.
2L-SZ-151 CS-510 A312 2.00 0.154 IWC-1221(A) 205 70 CS EDUCTOR 1 TO CS EDUCTOR 2.
2M-SI-301 CS-510 B-19 A312 2.00 0.154 IWC-1221(A) 205 70 8A-SZ-151 TO CS EDUCTOR.
2N-SI-301 CS-510 A312 2.00 0.154 IWC-1221(A) 205 70 CS EDUCTOR 2 TO 2N-SI-301 2P-SI-151 CS-510, A312 2.00 0.154 IWC-1221(A) TO VALVE 873B. 'L-SZ-151 CS-520 2Q-SI-301 CS-510 A312 2.00 0. 154 IWC-1221(A) 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 CS-520 A312 2.00 0.154 IWC-1221(A) 2" TEE ON P-SZ-151 PAST VALVE.
2S-SI-151 CS-520 A312 2.00 0.154 IWC-1221(A) 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 Gilbert SWRZ ISZ Natrl. Sixo Thkns Exemption NDE Po Temp In7 Line Description/Romarks Line No. Line No. Lino No, Fig. (in.) (in.) Basis Nothod 8A-SI-301B SI-400 8-SZ-2001 B-15 A312 8.00 0.322 SUR/VOL 5 210 BORZC ACID TANK B TO SX8XS TEE-8B-SZ-301A SZ-400 8-SZ-2001 B-15 A312 8.00 0.322 SUR/VOL 5 210 BORIC ACID TANK A TO 8XSXB TEE.
3A-CH-151A SI-400 3.00 0.000 IWC-1221(A) 5 210 BORIC ACID TANK A TO LOOP SEAL.
3B-CH-151B SZ-400 A312 3.00 0-120 IWC-1221(A) 5 210 BORIC ACZD TANK B TO LOOP SEAL.
2A-SZ-151B SZ-400 A312 2.00 0.154 IWC-1221(A) 5 210 SXSX2 TEE ON 8A-SI-301B TO VALVE 345.
2B-CH-151 B SZ-400 A312 2.00 0.154 IWC-1221 (A) 5 210 BORIC ACID TANK B TO HCV 105.
2C-SZ-151A SZ-400 A312 2.00 0.154 IWC-1221(A) 5 210 SXSX2 TEE ON 8B-SZ-301A TO VALVE 331.
2D-CH-151 2.00 0.000 ZWC-1221(A) 80 190 THIS LINE WILL CONT. ON 33013<<1265.
2D-CH-151A SZ-400 A312 2.00 0.154 ZWC-1221 (A) 5 210 BORIC ACID TANK A TO HCV 104.
2E-CH-151 2.00 0.000 ZWC-1221(A) 80 200 THZS LINE ACCOUNTED FOR ON 33013-1265.
2F-CH-151 2.00 0.000 IWC-1221(A) 80 200 THIS LINE ACCOUNTED FOR ON 33013-1265.
1A-CH-151B SI-400 A312 1.00 0.000 IWC-1221(A) 5 210 BORZC ACID TANK TO VALVE 343.
1B-CH-151A SZ-400 1.00 0.000 IWC-1221(A) 5 210 BORZC ACID TANK A TO VALVE 328.
lc-CH-151 1.00 0.000 IWC-1221(A) 80 190 THIS LINE ACCOUNTED FOR ON 33013-1265.
1D-CH-151 1.00 0.000 IWC-1221 (A) 80 190 THIS LINE ACCOUNTED FOR ON 33013-1265.
.75A-CH-151B SZ-400 0.75 0.113 IWC-1221(A) 5 210 2B-CH-151B TO VALVE 344.
.75B-CH-151A 0.75 0.083 IWC-1221(A) 5 210 2D-CH-151A TO VALVE 2242.
.75C-CH-151A 0.75 0.083 IWC-1221(A) 5 210 2D<<CH-151A TO VALVE 329.
.75D-CH-151 0.75 0.000 IWC-1221(A) 80 190 2D-CH-151 CONTINUE ON 33013-1265.
.75E-SI-151B SI-400 A312 0.75 0.113 IWC-1221(A) 5 210 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 Gilbert SWRI ISI Matrl. Sire Thkns Exemption NDE Po Temp In? Lino Description/Remarks Lino No. Line No. Lino No. Fig. (in.) (in.) Basis Method
. 75F-SI-151A SI-400 A312 0.75 0.113 INC-1221(A) 5 210 Y 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 Gilbert SNRZ ISZ Matrl. size Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in+) (in.) Basis Method B A TANK A 1266 0.00 0.000 5 210 NOT UNDER SECTION XI JURISDICTION, TANK B A TANK B 1266 0.00 0.000 5 210 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 Gilbert SWRI ISZ Matrl. Sire Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method CS EDUCTOR 1261 0.00 0.000 IWC-1221(A)
CS EDUCTOR 1261 0.00 0.000 IWC-1221(A)
R W STOR 1261 0.00 0 F 000 30 70 NOT UNDER SECTZON XZ JURISDICTION, TANK TANK SPRAr ADD 1261 (SEE NOTE) 0.00 0.000 IWD.1220.2 <275 <200 NOT UNDER SECTION XZ JURISDZCTZON, TANK 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 Cilbort SWRI ISI Hatrl. Siso Thkns Exemption NDE Po Temp In? Line Description/Remarks Lino No. Linc No ~ Line No. Fig. (in.) (in.) Basis Mothod STANDBY AUX'EED TEST TANK 0.00 0.000 IWD-1220.2 <275 <200 PUMPS COND 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 Gilbert SWRI ISZ Matrl. SiLO Thkns Exemption NDE Po Temp Zn? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method DIESEL GEN. A WATER HEAT 0.00 0.000 VT-3 JACKET EXCHANGER DZESEI GEN B WATER HEAT 0.00 0.000 JACKET EXCHANGER DIESEL GEN WATER 0.00 0.000 COOL EXPANSION DIESEL GEN WATER TANK B 0.00 0.000 COOL EXPANSION LUBE OZL 0.00 0.000 HTEX A LUBE OIL 0.00 0.000 HYTEX B 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 Gilbert SWRI ISI Matrl. Sire Thkns Exemption NDE Po In7 Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method B LOWDOWN HT. EX. A 0.00 0.000 IWD-1220 ' <275 <200 SAMPLE BLOWDOWN HT. EX. B 0.00 0.000 IWD-1220.2 <275 <200 SAMPLE CCW HT. EX. A 0.00 0.000 VT-3 CCW HT EX B 0.00 0-000 VT-3 CCW SURGE 0.00 0.000 TANK FAIL FUEL MONITOR EXCHANGER 0.00 0.000 ZWD-1220.2 <275 <200 RAD. HEAT A FAIL FUEL MONITOR EXCHANGER 0.00 0.000 ZWD-1220.2 <275 <200 RAD. HEAT B SAMPLE HT. 0.00 0.000 IWD-1220.2 <275 <200 EX B SAMPLE HT. 0.00 0.000 ZWD-1220.2 <275 <200 EX. A SAMPLE HT. 0.00 0.000 IWD-1220.2 <275 <200 EX. C 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 Gilbert SWRI ISZ Matrl. Sire Thkns Exemption HDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method EXCESS HT. EX. 0.00 0.000 IWD-1220.2 <275 <200 LETDOWN NON REGEN 0.00 0.000 HTEX SEAL WATER 0.00 0.000 IWD-1220-2 <275 <200 HTEX W.G. COMP. WATER HT- 0.00 0.000 ZWD-1220.2 <275 <200 SEAL EX ~ A W.G- COHP. WATER HT. 0.00 0.000 IWD-1220.2 <275 <200 SEAL EX. B 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 Gilbert SWRI ISI Matrl. Sino Thkns Exemption NDE Po Temp In? Line Description/Romarks Line No. Lino No. Line No. Fig. (in.) (in.) Basis Hothod SPENT FDEL 0.00 0.000 IWD-1220.2 <275 <200 POOL SPENT FUEL HT. EX. B 0.00 0.000 IWD-1220.2 <275 <200 POOL 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 Gilbert SWRZ ISI Matrl. Sire Thkns Exemption NDE In? Line Description/Remarks Line No. Line No. Line No Fig. (in.) (in.) Basis Method CCW HT. EX. A 0 F 00 0.000 VT-3 CCW HT. EX. B 0.00 0.000 VT-3 DIESEL GEN. WATER HT EX A 0.00 0.000 VT-3 JACKET DIESEL GEN. WATER HT. EX B 0.00 0.000 JACKET DIESEL GEN. OZL HT. 0.00 0.000 LUBE EX' DIESEL GEN. OIL HT. 0.00 0.000 LUBE EX. B SPENT FUEL HT. EX. A 0.00 0.000 IWD-1220.2 <275 <200 POOL SPENT FUEL HT. EX. B 0.00 0.000 ZWD-1220.2. <275 <200 POOL SPENT FUEL STANDBY 0.00 0.000 IWD-1220.2 <275 <200 POOL HT. EX.
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 Gilbert SWRI ISI Matrl. Siso Thkns Exemption NDE Po Temp In? Lino Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method PRESS. RELIEF 0.00 0.000 IWD-1220.2 <275 <200 TK 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 Gilbort SWRZ ISI Matrl. Sire Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in. ) Basis Mothod CATION TANK 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION (ZWD2500)
DEMIN TANKS, 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION A&B (IWD2500)
MIX BED (A & TANKS 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION B) (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 Gilbort SWRI ISI Matrl. Sixo Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Iino No. Fig. (in.) (in.) Basis Method 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: 3 System: VESSELS P&ZD No.: 33013-1267 RG&E Gilbert SWRI ISI Matrl. Sire Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method BASE REMOVAL ZON (A & B) 0.00 0.000 IWD-1220. 2 <275 <200 NOT UNDER SECT. XI JURISDICTION EXCHANGER (IWD2500)
CATION EX. (A 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XZ JURISDICTION
& B) (IWD2500)
CVCS HOLD UP TANKS 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION (A,Bi & (ZWD2500)
C)
PAGE 18 OF 33
Table 1 R. E. Ginna Nuclear Power Plant Znservice Examination Boundary Line List Third Inspection Interval (APP B ATT A PG 109) ass:
System: VESSELS i&ID No 33013-1270 RG&E Gilbert SWRI ISZ Matrl. Sire Thkns Exemption NDE Po Temp Zn? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method SPENT RESIN TANKS (A 0.00 0.000 ZWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION h
& B) (IWD2500)
WASTE HOLDUP 0.00 0.000 ZWD-1220. 2 <275 <200 NOT UNDER SECT. XZ JURISDICTION TK (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 Gilbert SWRI ZSZ Natrl. ~ Size Thkns Exemption NDE Po Tamp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method GAS DECAY (Ai Bi C 0.00 0. 000 ZWD-1220. 2 <275 <200 NOT UNDER SECT. XZ JURISDICTIO'N TANKS Zi D) (IWD2500)
SEAL WATER EXe (A Ei 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION HT. B) (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 Gilbert SWRI ZSI Hatrl, Bise Thkns Exemption NDE Po Temp In? Iine Description/Remarks Line No. Line No. Lino No. Fig. (in.) (in.) Basis Method TDAFWP- 0.00 0.000 VT-3 TURBINE 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 Gilbert SWRI ZSI Matrl. Sire Thkns Exemption NDE Po In? Tine Description/Remarks Lino No. Line No. Line No. F J.g. (in.) (in.) Basis Hothod AFW PUMP A OIL 0.00 0.000 75 80 LUBE COOLER AFW PUMP B OZL 0.00 0.000 75 80 LUBE COOLER AUX FW PUMP A 0-00 0.000 1250 100 AUX FW PUMP B 0.00 0.000 1250 100 TDAFW PUMP 0.00 0.000 VT-3 1250 100 TDAFW PUMP OZL 0.00 0.000 VT-3 75 80 LUBE COOLER 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: 3 System: PUMPS & COMPONENTS P&ID No.: 33013-1238 RG&E Gilbert SWRI ISI Matrl. Sire Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method STANDBY AUX PUMP D 0.00 0.000 VT-3 FW STANDBY AUX. PUMP C 0.00 0.000 FW 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 Gilbert SWRI ISI Hatrl. sire Thkns Exemption NDE Po Temp In? Line Description/Remarks Lino No Line No. Line No. Fig. (in.) (in.) Basis Hethod DIESEL GEN. OIL PUMP FZITER A 0.00 0.000 IWD-1220.1 LUBE AND DIESEL GEN. OIL PUMP FILTER B 0.00 0. 000 IWD-1220. 1 LUBE AND DIESEL GEN. A FUEL OIL PUMP A 0.00 0.000 IWD-1220.1 TRANS DIESEL GEN. A FUEL OZL PUMP B 0.00 0.000 IWD-1220.1 TRANS DIESEL GEN. A STARTING RECEIVER 0.00 0.000 AZR Al & A2 DIESEL GEN. B STARTING RECEIVER 0.00 0.000 AIR Al & A2 FUEL OIL PUMP A 0.00 0.000 IWD-1220.1 BOOST FUEL OIL PUMP B 0.00 0.000 IWD-1220.1 BOOST FUEL OIL 0.00 0.000 IWD-1220. 1 PRIHE FUEL OIZ PUMP B 0.00 0.000 IWD-1220.1 PRIHE 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 Gilbert SWRI ISI Matrl. Size Thkns Exemption NDE Po In? Line Description/Remarks Line No@ Line No. Line No. Fig. (in.) (in.) Basis Method CCW PUMP A 0.00 0.000 CCW PUMP B 0.00 0.000 PASS 0.00 0.000 IWD-1220.2 <275 <200 COOLERS(4)
RHR PUMP 0.00 0.000 VT-3 COOL.A RHR PUMP 0.00 0.000 COOL.B 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 Gilbert SWRZ ISZ Hatrl. Sire Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Hethod B. A. CONDENSE COOLERS'IST.
COOLER 0.00 0.000 IWD-1220.2 <275 <200 B A CONDEN. COOLERS, AIR EJ. 0.00 0.000 IWD-1220.2 <275 <200 STEAM CONe COOL B. A. CONDEN. COOLERS, UNIT 0.00 0.000 ZWD-1220.2 <275 <200 COND CS PUMP COOL. 0.00 .0.000 VT-3 A
CS PUMP COOL 0.00 0.000 B
RCP UPPER COOLER A 0 F 00 0.000 IWD-1220.2 <275 <200 BEAR.
RCP UPPER COOLER B 0.00 0.000 IWD-1220.2 <275 <200 BEAR.
REACTOR COOLER A 0.00 0.000 IWD-1220 ' <275 <200 r
SUPPORT REACTOR COOLER B 0.00 0.000 IWD-1220.2 <275 <200 SUPPORT SZ PUMP 0.00 0.000 COOL.-6 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 Gilbert SWRZ ZSI Matrl. Sire Thkns exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method SPENT FUEL RECIRC 0-00 0.000 IWD-1220.2 <275 <200 POOL PUMP B 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 Gilbert SWRI ISZ Matrl. Sire Thkns Exemption NDE Po Temp In? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method CHARGING PUMP COOLER A 0.00 0.000 VT-3 CHARGINE PUMP COOLER B 0.00 0.000 VT-3 CHILLER PACK. 0.00 0.000 IWD-1220.2 <275 <200 A
CHILLER PACK 0.00 0.000 IWD-1220.2 <275 <200 B
PEN COOLER 0.00 0.000 ZWD-1220.2 <275 <200 RHR PUMP COOLER A 0.00 0.000 VT-3 RHR PUMP COOLER B 0.00 0.000 VT-3 SI PUMP COOL. 0.00 0.000 A
SI PUMP COOL. 0.00 0.000 B
SI PUMP COOL. 0.00 0.000 VT 3 C
STANDBY AUX. FW PUMP COOLING 0.00 0.000 IWD-1220.2 <275 <200 ROOM UNIT A STANDBY AUX. FW PUMP COOLING 0.00 0.000 IWD-1220.2 <275 <200 ROOM UNIT B SW PUMP A 0.00 0.000 VT-3 SW PUMP B 0.00 0.000 VT-3 SW PUMP C 0.00 0.000 VT-3 SW PUMP D 0.00 0.000 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 Gilbert SWRZ ISZ Matrl. Sire Thkns Exemption NDE Po Temp Int Line Description/Remarks Line No. Zino No. Line No. Fig. (in.) (in.) Basis Mothod B. A. PUMP B 0.00 0.000 IWD>>1220.2 <275 <200 TRANSFER B. A. PUMP A 0.00 0.000 IWD-1220.2 <275 <200 TRANSFER 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 Gilbert SWRZ ISI Matrl. Size Thkns Exemption NDE Po Temp Zn? Line Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method GAS STRIPPER FEED 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION PUMPS A (IWD2500)
& B GAS STRIPPER PACKAGE 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT XZ JURISDICTION (ZWD2500)
ZON EX. 0.00 0.000 ZWD<<1220.2 <275 <200 NOT UNDER SECT- XZ JURISDICTION FILTER (IWD2500)
RECIRC PUMP 0.00 0.000 IWD<<1220.2 <275 <200 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 Gilbert SWRI ZSZ Matrl. Sire Thkns Exemption NDE Po Zn? Line Description/Remarks Line No. Line No. Line No. Fig. (in ) (in.) Basis Method ULTRA SYSTEM 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XZ JURZSDICTION FILTRATIN (ZWD2500)
WASTE EVAP. FEED PUMP 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XZ JURISDICTION (ZWD2500)
PAGE 31 OF 33
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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 Gilbert SWRI ISI Matrl. Sire Thkns Exemption NDE Po Temp In? Lino Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method WASTE EVAP. 0.00 0.000 IWD-1220 ' <275 <200 WASTE EVAP. DISTILL 0.00 0.000 IWD-1220 ~ 2 <275 <200 COOLER 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 Gilbert SWRZ ZSI Matrl. size Thkns Exemption NDE Po In7 Zine Description/Remarks Line No. Line No. Line No. Fig. (in.) (in.) Basis Method GAS COMP ~ (A 0.00 0.000 IWD-1220.2 <275 <200 NOT UNDER SECT. XI JURISDICTION
& B) (IWD2500)
MOISTURE SEP. (A & B) 0.00 0.000 IWD-1220. 2 <275 <200 NOT UNDER SECTS XZ JURISDICTION (ZWD2500)
PAGE 33 OF 33
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