ML20196J123

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ISI Summary Rept for GGNS Unit 1
ML20196J123
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 07/17/1997
From: Bivins D, Burton E
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20196J121 List:
References
OAR-1-00001, OAR-1-1, NUDOCS 9708040007
Download: ML20196J123 (54)
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Text

{{#Wiki_filter:_ _. REPORT NUMBER OAR-1-00001 INSERVICE INSPECTION

SUMMARY

REPORT i FOR GRAND GULF NUCLEAR STATION UNIT 1 BALD HILL ROAD PORT GIBSON, MS. 39150 COMMERCIAL OPERATION DATE: JULY 1,1985 l l OWNER / OPERATOR ENTERGY OPERATIONS, INC. j ECHELON ONE P.O. BOX 31995 l JACKSON, MS. 39286-1995 PREPARED BY APPROVED BY APP OVE Y c) T3 h x)m&Ab L //}/ C 8x RESP. ENG (ISI) INS SECTOR (ANII) TESTING /INSP/CTIONS PROGRAMS SUPERVISOR DOCUMENT COMPLETION DATE l Q 7/,v /4 7 e- - w ENTERGY / / 9708040007 970728 PDR ADOCK 05000416 G PDR

- _. - _ _ _ ~ _. _.. -.. ~ - - I l INTRODUCTION i The Inservice Inspections performed between June 21, 1995 and November 30,1996 were conducted, unless otherwise noted, in accordance with the 1977 Edition of the ASME Boiler and Pressure Vessel code Section XI, through and including the summer of 1979 Addenda, with Relief / j Relaxation Paragraphs specified in the Ten Year Plan for Grand Gulf Nuclear Station, (GGNS) Unit 1, (SERI-M-489.1). In addition, the GGNS Unit i Insenice Inspection Plan is in compliance with the following Regulatory Guides, IE Bulletins, NUREGS, Standard Review Plans, and Code Cases: Regulatory Guide 1.147, Rev.5 Inservice Inspection Code Case Acceptability ASME Section XI, Division 1 Regulatory Guide 1.150, Rev.1 Ultrasonic Testing of Reactor Vessel Welds during Presenice and Insenice Inspection. NUREG 0619, Rev.1 BWR Feedwater Nozzle and Control Rod Drive Retum Nozzle Cracking. IE Bulletin No. 79-17, Rev.1 Piping Cracks in Stagnant Borated Water Systems in Power Plants. IE Bulletin No. 80-07 BWR Jet Pump Assembly Failure. l IE Bulletin No. 80-13 Cracking in Core Spray Spargers. l SRP 3.6.2 Determination of Break Location and Dynamic Effect { Associated with Postulated Rupture of Piping. Code Case N-307-1 Revised Ultrasonic Examination Volume for Class i Bolting Table IWB-2500, Examination Category B-G-1, When Examinations are Conducted from the Centered-Drilled Holes, Section XI, Division 1. Code Case N-335 Rules for Ultrasonic Examination of Similar and Dissimilar Metal Piping Welds Code Case N-343 Alternative Scope of Examinations of Attachment Welds for Examination Categories B-H, B-K-1, and C-l C of ASME Section XI, Division 1. j Code Case N-356 Certification Period for Level Ill NDE Personnel { Section XI, Divisions 1,2 and 3. V iof4

s a INTRODUCTION (Continued) l Code Case N-416-1 Alternate Pressure Test Requirements for Welded Repairs or Installation of Replacements items by l Welding, Clas 1,2, and 3 Section XI, Division 1 ~ Code Case N-426 Extent of VF-1 Examinations, Category B-G-2 of Table IWB-2500-1 Section XI, Division 1. Code Case N-427 Code Cases in Inspection Plans Section XI, Division 1. Code Case N-435-1 Alternative Exammation Requirements for Vessels with Wall Thickness 2 in. or Less Section XI, Division 1. Code Case N-460 Alternative Examination Coverage for Class 1 and 2 Welds Section XI, Division 1. Code Case N-461 Alternative Rules for Piping Calibration Block Thickness Section XI, Division 1. Code Case N-496 Helical-Coil Threaded Inserts Section XI, Division 1 Code Case N-498-1 Alternative Rules 10-Year Hydrostatic Pressure Test fcr Class I and 2 Systems Code Case N-508-1 Rotation of Service Snubbers and Relief Valves for the Purpose of Testing Code Case N-532 Alternative Requirements to Repsir and Replacement Documentation Requirements and Inservice Summary Report Preparation and Submission as Required by IWA-4000 and IWA-6000, Section XI, Division 1 Generic Letter 88-01 NRC Position on IGSCC in BWR Austentic Stainless Steel Piping. During the course of the exammations, Entergy Operations, Inc. controlled the examination activities through our established programs. Actual exammations were either performed by Entergy Operations Quality Programs Inspectors working to GGNS procedures or contractor inspectors working to GGNS procedures or procedures approved for use by Entergy Operations. ( Arkwright Mutual Insurance Company served as the authorized inspection agency as dermed in IWA-2130. By this arrangement, Arkwright Mutual Insurance Company reviewed the applicable 1 ? 2 of 4

INTRODUCTION (continued) procedures, examined personnel certification records, witnessed selected inspections, and checked for general code compliance as specified by IWA-2120. This report is being presented as one volume divided into several sections as necessitated by the degree of detail required by Code Case N-532. Code Case N-532-1 requires that an Owner's Activity Report Form OAR-1 shall be prepared and certified upon the completion of each refueling outage and that each Form OAR-1 prepared during an inspection period shall be submitted to the ) NRC following the end of that inspection period. Each OAR-1 shall contain the following: an i abstract of applicable examinations and tests, Table 1; a listing ofitem(s) with flaws or relevant conditions that require evaluation to determine acceptability for continued senice (whether or not ) the flaw or relevant condition was discovered during a scheduled examination or test), Table 2; and an abstract of repairs, replacements, and corrective measures performed which were required due l to an item containing a flaw or relevant condition that exceeded Section XI acceptance criteria, I Table 3. For that purpose, Section I contains the owner's Activity Report, Form OAR-1, Table 1, Table 2, and Table 3. Section 11 provides information pertaining to the resolution of open items contained in Insenice Inspection Summary Reports NIS-1-00010 and NIS-1-00011. Section III l contains a code category summary. Section IV contains drawings / isometrics applicable to the ccmponents examined. Section V contains a copy of all approved Relief Requests referenced in this report. ] l i l l I 3 or4 f l i

TABLE OF CONTENTS SECTION 1 OAR OWNERS ACTIVITY REPORT SECTION 11 OPEN ITEMS RESOLUTION SECTION Ill CODE CATEGORY

SUMMARY

SECTION IV DRAWINGS /lSOMETRICS l SECTION V RELIEF REQUESTS 1 l l 1 i 4 of 4 l

~ SECTION I OWNER'S ACTIVITY REPORT l l i 7 4

SECTION I OWP. IER'S ACTIVITY REPORT l I I

l i l FORM OAR-1 OWNER'S ACTIVITY REPORT Report Number : OAR-l 00 mil Owner Enterry Operations Inc. Echelon One. P O liox 31995. Jackson Ms 39286-1995 Name and Address orOwner l plant Grand Gulf Nuclear Station. Itald flill Road. Port Gibson. Ms. 39150 Name and Address of Owner Umt No. I Commercial Service Date July 1.1985 Refueling Outage No. 8 (if appheable) l Current inspection Inteival ist Ist. 2nd. 3r t. 4th other Cunent inspe f.on Period 3rd ist. 2nd, 3rd Edition and Addenda of hecdon XI appheable to the inspection plan 1977 Edition. through and including the summer of 1979 Addenda Date and revision ofinspection :Ian _ November 5. I996. Revision 9 Edition and Addenda of Section XI apph. pole to repain and replacements different than the inspection plan N/A l ~ ~ I5 VNER'S CERTIFICATE OF CONFORMANCE I certify that the statements mad in this Owner's Activity Report are corr;et. and that the exammations tests. repains replacements, evaluations. and corrective v ensures represented by thm report etmform to the requirements of Section XI. Ce:1ilicate of Authonzation No. N/A Expiration Date N/A Signed _ 1 . ISI Coordinator Date

7. l4 $~7 Owner or Owner's Desgnee. Title CERTIFICATE OF INSERVICE INSPECTION
1. the undersigned, holding a valid commission issued by the National lloard oflioiler and Pressure Vessel Inspectors and the State or Provmee of Mississippi and empio>ed by ArkwTinht Mutual Insurance Comning of Waltham. Ma. have mspected the stems desenhed in this Owner's Actinty Repo1 during the period June 21.1995 to Nosetnber 30.1996, and state that to the best of my knowledge and behef. the Owner has performed all activities represented by thn report m accordance with the requirenwnts of Sectmn XL liy signing this c.rtificate neither the Inspector nor hm employer makes any warranty, expressed or implied, concernmg the exammations, tests, repairs, replacements, evaluations, and corrective measures described in this report. Furthermore, neither the inspector nor his employer shall be liable in any manner for any personal mjury or property damage or loss of any kind arising texn or connect d with this inspection.

3 ?, _ Coimmssions _ _ .....r l Inspes % Signature National It wd. State. }%vmce. and Endorsements Date

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TABLEI i l ABSTRACT OF EXAMINATIONS AND TESTS i Examination Total Total Total Total Remarks Category Examinations Examinations Examinations Examinations Required For Credited For This Credited (%) Credited (%) To The Interval Period For The Period . Date For The Inten al B-A 47 17 100 100 t B-D 70 22 100 100 l B-E 6 1 100 100 B-F 80 24 100 100 I i B-G-1 24 9 100 100 B-G-2 19 5 100 100 B-H I I IO0 100 B-J 883 372 100 100 i B-K-1 60 26 100 100 ~ B-L-2 1 0 100 100 B-M 2 9 4 100 100 B-N 1 3 1 100 100 B-N-2 1 1 100 100 j C-A 2 1 100 100 C-B 6 6 100 100 C-C 35 13 100 100 C-D 1 1 100 100 C-F 517 206 100 100 i C-G 42 18 100 100 D-A 8 8 100 100 D-B 20 13 100 100 D-C 31 to 100 100 D-A, D-B 86 35 100 100 1 of 2

_. ~ TABLE 1 ABSTRACT OF EXAMINATIONS AND TESTS Examination Total Total Total Total Remarks Category Examinations Examinations Examinations - Examinations Required For Credited For This Credited (%) Credited (%) To The Inten al Period For The Period Date For The Inten al D-A,D-B, 47 20 100 100 j D-C F-A 44 17 100 100 F-B 562 341 100 100 F-C 177 74 100 100 F-A, F-B 18 8 100 1(X) l F-A, F-C 9 0 100 100 F-A> F-B, 4 4 100 100 F-r B-P 9 9 100 100 Hydro Test B-P 17 9 100 100 Pressure Test C-H 153 51 100 100 Pressure Test DA, DB DC 26 17 100 100 Hydro Test DA, DB,DC 75 25 100 100 Pressure Test l TOTAL 1091 1169 100 100 The total number of examinations required for the interval is based on current number of pressure test zones required to implement the program. 20f2

TABLE 2 ITEMS WITIl FLAWS OR RELEVANT CONDITIONS TIIAT REQUIRED j EVA' UATION FOR CONTINUED SERVICE L j Examination Item item Flaw Characterization Flaw or Relevant Condition Category Number Description (IWA-3300) Found During Scheduled Section XI Examination (Yes or No) B-G-2 B-7-10 Control Rod Linear Indications Yes Drive (CRD) Detected by Penetrant l Flange-to-Exam (PT) Afler Flange Bolting Unacceptable VT-l' 1 l l l i l l i i i ' MNCR 92/00173 was written to document the unacceptable VT-1. Eighteen of 176 cap screws examined had visual indications. Fificen of the cap screws were subjected to a Penetrant Test (PT). The 1 test indicated small linear indications. A detailed metallographic examination of five of the worst case CRD cap screws was performed. GE report RDE43-0592 found the degradation of the cap screws acceptable and. if left as is, were not expected to result in a failure of the cap screws in the future. I l I of 1 i I l

TABLE 2 ITEMS WITil FLAWS OR RELEVANT CONDITIONS TIIAT REQUIRED EVALUATION FOR CONTINUED SERVICE Examination item item Flaw Characterization Flaw or Relevant Condition Category Numher Description (IWA-3300) Found During Scheduled Section XI Examination (Yes or No) B-G-2 B-7-10 Control Rod Linear Indications Yes Drive (CRD) Detected by Penetrant Flange-to-Exam (PT) After Flange Bolting Unacceptable VT-l' ' MNCR 92/00173 was wTitten to document the unacceptable VT-1. Eighteen of 176 cap screws examined had visual indications. Filleen of the cap screws were subjected to a Penetrant Test (PT). The test indicated small linear indications. A detailed metallographic examination of five of the worst case CRD cap screws was performed. GE report RDE43-0592 found the degradation of the cap screws acceptable and, if left as is, were not expected to result in a failure of the cap screws in the future. I of 1

I I TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTIVE MEASURES REQUIRED FOR CONTINUED SERVICE Code

Repair, Item Description Flaw or Relevant Date Repaid Class Replacement, Description of Work Condition Found Completed Replacement or Corrective During Scheduled Plan Number Measure Section XI Examination (Yes or No) 2 B-G-2 Replacement /

Control Rod Replace Yes 11-30-96 Note 1 Corrective Drive (CRD) CRD Cap Measure' Flange-to-Screws Flange Bolting Note 1: Repair / Replacement Plan Numbers: NIS 2-00289 (RF05 NIS-2 form submitted to the NRC following RFOS and included in Inservice Summary Report NIS-1-00009 for GGNS) NIS-2A-WOl6483, WOl64824 WOl64822, WOl64823, WOl64816. WOl64813, WOl71978, WOl6481, WOl63717, WOl64820, WOl64847, WOl64842, WOl69567, WO157794, WOl69471, WOl69566, WOl69568, WOl64832 WOl69477, WOl64825, WOl64846, WOl69467, WOl64815 WOl64821 WOl63719 WOl64817 (RFO8 Repair / Replacement Plan Numbers NIS-2A-Number) uring RF05, the old style capscrews were use to replace 144 of the removed capscrews while 32 of the ^ rew redesigned cap screws were used to replace the remaining remcved cap screws. During the last outage (RF08), all CRD cap screws removed were visually inspected and all removed cap screws were replaced with the new redesigned cap screws. Prior to the plant returning to operation, the 5 cap screws showing the worst damage were analyzed. The results showed that the cracks were due to the same phenomenon as identified in RFOS and the indications and depth were as expected. ' Successive examinations will continue for the next three periods in accordance with the Inservice Inspection Plan. If cap screws with indicdons that exceed the established threshold limit of.150 inches flaw depth are detected, a conditioa Nport will be initiated to evaluate the condition and take appropriate action prior to returning to operation. I of I

TABLE 3 ABSTRACT OF REPAIRS, REPLACEMENTS, OR CORRECTJVE MEASURES R SQUIRED FOR CONTINUED SERVICE Code

Repair, Item Description Flaw or Relevant Date Repair /

Class Replacement, Description of Work Condition Found Completed Replacement or Corrrctive During Scheduled Plan Number Measure Section XI Examination (Yes or No) 2 B-G-2 Replacement / Control Rod Replace Yes 11 30-96 Note 1 Corrective Drive (CRD) CRD Cap Measure' Flange-to-Screws l Flange Bolting Note 1: Repair / Replacement Plan Numbers: NIS-2-00289 (RFOS NIS-2 form submitted to the NRC following RFOS and included in Inservice Sununary Report NIS-I-00009 for GGNS) NIS-2A-WOl6483, WOl64824 WOl64822, WOl64823, WOl64816 WOl64813, WOl71978, WOl6481, WOl63717 WOl64820. WOl64847. WOl64842, WOl69567, WO157794, WOl69471, WOl69566, WOl69568, WOl64832, WOl69477, WOl64825, WOl64846, WOl69467. WOl64815, WOl64821, WOl63719 WOl64817 (RFO8 Repair / Replacement Plan Numbers NIS-2A-Number) 2 During RF05, the old style capscrews were use to replace 144 of the removed capscrews while 32 of the new redesigned cap screws were used to replace the remaining removed cap screws. During the last outage (RF08), all CRD cap screws removed were visually inspected and all removed cap screws were replaced with the new redesigned cap screws. Prior to the plant returning to operation, the 5 cap screws showing the worst d:miage were analyzed. The results showed that the cracks were due to the same phenomenon as identified in RFO5 and the indications and depth were as expected.

  • Successive examinations will continue for the next three periods in accordance with the Inservice inspection Plan. If cap screws with indications that exceed the established threshold limit of.150 inches flaw depth are detected, a condition report will be initiated to evaluate the condition and take appropriate action prior to returning to operation.

I of 1

I l O l SECTION II ) OPEN ITEMS RESOLUTION l l l. f 1

l I Resolution Of Open items Noted In Last Report (NIS-1-000ll) This section lists an item that was identified as a open item during RFO7. The resolution for this item was not complete at the time outage report NIS-1000ll we:; issued following the last outage. ) j 1 QlE12C002B-SB12 PT exam performed after PT exam accepted - QDR # l sand-blasting (cleaning) 0069-95 weld. Unable to perform ) MT exam. .i This section lists items that were identified during the reporting period for NIS-I-00010 but were not resolved before issuing NIS-1-0001 I following the last outage. i l 1 B33G3-Al-F Entire examination Accepted by Relief Request volume cannot be examined-RR-1-00010 l l SCR 93-0014 (RFOS Item) 2 B33G3-Al-G Entire examination Accepted by ReliefRequest volume cannot be examined-RR-1-00010 SCR 93-0014 (RF05 Item) 1 3 B33G3-Al-H Entire examination Accepted by ReliefRequest volume cannot be examined-RR-I-00010 SCR 93-0014 (RFOS Item) i 4 B33G3-Al-J Entire examination Accepted by Relief Request volume cannot he examined-RR-1-00010 SCR 93-0014 (RF05 Item) l 5 B33G4-B 1-H Entire examination Accepted by Relief Request volume cannot be examined-RR-I-00010 SCR 93-0014 (RF05 Item) 6 B33G4-B i-J Entire examination Accepted by Relief Request volume cannot be examined-RR-1-00010 SCR 93-0014 (RF05 Item) 7 B33G4-B I-K Entire examination Accepted by Relief Request volume cannot be examined-RR-1-00010 l SCR 93-0014 (RFO5 Item) 4 1 1of2 l l

1 l l l Resolution Of Open items (continued) 8 B33G4-B1-L Entire examination Accepted by Relief Request volume cannot be examined-RR-1-00010 SCR 93-0014 (RF05 Item) 9 E32G119-W-32 Entire examination Accepted by Relief Request volume cannot be examined-RR-I-00010 SCR 93-0014 10 E51G001W39 Entire examination Accepted by Relief Request volume cannot be examined-RR-1-00010 SCR 93-0014 i 1 i i j i l l l 2 of 2

) 4 SECTION III a 4 j CODE CATEGORY

SUMMARY

l i 4 J 4 1 i i 3 J 1 a

I 1

'l

CODE CATEGORY

SUMMARY

Abstract Of Examinations - Reactor Pressure Vessel - (RPV ) The following is a summary of the results of hiservice Inspection (ISI) conducted on the Grand Gulf Nuclear Station, Unit 1, Reactor Pressure Vessel (RPV). The sununary is itenuzed by the applicable code categories described in Table IWB-2500-1 of the ASME Section XI,1977 Edition, _ with addenda through and including Summer 1979. GGNS is also committed to meeting the l requirements of Regulatory Guide 1.150, Revision I for inservice inspection, although Regulatory ] guide 1.150 was not applicable during the GGNS pre-service. When the term " visual exam" is used, it will designate a VT-1, VT-2, or VT-3 is performed. B13 Reactor Pressure Vessel-Volumetric Exam Item B1.11 Circumferential Welds Category Item ID Number Drawing Number ReliefRequest B-A Weld JC 351N80B0007 N/A Item Bl.12 Longitudinal Welds I Category Item ID Number Drawing Number ReliefReauest B-A Weld BF 351N80B0007 N/A B-A Weld BG 351N80B0007 N/A B13 Reactor Pressure Vessel-Visual Exams l l Item B4.11 Partial Penetration Weld l i t Category Item ID Number Drawine Number Relief Reauest B-E Weld N18 351N80B0007 N/A Vr-2 l l 1 of 8

~ B13 Reactor Pressure Vessel - Visual Exams (continued) Item No. B7.10 Bolts Studs, and Nuts Category Item ID Number Drawing Number Relief Reauest B-G-2 B ITS GD-HWIBM N/A I-00008 VI-1 BITIN 3 Item B13.20 VesselInterior Attachments Within Beltline Region Category Item ID Number Drawine Number Relief Reauest B-N-2 Weld Attachment 351N80B0007 N/A VI-1 Welds Jet Pump riser arm brace arm pad to vessel weld Surviellance sample holder to vessel weld Item B13.30 VesselInterior Attachments Beyond Beltline Region Category Item ID Number Drawing Number Relief Request B-N-2 Weld Attadumt 351N80B0007 N/A VI-3 Welds Steam dr/er hold-down brackets @ 0,40,140,180,220, and 320 degrees. Lower gaide rod brackets @ 0 and 180 degrees 2 of 8

i ~ 1 B13 Reactor Pressure Vessel-Visual Exams (continued) Item B13.40 Core Support Structure Category item ID Number Drawing Number Relief Request B-N-2 Weld CS 351N90B0007 N/A VI-3 l l Top guide to internal structure Core plate, fuel support orifice, and control rod guide tubes @ Core location 16-25, 16-41,20-17,20-49,44-17,44-49,48-25,48-41 Core plate studs, nuts, and wedges @ core location 05-18,09-10,17-06,47-06,47-60, 55-10, 55-56, 59-18,59-48 1 B13 Reactor Pressure Vessel-Visual Exams (continued) Visual exams required by SILs, MNCRs, NUREG, etc., Not required by Section XI l Category item ID Number Drawing Number Relief Reauest B-N-1 See See Below 351N80B0007 N/A VT-3 Below 351N830009 351N85B0010 RPV-11-1 & 2 Feedwater nozzle sparger holes (augmented inspection in accordance with NUREG-0619) Steam Dryer Drain Channel Attachment Welds (SIL# 374) LPCI Coupling (MNCR# 0212-93) Jet Pump Raiser Brackets - 50% (SIL# 55l) Jet Pump Adjusting Screws (100%) Jet Pump wedges and inlet mixter Shsam Assembly and tack wed! #14 (MNCR# 0220-93) Shsam Assembly to Separator Flange Attachment Weld #14 (MNCR# 0220-93) Shroud head to shroud mating surface between #12 and # 16 Shsam Lower sparger, nozzle tack welds, T-box brackets @ 10,120,170,190,240,350 degrees LPRMs @ core location I l-18,18-27, 24-27, 34-35, 35-26, 42-59, 43-26, 43-34, 51-18 l degrees i f n 3 of 8

i l Abstract Of En.mination (Piping Welds, Components and Supports) The following is an overall summary of the results of Insenice inspection (ISI) conducted on Grand Gulf Nuclear Station, Unit I piping pressure boundary welds, components and supports. Z51 Control Room HVAC J l 1 ) Category item ID Number Class Drawing Relief Request l Number F-A Attach. GZ51B002A-S1 3 GV-1-1 N/A VT-3 Weld F-A Attach. CSZ51B002A-S2 3 GV-1-1 N/A VT-3 Weld 1 l l 4cf8 l

L r Ahstract Of System Hydrostatic Test Examinations First Interval The following is an overall summag of Inservice Inspection (ISI) for System Hydrostatic Testing l conducted at Grand Gulf Nuclear Station. The summary is itemized by the applicable Code Categories described in Table IWB-2500-1, IWC-2500-1 and IWD-2500-1 of ASME Section XI, 1977 Edition, with the Addenda through and including Summary of 1979. In lieu of performing the hydrostatic test, the pressure tests described were performed in accordance with Code Case N-498-1. The term " Pressure Test Zone" refers to the actual System pressure test that actually placed the applicable portion of the system in the condition required for the VT-2 ( Code Category B-P (pressure retaining components) System Number Pressure Test Zone Number Various 03-1-01-6 C41 P-1082-02 E12 P-1085-12 E12 P-1085-13 E12 P-1085-14 E21 P-1087-03 l E22 P-1086-02 l E38 P-1112-02 E5i P-1083-04 i I Code Category D-A, D-B, D-C (pressure retaining components) System Number Pressure Test Zone Number B21 P-1077-03 B21 P-1077-04 E12 P-1085-09 E12 P-1085-10 E12 P-1085-11 G41 P-1088-03 G41 P-1088-04 P41 P-1061-05 P75 P-1070-01 P75 P-1070-02 P75 P-1070-03 P75 P-1070-04 P75 P-1070-05 P75 P-1070-06 P81 P-1093-01 P81 P-1093-02 P81 P-1093-03 5 of 8 I l.

l Abstract of System Pressure Test Examinations First Interval The following is an overall summary of Inservice inspection (ISI) for System Pressure Testing l conducted at Grand Gulf Nuclear Station. The summary is itemized by the applicable Code l Categories described in Table IWB-2500-1, IWC-2500-1 and IWD-2500-1 of ASME Section XI, 1977 Edition, with the Addenda through and including Summary of 1979. The term " Pressure Test Zone" refers to the actual System pressure test that actually placed the l applicable portion of the system in the condition required for the VT-2 i l Code Category H-P (pressure retaining components) i System Number Pressure Test Zone Number Various 03-1-01-6 C41 P-1082-02 E12 P-1085-12 l E12 P-1085-13 L E12 P-1085-14 E21 P-1087-03 E22 P-1086-02 E38 P-i l l2-02 E5i P-1083-04 1 l Code Category C-II (pressure retaining components) System Number Pressure Test Zone Number B21 P-1077-01 B21.E12 P-1077-02 B21 P-1077-05 i B21 P-1077-06 B21 P-1077-07 ] B21 P-1077-08 B33 P-1078-01 B33 P-1078-02 C41 P-1082-03 C41 P-1082-04 C41 P-1082-05 E12 E30 P-1085-02 1 E12 P-1085-03 E12 P-1085-04 E12 P-1085-05 E12 P-1085-06 E12 P-1085-07 E12 P-1085-08 E21 P-1087-02 E22 P-1086-01 l 6of8

~ Abstract of System Pressure Test (continued) Code Category C-H E30 P-1096-01 E30 P-1096-02 E30 P-1096-03 E30 P-1096-04 E30 P-1096-05 E30 P-1096-06 E32 P-1097-02 E38 P-1112-01 E51 P-1083-01 E51 P-1083-02 E51 P-1083-03 E61 P-1091-01 E61 P-1091-02 E61 P-1091-03 E61 P-1091-12 E61 P-1091-13 E61 P-1091-14 E61 P-1091-15 E61 P-1091-16 E61 P-1091-17 M71 P-il10A-01 M71 P-1110A-04 Code Category D-A, D-B, D-C (pressure retaining components) System Number Pressure Test Zone Number B21 P-1077-03 B21 P-1077-04 E12 P-1085-09 E12 P-1085-10 E12 P-1085-ll G4i P-1088-01 P4I P-1061-01 P4i P-1061-02 P41 P-1061-03 P41 P-1061-04 P41 P-1061-05 P41 P-1061-06 P42 P-1063-01 P75 P-1070-01 P75 P-1070-02 P75 P-1070-03 P75 P-1070-04 7 of 8

' Abstract of System Pressure Test (continued l Code Category D-A. D-B, D-C P75 P-1070-05 P75 P-1070-06 P81 P-1093-01 l P81 P-1093-02 P81 P-1093-03 l l l i l 1 1 l i l l 4 i r e i I I 'i 8 of 8 i i 1 5

l SECTION IV DRAWING / ISOMETRICS l i i i l l l

DRAWING / ISOMETRICS LIST l Drawine List 35iN80B0007 35iN80B0009 351N85B0010 RPV-11-1 RPV-11 -2 CRWl-1 i l 4 i l of I l l l

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i GRC (UPPER PORTION) - M CORE PLATE WEDf,E - NTERNAL STRUCTURE 1 CLASS CS LASS CS WELD TO NTERNAL STRUCTURE (UPPER PORTON OF GRO) ll 0 (LOWER POR TON) - CLASS CS \\\\ k -CORE NSTRUMENTATON - UD NUT ASSY'- ll INSTRUMENTATION NEUTRON SOURCE - CORE COMPONENT (l CLASS CS L ASSEMBLY - CORE COMPONENT TERNAL STRUCTURE WELD 10 hTERNAL STRUCRURE NSHROUD - CLASS CS LOW PRESSURE COOLANT NJECTON ELBOW - INTERNAL STRUCTURE HAT i,OR , CLASS CS ORFICED FUEL SUPPORT j CLASS CS CORE PLATE - CLASS CS CONTROL ROD GUIDE IT PUMP .m.. TU6E-CLASS CS h NTERNAL M STRUCTURE i s ONTROL ROD - CONTROL SHROUD SUPPORT I I COMPONENT PLATE - CLASS CS I SHROUD SUPPORT NTERNAL STRUCTURE k,h CYLINDER - CLASS CS - WELD TO INTERNAL i STRUCTURE r*'s 3 I/ : SHROUD SUPPORT LEG - CLASS CS (JET PUMP ADAPTERI A I I r---CLASS CS WELDS TO Ig': CLASS IPRESSURE VESSEL NOTE: CLASS CS ITEMS ARE CORE [ 5 ONTROL ROD DRIVE HOUSNG SUPPORT STRUCTURES 2-En 1 I CLASS CS (UPPER PORIION) J f CLASS 1(LOWER PORil0N) fCOREPLATE s 0 !(' ii d j - u. STUD AND \\ CLASS CS WELDS TO CLAS5 I NUT - CLASS CS j \\ lj PRESSURE VESSEL A i N e h~. r.e:Aay - GGNS-z .c t.. S h[ L:' W -' A O s s,.. .,... c .w - w w- _~,_ N IO

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i i t SECTION V RELIEF REOUESTS l I 1 l t e l l

\\ ~ RELIEF REOUEST LIST RR-I-00008 RR-I-00010 l i e I

GRAN1> GULF NUCLEAR STATION INSERVICEINSPECTION REQUIREhENTS IN' SERVICE INSPECTION SECTION 4 TEN YEARPROGRAM RELTPF REQUESTS b V PAGE 1 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELEF REQUEST I-00008, REVISION 3 l INSERVICE INSPECTION OF CONTROL ROD DRIVE AND INCORE HOUSING WELDS & FLANGE BOLTING I. Compong_n_1: Peripheral control rod drive housing welds (tube-to-tube, tube-to-flange) and bolting located on CRD housings. II. Code: These portions of the CRD and in-core housing were designed and fabricated to the AShE Section l III, Class 1 requirements. Applicable inservice inspections are to be performed in accordance with l AShE Section XI,1977 Edition through and including Summer 1979 Addenda. lQ Q III. Code requirements: r 1. Welds located in 10% of the peripheral CRD housings require surface examination (dye l penetrant) during each ten-year inservice inspection interval in accordance with ASME Section XI, Table IWB-2500-1, Examination Category B-0. 2. Pressure retaining bolting for the flange-to-flange joints, located on the CRD and incore i housings, are required to be visually examined (VT-1) once every ten-year inspection interval in accordance with AShE Section XI, Table IWB-2500-1, Examination Category B-G-2. IV. Information to suonort the determination that the code reauirements are impractical: The weld areas and bolting are not accessible for inspection unless the control rod drive (CRD) i support structures are removed. A 360 surface examination cannot be accurately accomplished from the outside, due to interference from the adjacent CRD housings. Inspection cf the weld from the inside of the CRD housing would require that the CRD mechanism be removed, which could result in damage to the drive. With removal of the drive, a small amount of reactor water would escape to the CRD cavity area, possibly causing contamination of personnel and equipment. The time frame associated with the CRD support structure removal and CRD mechanism would be approximately six (6) man hours per drive. Dosage received by personnel in this interval cannot justify the inspection process to possibly find (\\] a fault which could be discovered by excessive leakage in the drywell sump monitored per Operating License Manual (Technical Specification) limits in effect.

GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICEINSPECTION SECTION 4 TEN YEAR PROGRAM RELEF REQUESTS / lt PAGE 2 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 l RELEF REQUEST I-00008, REVISION 3 l l INSERVICE INSPECTION OF CONTROL ROD DRIVE AND INCORE HOUSING WELDS & FLANGE BOLTING V. Specific reliefreauested: Permission is requested to exempt from inservice inspection, the peripheral CRD housing welds (tube-to-tube, tube-to-flange), the eight (8) bolts associated with each flange of 193 CRD housings and the four bolts associated with each flange of 58 incore housings. j VI. Reasons why relief should be uran *J: l Request for exemption from inservice inspection should be granted for the following reasons: 1. The peripheral CRD housing welds have been examined by radiography and liquid penetrant methods and have been hydrostatic tested in accordance with ASME Section E code requirements. l 2. All incore and CRD housing bolting has been examined in accordance with the requirements of l AShE Section E, which exceed the Section XI (VT-1) virual examina ion requirements. 3. The welds and bolted connections will be subject to pretsure testing in accordance with the l requirements of AShE Section XI, Table IWB-2500-1 and AdhT Section XI Code Case N-l 498-1. 4. If the welds and/or the bolts fail while in operation, the maximum leakage rate, by calculation, will occur at at the peripheral CRD housing tube-to-flange weld. The maximum calculated leak rate is to 681 gpm. By criteria established in Subarticle IWB-1200, " exemptions by make up capacity," the normal make up capability for GGNS is 878 gpm, which exceeds the calculated maximum leakage. 5. Leak detection is provided with the leakage detection system, with continuous monitoring in the l control room. i 6. The CRD housing supports would prevent ejection of the housings in case of total failure of the welds or bolts. 4i O d 7. Removal of the CRD support structure would result in hardships with no compensatory increase in the level ofquality and safety.

GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS b V PAGE 3 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00008, REVISION 3 l INSERVICE INSPECTION OF CONTROL ROD DRIVE AND INCORE HOUSING WELDS h FLANGE BOLTING i l VII. Altemate testing: None NOTE A similar request for relief from preservice inspection requirements was accepted by NRC in GGNS Safety Evaluation Report, Supplement #2. l l ,o l l t !O I

[- GRAND GULF NUCLEAR STATION INSERVICEINSPECTION REQUIREMENTh IN' SERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS PAGE 1 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l INSERVICE EXAMINATION OF PRESSURE RETAINING WELDS I. Comoonent: Inaccessible portions of ASME Section III, Class 1 and 2 pressure retaining and integral attachment piping welds listed in Table 1 (see attached). II. Code: These portions of the pressure retaining and integral attachment piping welds were designed and fabricated to ASME Section III, Class 1 and Class 2 requirements. Applicable inservice inspections are to be performed in accordance with the ASME Section XI,1977 Edition, through and including t'he Summer 1979 Addenda. i III. Code Requirements: Class 1 and Class 2 pressure retaining piping welds are required to be volumetrically and surface examined, essentially 100% of the weld, once every ten year interval in accordance with ASME ' Section XI, Table IWB-2500-1, Category B-J, Table IWC-2500-1, Category C-F. The Class 1 integral attachment welds depicted in table 1 are required to be swface examined once each ten year interval in accordance with ASME Section XI, Table IWB-2500-1, Category B-K-1. IV. Lnfprmation to supoort the determination that the Code reauiremeats are impractical: Portions of welds that were preservice examined have physical obstructions due to design. Due to this limited accessibility, it is impractical to perform the rurface and volumetric examination for 100% of the required examination volume as indicated for the welds listed in Table 1. l V. Specific Relief Requested: Permission is requested to perform the Code required examinations to the extent described in Table 1. s i

h GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS O PAGE 2 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l INSERVICE EXAMINATION OF PRESSURE RETAINING WELDS VI. Reasons why relief should be granted: Request for permission to limit the code required examination to the accessible areas should be granted for the following reasons: 1. The inaccessible portions oflisted pressure retaining welds were examined by radiography, passed in accordance with ASME Section III, Class 1 and 2 requirements. 2. The inaccessible portions of the pressure retaining and integral attachment welds were surface examined (magnetic particle or liquid penetrant), passed in accordance with ASME n III and/or XI, Class 1 and Class 2 requirements. t !U l 3. The piping welds with limited examinations will be subject to pressure testing in accordance with ASME Section XI, Table IWB-2500-1 cr IWC-2500-1, as applicable, and ASME l Section XI Code Case N-498-1. 4. Deleted l 5. Accessible portions of listed welds will be volumetrically and surfhce examined each I inspection interval in accordance with ASME Section XI. Should indications be found, an engineering evaluation will be made to determine if the inaccessible portions of the listed welds have been affected. 6. Leak detection is provided, by way of the leakage detection system with continuous monitoring, for the RHR, RCIC, MS, RWCU, RECIRC and FW systems. 7. The failure of any one of these pressure retaining piping welds would have no adverse effect on plant safety as there is isolation capability and/or shut down capability as part of the plant design. The design analysis bounds the limiting fault conditions for line breads in and outside of containment. 1 ( t .U I

1 } I GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 i TEN YEAR PROGRAM RELIEF REQUESTS o PAGE 3 OF 3 l GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l INSERVICE EXAMINATION OF PRESSURE RETAINING WELDS 8. The calculated maximum piping stresses and usage factor at the integral attachments on the piping, including consideration of the local pipe wall stresses, have been determined in the Class 1 Stress Report and are equal to the following: a) Primary plus secondary (equation 10); 32,775 psi (1.72 S.), b) Usage factor is 0.0442. Circumferential and longitudinal welds in piping with stress levels below 2.4 S. and usage factors below 0.4 are excluded from ISI examinations, in accordance with Table IWB-2500-1 Category B-J. p) \\. 9. Examinations at GGNS of category B-J, B-K-1 and C-F welds have not identified any flaws or evidence of service induced degradation. VII. Alternate testing: 1 The applicable welds will be examined to the maximum extent practical at determined by the extent of the specific limitation. Each weld will be subjected to a volumetric or surface examination as required by Talbes IWB and IWC 2500-1. l

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V lJ 1 > + -... - i ) k. GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 , TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST I-00010, REVISION 6 l TABLEI EXAMINABLE EXAMINABLE ITEM SYSTEM WELD ISO PIPE VOLUMETRIC TYPE SURFACE WELD REASON FOR NO NO NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMITATIONS I E12 G014-FW-44 RH-8-8 6" VALVE TO ELBOW 55 % T 100 % 1 CIRC ELBOW RADIUS 2 B21 G9-C1-B-UB MS-11-8 28" ELBOW SEAM 38 % T 38 % 1 LONG PIPE RESTRADE 3 E51 G004-8 8-1 RI-8-2 6" ELBOW TO ELBOW 70 % T 100 % 2 CIRC ELBOW RADIUS l 4 B21 GIl-D1-B-UB MS-11-11 28" ELBOW SEAM 38% T 38 % 1 IDNG PIPE REsIKAINT 5 B21 G8-Al-B-UB MS-11-2 28" ELBOW SEAM 38% T 38 % 1 LONG PIPE RFSTRAINT 6 B21 G030-FW-23 FW-8-2 24" VALVE TO PIPE 93 % T 100 % 1 CIRC SOCK-O-LET 7 B21 G030-FW-36 FW-8-4 24" VALVE TO PIPE 93% T 100 % 1 CIRC SOCK-O-LET 8 B21 G026-FW-17 FW-11-7 24" PIPE TO TEE 93 % T 100 % 1 CIRC SOCK-O-LET 9 B21 G001-W4 MS-11-3 28" VALVE TO PIPE 82 % T 100 % 1 CIRC PIPE Res1xAINT 10 B21 G00I-W4 MS-11-9 28" VALVE TO ELBOW 82 % T 100 % 1 CIRC PIPE RESTRAINT 11 B21 G9-C1-B-UA MS-11-8 28" ELBOW SEAM 38 % T 38 % 1 LONG PIPE RESTRAINT DELETED 13 E51 G004-7-8-4 RI-8-1 10" REDUCER TO TEE 71 % T 100 % 2 CIRC TEE TEE 14 E31 0004-7-8-9 RI-8-1 10" REDUCER TO TEE 71% T 100 % 2 CIRC 15 E51 G004-7-8-8 RI-8-1 10" REDUCER TO TEE 71% T 100 % 2 CIRC TEE 16 B33 G024.W2 RR-11-19 4" ELBOW TO TEE 62% T 100 % 1 CIRC TEE DELETED 18 B21 Gi l-D' _B-UA MS-II-11 28" ELBOW SEAM 38% T 38 % 1 IONG PIPE RESTRAINT 19 B21 GO "-W9 MS-11-12 28" VALVE TO PIPE 82 % T 100 % 1 CIRC PIPE RESTRAINT 20 B21 G8-Al-B-UA MS-11-2 28" ELBOW SEAM 38% T 38 % 1 IONG PIPE RESTRAINT 21 E51 G001-W1 RI-8-12 6" VALVE TO ELBOW 73 % T 100 % 2 CIRC ELBOW RADIUS 22 E51 G001-W40 RI-11-4 6" VALVE TO ELBOW 51.5 % T 100 % 1 CIRC ELBOW RADIUS 23 B33 GOO 3-W5 RR-11-2 24" ELBOW TO PUMP 73% see note 1 T 100 % 1 CIRC PUMP 24 B33 G001-W6 RR-11-2 24" PIPE TO PUMP 58% see note i T 100 % 1 CIRC PUMP 25 B33 G001-W8 RR-11-3 24" VALVE TO PIPE 50% see note 2 T 100 % 1 CIRC VALVE 26 B33 G001-W28 RR-11-9 24" ELBOW TO PUMP 62% see note 1 T 100 % 1 CIRC PUMP 27 B33 G001-W29 RR-11-9 24" PUMP TO PIPE 61% sce note l T 100 % 1 CIRC PUMP I

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  • GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST I-00010, REVISION 6 l

TABLE 1 EXAMINABLE EXAMINABLE ITEM SYSTEM WELD ISO PIPE VOLUMETRIC TYPE SURFACE WELD REASON FOR NO NO NO NO SIZE COMPONENT AREA SCAN AREA CLASS TYPE LIMrrATIONS 28 B33 G001-W31 RR-11-10 24" VALVE TO PIPE 50% see note 1&2 T 100 % 1 CIRC VALVE 29 B33 GS-B1-B RR-11-9 4*/24" SWEEP TO PIPE 59% see note 1 T 100 % 1 BRANCH SWEEP-O-LET 30 B33 GS-BI-E RR-11-9 4"/24" SWEEP TO PIPE 63% see note 1 T 100 % 1 BRANCH SWEEP-O-LET 31 B33 G023-W37 RR-11-15 20" TEE TO PIPE 65% see note 1 T 100 % 1 CIRC TEE 32 B33 G024-W8 RR-11-16 4" PIPE TO SWEEP 50% see note 2 T 100 % 1 CIRC SWEEP-O-LET 33 B33 G024-W27 RR-11-17 4" PIPE TO SWEEP 50% see note 2 T 100 % 1 CIRC SW12r-O-LET 34 B33 G10-B1-L RR-11-11 12'/16' SWEEP TO PIPE 50% see note 3 P 100 % 1 BRANCH SWEEP-O-GT 35 B33 G10-B1-K RR-11-11 12*/16" SWEEP TO PIPE 50% see note 3 P 100 % 1 BRANCH SWEEP-O-LET 36 B33 G10-B1-J RR-11-11 12*/16' SWEEP TO PIPE 50% see note 3 P 100 % i BRANCH SWEEP-O-LET 37 B33 Glo-BI-H RR-11-11 12"/16" SWEEP TO PIPE 50% see note 3 P 100 % 1 BRANCH SWEEP-O-LET r 38 B33 G10-BI-G RR-11-Il 12*/16" SWEEPTO PIPE 50% see note 3 P 100 % 1 BRANCH SWEEP-O-LET 39 B33 G10-Bi-F RR-11-11 12*/16' SWEEP TO PIPE 50% see note 3 P 100 % 1 -BRANCH SWEEP-O-LET 40 B33 G001-W34 RR-11-11 24" PIPE TO CROSS 50% see note 3 P 100 % 1 CIRC CROSS 4i B33 G10-Bl-A RR-11-11 16" PIPE TO CROSS 50% see note 3 P 100 % 1 CIRC CROSS 42 B33 G10-BI-B RR-11-11 16* PIPE TO CROSS 50% see note 3 P 100 % 1 CIRC CROE 43 B21 G8-Al-C MS-II-2 8"/28" SWEEP TO PIPE 100 % T 98 % 1 BRANCH PIPE SUPPORT 44 B2I G026-W36 !~n-11-1 24" PIPE TO VALVE 95 % T 100 % 1 CIRC PIPE SUPPORT 45 B2i G8-Al-L,M,N,P MS-11-2 28" LUGS TO PIPE N/A N/A 49% 1 INT ATT PIPE RESTRAINT 46 B2I G10-B1-L,M,N,P MS-11-5 28" LUGS TO PIPE N/A N/A 49% 1 INT ATT PIPE ResiKAINT 47 B2i G9-CI-L,M,N,P MS-11-8 28" LUGS TO PIPE N/A N/A 49% 1 INT ATT PIPE RE5TKAINT 48 B21 G11-DI-L,M,,N,P MS-11-11 28' LUGS TO PIPE N/A N/A 49% 1 INT ATT PIPE RESTRAINT 49 B33 G001W27 RR-11-9 24' PIPE TO VALVE 50% see note 1 T 100 % 1 CIRC VALVE 50 B33 G00lW33 RR-11-10 24' VALVE TO PIPE 50% see note l T 100 % 1 CIRC VALVE 51 B33 G10-Al-A RR-11-4 16' CROSS TO PIPE 50% see note 3 P 100 % 1 CIRC CROSS 52 B33 Glo-Al-B RR-11-4 16* CROSS TO PIPE 50% see note 3 P 100 % 1 CIRC CROSS 53 B33 G6-B1-C RR-11-9 4*/24" PIPE TO SWEEP 50% see note i T I00 % I BRANCH SWEEP 54 B33 G10-Al-F RR-11-4 16*/12' PIPE TO SWEEP 50% see note 3 P 100 % i BRANCH SWEEP

.e GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREhENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT 1 RELIEF REQUEST I-00010, REVISION 6 l TABLE 1 EXAMINABLE EXAMINABLE HEM SYSTEM WELD ISO PIPE VOLUMETRIC TYPE SURFACE WELD REASON FOR NO NO NO NO SIZE COMPONENT AREA SCAN taEA CLASS TYPE LIMITATIONS i 55 B33 G10-Al-G RR-l 1-4 16"/12" PIPE TO SWEEP 50% see note 3 P 100 % 1 BRANCH SWEEP 56 B33 G10-Al-II RR-11-4 16"/12" PIPE TO SWEEP 50% see note 3 P 100 % 1 BRANCH SWEEP 57 B33 G10-Al-J RR-11-4 16"/12" PIPE TO SWEEP 50% sce note 3 P 100 % i BRANCH SWEEP 58 B33 G10-Al-K RR-114 16"/12" PIPETO SWEEP 50% sce note 3 P 100 % 1 BRANCli SWEEP 59 B33 G10-Al-L RR-11-4 16"/12" PIPE TO SWEEP 50% see note 3 P 100 % 1 BRANCH SWEEP 60 B33 GOO 1W4 RR-11-2 24" VALVE TO PIPE 50% see note 1 T 100 % 1 CIRC VALVE 61 B33 G00lW9 RR-11-3 24" PIPE TO VALVE 50% see note 1 T 100 % 1 CIRC VALVE 62 B33 G00lW10 RR-11-3 24" VALVE TO PIPE 50% see note 1 T 100 % 1 CIRC VALVE 63 B33 G6-Al-C RR-11-2 4"/24" PIPE TO SWEEP 50% see note 1 T 100 % 1 BRANCH SWier 64 B33 GS-Al-E RR-11-2 4"/24" PIPE TO SWEEP 50% see note i T 100 % 1 BRANCH SWEEP 65 B33 GS-Al-B RR-11-2 4"/24" PIPE TO SWEEP 50% sm note I T 100 % 1 BRANCH SWEEP 66 B21 G11-Dl-C MS-11-11 28"/10" PIPE TO SWEEP 57 % T 97 % 1 BRANCH HANGER 67 B21 G10-BI-C MS-I I-5 28"/10" PIPE TO SW121 71% T 100 % 1 BRANCH HANGER 68 B21 G10-B1-E MS-11-5 28"/10" PIPE TO SWEEP 71 % T 85 % 1 BRANCH HANGER 69 B21 G10-BI-F MS-11-5 28"/10" PIPE TO SWEEP 78 % T 100 % 1 BRANCH HANGER 70 B21 G10-BI-H MS-I I-5 28"/10" PIPE TO SWEEP 78 % T 100 % 1 BRANCH HANGER 71 B21 G10-B1-G MS-11-5 28"/10" PIPE TO SW12r 78 % T 100 % 1 BRANCH HANGER 72 ESI G004W18 RI-8-21 6" VALVE TO PIPE 83.18 % T 100 % 2 CIRC PIPE RESTRAINT l 73 G33 0012W54 CU-l1-13 6" VALVE TO ELBOW 85.59 % T 100 % 1 CIRC ELBOW RADIUS 74 B21 G00lW5 MS-11-9 28" VALVE TO PIPE 62.8 % T 100 % 1 CIRC VALVE 75 B21 G001W10 MS-11-12 28" VALVE TO PIPE 80.8 % T 100 % 1 CIRC VALVE 76 B33 G00lW3 RR-11-1 24" ELBOW TO VALVE 30.0 % T 100 % 1 CIRC VALVE 77 B33 000lW26 RR-11-8 24" ELBOW TO VALVE 50.0 % T 100 % 1 CIRC VALVE 78 B33 G3-Al-F,G,H,I RR-11-1 24" LUGS TO PIPE N/A N/A 75 % 1 INT ATT PIPE RESTRAINT 79 B33 G4-BI-II),K,L RR-11-8 24" LUGS TO PIPE N/A M/A 75 % 1 NT ATT PIPE RESTRANT 80 E32 G119W32 IV-8-3 1.5' TEE TO ELBOW N/A N/A 83 % 1 CIRC PIPE SUPPORT 81 ESI G001W39 RI-11-4 6" PIPE TO VAI VE 79.0 % T 100 % 1 CIRC VALVE l

O O t-GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 TEN YEAR PROGRAM RELIEF REQUESTS GRAND GULF NUCLEAR STATION UNIT I RELIEF REQUEST I-00010, REVISION 6 l I TABLE 1 LEGEND [ P = SCAN PARALLEL TO THE WELD T = SCAN TANGENT (PERPENDICULAR) TO THE WELD NOTES:

1. In addition to the "T" scan limitation, these welds are augmented by the requirements of NUREG 0313 and therefore are examined with a parallel scan that is not required by ASME Section XI. The parallel scan is limited to one side of the weld (50%) due to the fittings being joined by the weld.

t 2. 100% coverage was obtained in one direction only, using refracted longitudinal wave. (

3. The "P" scan is performed for compliance with NUREG 0313,100% of ASME Section XI coverage is obtained without limitation.

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