ML20234D927
| ML20234D927 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/04/1988 |
| From: | Kintner L Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8801070319 | |
| Download: ML20234D927 (104) | |
Text
_ _ _ _ - _ _ _ _ - - _ _ _ _ __ --____ _ _
,pf Ik UNITED STATES y g NUCLEAR REGULATORY COMMISSION 5 j WASHINGTON, D. C. 20555
\*****/ JAN04%
Docket No. 50-416 LICENSEE: System Energy Resources, Inc.
FACILITY: Grand Gulf Nuclear Station (GGNS), Unit 1
SUBJECT:
SUMMARY
OF OCTOBER 22, 1987 MEETING REGARDING LICENSING ACTIONS The purpose of the meeting was to discuss the status and schedule of licensing actions. Enclosure 1 is a list of attendees. Enclosure 2 is an agenda and handout prepared by the licensee.
l The plant continued to operate at 100% power. The second refueling outage 1 (RF02) is scheduled for November 6, 1987 to January 8, 1988. Major RF02 activities will include expansion of the control room and correction of human engineering deficiencies found as a result of the detailed control' room design review. Also, equipment required by 10 CFR 50.62 regarding anticipated transients without SCRAM (ATWS) will be installed including modifications to )
the ATWS recirculation pump trip and standby liquid control system (SLCS) and j installation of the alternate rod insertion system. Modifications to the SLCS include increasing design pressure to 1500 psig, adding pulsation dampeners, improving the control capability of the test loop and adding flow instrumentation to the test loop.
The following coments were made regarding particular agenda items.
III.A.1 The request to delete the requirement for operability of containment isolation valves during refueling was briefly discussed. The licensee stated that, of the valves initially requested, eleven are drywell isolation valves which would not isolate the reactor vessel during an inadvertent draining of the vessel and, therefore, could easily be justified as not required to be operable during refueling. However, !
this amendment will not be pursued at this time.
III.A.2 The licensee said that General Electric Company (GE) analyses indicate that 2 of 20 safety relief valves (SRVs) may be inoperable and still meet ASME Code allowable stress values in the reactor pressure vessel ;
(RPV) for an anticipated transient without scram (ATWS). With 7 SRVs out of service, the GE analysis indicates that for an ATWS event the ASME code allowable values would be exceeded but the RPV integrity .
would be maintained. The licensee will submit results of the GE analysis I as requested by the staff. ;
III.A.3 Interlocks will be installed on the residual heat removal -(RHR) system
, suction valves from the suppression pool and valves in the test return lines to the suppression pool to prevent an inadvertent a,lignment of the reactor vessel to the suppression pool and consequent draining .
of the vessel.
I 8801070319 880104 PDR ADOCK 05000416 ,
p PDR I
_ J
III.B.1 The licensee had previously connitted to an inspection of an RHR heat exchanger durin.a RF02 because of biofouling in the standby service water system. Both RHR heat exchangers had been inspected in RF01 and no significant fouling was found. No changes in RHR performance were noted during fuel cycle 2. The biofouling was found in the basins and one diesel generator cooling water circuit. The licensee plans to chemically clean one of the basins during RF02. The staff said it had no objection to not inspecting an RHR heat exchanger in RF02.
III.B.2 The licensee requested the status of the staff's re-evaluation of reporting requirements in 10 CFR 50.72 and 10 CFR 50.73. In response to the licensee's July 16, 1985 request for exemption, the staff had stated in its October 2, 1987 letter that it was reevaluating these requirements on a generic basis. Subsequent to the meeting the NRC Project Manager found that the generic effort is continuing. Region 11 staff are considering specific deportability questions for Grand Gulf.
III.B.3 The low pressure turbine will be inspected by the turbine manufacturer, Kraftwerk Union of West Germany.
IV. The licensing actions are proceeding on a satisfactory schedule. The schedule as of the meeting date is given in Attachment 1 to Enclosure 2.
V.A. The licensee said it is interested in implementing Generic Letter 86-10 regarding removal of fire protection specifications from the Technical Specifications (TS) and Generic Letter 87-09 regarding changes to Sections 3.0 and 4.0 of the TS. The licensee has requested an amendment per Generic Letter 86-10. The staff has been reviewing earlier requests for the Callaway and Wolf Creek Plants and plans to review the GGNS request after completion of these requests. A generic letter is being prepared for use in evaluation of subsequent plants.
The licensee has submitted a request for specific one-time exceptions to Section 3.0.4 of the GGNS TS and plans to submit a request for the changes allowed in Generic Letter 87-09 during 1988.
The licensee is a participant in the BWR Owners Group effort regaroing ,
improvement of tee.hnical specifications. BWR-6 Standard Technical Specifications will be prepared by the Owners Group. Then the licensee will submit a request to amend the GGNS TS in accord with the improved BWR-6 Standard Technical Specifications.
V.B. The NRC Project Manager described the modified review process for licensee amendments which was implemented September 4, 1987, wherein: )
incomplete applications will be returned for resubmittal (Category 1); j applications which can be determined to have no significa'nt hazards j considerations (NSHC) without technical staff review will be noticed l with a preliminary finding of NSHC (Category 2); and applications which j require technical staff review will be noticed for prior hearing without I a finding about the matter of NSHC. (Category 3). l a
JAN 04 ngy 5
VI. The staff indicated that the licensee appears to be improving in many functional areas.
The out oflicensee materialstated one area it reports non-conformance is attempting)to (MNCR andimprove qualityisdeficiency the close reports (QDR). Although the procedure allows 7 days to prepare these reports, they will be done sooner if possible. In addition, significant MNCRs and QDRs will be elevated to higher management if they are not completed in a timely manner.
/
+2 Lester L. Kintner, Sr. Project Manager Project Directorate 11-1 Division of Reactor Projects I/II l cc: See next page l
DISTRIBUTION:
% Docket-File l NRC & Local PDRs PD21 r/f EAdensam LKintner 0GC-Bethesda EJordan JPartlow NRC Participants ACRS(10)
- 0FC :PDII -
PR : / DI :DRPR: : : : :
HAME :LK nr :E de sam : : : : :
DATE :12/1f/87 :12/0l/87 : : : : : .
-o l OFFICIAL RECORD COPY
Mr. Oliver D. Kingsley, Jr.
System Energy Resources, Inc. Grand Gulf Nuclear Station (GGNS) a cc:
Mr. Ted H. Cloninger Mr. C. R. Hutchinson Vice President, Nuclear Engineering GGNS General Manager and Support System Energy Resources, Inc.
System Energy Resources, Inc. Post Office Box 756 Post Office Box 23054 Port Gibson, Mississippi 39150 Jackson, Mississippi 39205 Robert 2, McGehee, Esquire The Honorable William J. Guste, Jr.
Wise, Cart a . Child, Steen and Caraway Attorney General-P.O. Box 651 Department of Justice '
Jackson, Mississippi 39205 State of Louisiana Baton Rouge, Louisiana 70804 Nicholas S. Reynolds, Esquire Bishop, Liberman, Cook, Purcell Office of the Governor and Reynolds State of Mississippi 1200 17th Street, N.W. Jackson, Mississippi 39201 j Washington, D. C. 20036 i Attorney General Mr. Ralph T. Lally Gartin Building Manager of Quality Assurance Jackson, Mississippi 39205 Middle South Utilities System Services, Inc.
P.O. Box 61000 Mr. Jack McMillan, Director New Orleans, Louisiana 70161 Division of Solid Waste Management Mississippi Department of Natural Mr. John G. Cesare Resources Director, Nuclear Licensing System Energy Resources, Inc. Post Office Box 103S5 P.O. Box 23054 Jackson, Mississippi 39209 Jackson, Mississippi 39205 Alton B. Cobb, M.D. I Mr. R. W. Jackson, Project Engineer State Health Officer i Bechtel Power Corporation State Board of Health 15740 Shady Grove Road P.O. Box 1700 Gaithersburg, Maryland 20877-1454 Jackson, Mississippi 39205 i Mr. Ross C. Butcher President Senior Resident Inspector Claiborne County Board of Supervisors U.S. Nuclear Regulatory Comission Port Gibson, Mississippi 39150 Route 2, Box 399 Port Gibson, Mississippi 39150 Regional Administrator, Region II U.S. Nuclear Regulatory Comission 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 ,
Mr. James E. Cross GGNS Site Ob ector System Er rgy Resources, Inc.
P.O. Box 756 Port Gibson, Mississippi 39150
Enclosure 1 NRC - SERI Meeting 10/22/87 Attendees i SERI, Director, Nuclear Licensing J. G. Cesare J. L. Robertson SERI M. L. Crawford SERI Manager, Licensing H. C. Dance NRC, Section Head, Projects R II R. C. Butcher NRC, Sr. Resident Inspector.
i L. L. Kintner NRC, Project Manager i
i i
I i l
.' . Enclosure 2 l
NRC-SERI LICENSING ACTION STATUS MEETING October 22, 1987 l
AGENDA i
I. INTRODUCTION j 1
1 II. PLANT ACTIVITIES A. Plant Status .JG Cesare B. RF02 Scope Update JL Robertson l C. Recent Plant Issues'/ Events JGC_
1 III. SPECIAL TOPICS OF INTEREST A. NRR Interface Issues
- 1. RF02 Support (Attachment 1) ML Crawford
- 2. Safety Relief Valves Out-of-Service MLC.
- 3. Potential for Draining RPV JLR B. Region II Interface 1 sues
- 1. Deletion of Commitment to Inspect RHR MLC Heat Exchanger During RF02 ,
- 2. Report:bility of Isolations Actuated by NRC ESF Control Systems ,
- 1. RF02TechSpecs(Attachment 1)
- 2. RF02 Deferrals (Attachment 1)
- 3. RF02 Miscellaneous (Attachment 1)
- 4. SERI Organization Changes .
- 5. 10CFR20.103 Exemption Request J10MISCS7102101 - 1
-- _ 1- __ . - - _ _ _ _ _ . - _ - - - _ _ _ _ _
4 B. SERI Action
- 2. Summary of SRV Out-of-Service Analysis 10/23
- 3. Process Control Program (PCP) RAI 11/12 .
- 4. Unit 2 Preservation & QA Program 11/16
- 5. Summary Level Long Term Plant Schedule 11/30 V. OTHER-A. Generic Letters / Technical Specifications JGC ,
J B. Role of NRC Project Manager NRC 1
VI4 OBSERVATIONS REGARDING LICENSEE PERFORMANCE NRC Attachments I
- 1. RF02 Action Status
- 2. Recent SERI Submittals l 3. Forecast (Next 90 days) l l
J10MISCS7102101 - 2 l
l l
Attachment 1 SERI/NRC RF02 LICENSING SUPPORT ACTIONS
(
I. TECH SPECS (
A. RF01 Lessons Learned 4
- 1. Core Alteration Definition Issued 9/10
- 2. Snubber Test Sample Issued 9/10
- 3. Spec. 3.0.4 Exception Resubmit on 10/22 Issue by 12/9
- 4. Cont. Isolation Instrumentation TBD i
B. RF02 Support
- 1. ATWS Changes
- Response to RAI pertaining to Submit on 10/22 j proposed TS changes Issue by 12/15 1
- SLCS Relief Valve Setpoint' Submit on 10/22 )
Issue by 12/20
- 2. Reload Licensing Package - Cycle 3 To.be Noticed 11/4 l Issue by 12/18 Include MAPLHGR Curves and LFWH Analyses
- 3. Fire Protection Submitted TS changes related to Noticed 9/23 smoke and fire detector installation -Issue by 11/16
- 4. RWCU Containment Isolation Submit on 11/6
. Issue by 12/30 '
- Change power supply designation II. DEFERRALS A. RG 1.97, Flux Monitoring
- PCOL submitted to NRC 7/1
- SERI submitted revised PCOL SHC based 8/4 based on NRC comments
- Notice in Federal Register 8/26 Issue to SERI 11/6 J10 MISC 87102101 - 3 W _ - - - - , - , - _ _ - - - - - - _ - - , - - _ _ _ - - - - - , - - _ _ _ - - _ - - _ - _ _ _ _ _ - - - _ _ - - - - - . - - - - - - - - - - - - . - - - - - - - - - ~~ -- - --,-----------__-a.__- ---- --J
B. MSIV/ECCS Inst. Lines
- Formal deferral request submitted with 7/2 proposed commitment to install addition'al MANUAL VALVE
- NRC response to SERI 9/4 l C. EDG II
- Deferral request submitted 6/30
- NRC response to SERI 10/15 III. OTHER A. ISI Relief Request (RPV Nozzles)
- Submitted relief request for areas not 6/12 accessible or practical from geometry standpoint, RPV nozzles, RPV lower head, various ECCS piping
- Mtg with NRC to discuss moratorium on 10/15 ISI RPV relief requests
- Submit revised ISI RPV relief request 10/23 Response to SERI 12/15 l
1 B. ISI Relief Request (Later Addition of ASME Code)
- Submit relief request to adopt later 8/10 edition of ASME code for Class 3 Integral Attachments ,
- Submit relief request to adopt later 8/10 ;
edition of ASME code to allow use of )
pressure test boundary definition j
- Response to SERI 12/15 I
1 s
J10 MISC 87102101 - 4 i
, Attachment 2 i
i 1
RECENT SERI SUBMITTALS 1
1 l
l 9
MP&L NUCLEAR LICENSING & SAFETY RECENT MF&L LICENSING ACT1Y1 TIES PAGE: 1 STE: 10/208T ACTION TRACIING MANAGEMENT SYSTEM HQllTAL BATE NEC RE0 VEST DATE SL CORRES. NUM RESPONSE MP&L CORRES. NUM 10FIC OF SUBhl1TAL DESCRIPTION MP&L ID NUM NEEDED TAC NUMBER
/13/87 04/03/87 ATWS SUBMIT PCOL REQUESTING iS CHANGES 10 INCORPORATE ATWS DESIG' 1M-87/0152 AECM-87/0055 l70340
/14/87 07/21/87 RELIEF REQUEST SUBMIT REQUES1 FOR RELIEF FROM THE ASME SECT. Il 1977 987/0147 PMI-87/4361 EDITION, SUMMER 1979 ADDENDA, TABLE IWD-2500-1, REGARDING 70513 INSPECTION INTERVAL.
/14/87 08/10/87, MONTHLY OPERATING REPORT SUBMIT MONTNLY OPERATING REPORT FOR JULY 1987
@M-67/0150 X 3 170624 (
l
/14/B7 08/10/87 CONTAINMENT YENTING PROCEDURES SUBMIT CONTAINMENT YEWilNG PROCEDURES
- @M-87/0155 X
- 70625
/21/87 08/03/07 10CFR20 EXMP RAI $r Mll AECM RESPONDING 10 RA] ON 100FR20 EXEMPT 10N REQUEST.
- CM-87/0159 MAEC-87/0184 170550 I
t/21/87 // SR SUBMllSR10NRCCONCERNINGDIVIID/GTRIPDNHIGH
'@M:87/0161 IR 87-7-12 VIBRATION DURING MONTHLY SURVEILLANCE.
I70519 l/21/67 // DIV II EDG DEFERRAL SUBMIT SUPPLEMENTAL INFORMATION ON LIMITED DEFERRAL OF
- @M-87/0157 X INSPECTIONS ON THE DIY!SIDH II DIESEL GENERATOR I i70626 1/24/87 07/31/07 X SUBhl1 PM10F INSPECTION FEES.
- @Q-87/0166 MEC07/183 l70562 1/25/07 // REV 14 PHYSICAL SECURITY PLAN SUBMIT REVISION 14 TO GGNS PHYSICAL SECURITY PLAN AND
- @M-87/0lS6 X REVISION 4 10 GGNS SAFEGUARDS CONTINGENCY PLAN
)70627
)/28/87 // EFFLUENTS SUBMIT SEMIANNUAL EFFLUENT RELEASE REPOR110 NRC.
(CM-87/0165 NLSAP 2.4 ,
) 61340 l
)/28/87 08/04/86 HYDROGEN CONTROL SUBMll OUARTERLY STATUS REPOR1 JUNE,1987, ' DEGRADED CORE lCM-87/0163 LICENSE COND. ACCIDENT NYDR0 GEN CONTROL PROGRAM' 10 THE NRC
) 70379 3/28/87 06/30/07 LER 86-029-09 SU6MIT LER 10 NRC CONCERNING PIPE FOULING RESULTING IN LOW
!CM-87/0169 AECM-87/0126 FLOWS 10 ESF ROOM COOLERS AND RELATED SSW CONCERNS,
) 70477
o
- 1 MP&L NUCLEAR LICENSING & SAFETY ACTION TRACT!NG MANAGEMENT SYSTEM RECEN1 MP&L LICENSING ACTIVITIES PAGE: 2 i 2TE: 10/21/87-
>::::::::::::: :::::::: :::::.:::::::::: :::::::::::::::::::::::::::::: :::::::::::::::::::::::::::::::::::::::::::::::::::::::::::- l IBMITTALDATE NRC REQUESTDATE llCORRES.NUM RESPONSE MP&L CORRES. NUM TOPIC 0F SUBMITTAL DESCRIPTION MP&L ID NUM HEEDED TAC NUMBER SUlMIT CEEP 4.1 AND EPP 10-S-01-1 TCH 110 REV. 12,
/28/87 // CEPP AND EPP X 10-2-01-7 REV. 6,10-S-01-23 REV.10 AND 10-S-01 REY. 310 CM-07/0162-70569 THE NRC.
f28/87 07/29/87 LER SUBMITLER 87-011-00 CONCERNING THE RWCU CONTAINMENT i D07/0168 IR87-7-17 ISOLATION VALVE ISSUE.
70572 f28/87 07/29/87 LER SUBMIT LER 10 NRC CONCERNING RWCU POST PUMP VALVES POWERED IR87-7-14 FROM DIVISION 1 POWER.'
& 87/0168
'70536
/28/87 07/29/87 LER SUBMli LER 87-011-00 CONCERNING INE RWOU CONTAINMENT
&87/0168 IR 87-7-17 ISOLAi!0N VALVE ISSUE.
70572
/31/87 // LER . SUBMIT LER ON NEW FUEL CONTAINER DROPPED FROM TRANSFER
&87/0171 X CART DUE TO PERSONNEL ERROR
- 70628 l l
/01/87 // RESPONSE 10 SEC PLAN COMMENTS SUBMIT TO NRC RESPONSES TO NRC COMMENTS ON REVISION 1310 D87/0170 X 66HS PHYSICAL SECURITY PLAN l70629
'/03/87 08/06/87 LER SUBMli LER 10 NRC CONCERNING REACTOR SCPdM FROM TURIINE
&B7/0173 IR 87-8-3 CONTROL VALVE FAST CLOSURE.
t70551
>/03/87 // SCENARIOOBJECTIVE SUBMIT A DESCRIPTION OF INE OBJECTIVES OF INE ;
- &87/0167 X EXERCISE /ACTIONSTOBETESTEDTONRC.
)70559 1/04/87 07/28/87 ERC PSP SUBM11 REVISED PAGES TO EP PGP BASED ON NRC CONFERENCE CALL
- CM-87/0164 MTO-87/Oll8 FOR RESOLUTION OF NRC COMMENTS.
)70527 ,
1/04/87 08/07/87 LER SUBM11 LER 10 NRC CONCERNING DUCT WORI IN CONTROL BUILDING lCM-87/0172 IR 87-8-4 NOT ABLE TO WITNSTAND PRESSURE DROP.
D 70552 9/10/87 08/28/87 X SUBMIT ADDITION 100FR55.25 SUPPORilNG MEDICAL INFORMA110N.
[CM-87/0176 JEC MEM0 D 70576 9/10/87 // X SUBMil LICENSE RENEWAL APPLICA110NS.
[CM-87/0177 TRAINING 170577
MP&L NUCLEAR LICENSING & SAFE 1Y RECENT MP&L LICENSING ACTIYli!ES PAGE: 3 QVE: 10/21/87. ACTION TRACIING MANAGEMENT SYSTEM LTBMiiTAL DATE NRC REQUEST DATE BL CORRES. HUM RESPONSE MP&L CORRES. NUM TOPIC 0F SUBMITTAL DESCRIPTION MP&L ID HUW NEEDED TAC NUMBER s::::::::::::: :::::::: :::::::::::::::: :::::::::::::::::::::::::::::: :::::::::::::::::::::::::::::::::::::::::::: ::::::::: :::.*
/10/87 // ORGANIZATIONCHANGE SUBMil TO NRC PCOL REGARDING NUCLEAR SUPPORT ORG CHANGE
@M-87/0174 X l70630
/11/87 07/16/87 IEB SUBMIT IEB 87-01 RESPONSE 10 NRC: THINN]NG OF PIPE WALLS 11 KM-87/0175 PMI-87/4081RC NUCLEAR POWER PLANTS.
70483
/11/07 07/09/87 IEB SUBM11 IEB RESPONSE TO NRC CONCERNING THINNING OF P]PE f EM-87/0175 MAEC-87/0168 WALLS.
l70539 111/87 07/13/87 PIPE WALL THINNING SUBMIT INFORMATION CONCERNING PROGRAMS FOR MONITORING THE.
KM-87/0175 MAEC-87/0168 THICINESS OF PIPE WALLS IN HIGH ENERGY $1NGLE PHASE AND IWO t70479 PHASE CARBON STEEL PIPING.
V11/87 // DIV II EDG DEFERRAL SUBMIT SUPPLEMENTAL INFORMATION ON LIMITED DEFERRAL OF
'@M-87/0179 X INSPECTIONS ON THE DIVISION II EDG D70631 114/87 07/28/87 SLCS SUBMil ADDITIONAL INFORMA110N REQUESTED BY NRC CONCERNING
!@Q-87/0149 mig-86/0692 THE INCREASE IN THE SLCS RELIEF VALVE SETPOINT.
)70525 114/87 08/04/87 OL EXAM SCHEDULES SUBMIT AECM FROVIDING FY 1988,1989,1990,1991 OL EXAM
!@M-87/0160 MAEC-87/019] NEEDS.
)70549 115/87 // MONTHLY OPERATING REPORT SUBMIT MONTHLY OPERAllNG REPORT FOR AUGUST 1987
[@M-87/0182 X
) 70632 V17/87 // EPP SUBMITTAL SUBMIT 10-S-01 15 REV. 510' THE NRC. ,
lC0-87/0181 NLSAP2.8
) 70578 J/30/87 07/31/87 LER 87-005-2 SUIMIT UPDATE LER 10 NRC CONCERNING 3 MSL RAD]ATION MONITOR!
lCM-87/0184 AECM-87/0144 EXCEEDINGTECHSPECLIM!i.
) 70537 D/02/87 09/03/87 SAFETY ISSUES MGMT SYSTEM SUBMilSAFETYISSUESMANAGEMENTSYSTEMLISTTONRC.
(CM-87/0186. MAEC-87/0208 b70602.
SUBMIT COPIES OF COMPLETE EXIRCISE MANUAL, INCLUDING DESCR.
D/02/87 // EXERCISE SCENARIO
[CM-87/0183 X OF SCENARIO, LICENSE ACTIONS, MESSAGES PROVIDED 10 PLATERS, D 70558 DATA AVAILABLE TO PLAYERS AND INFO PROVIDED 10 CONTROLLERS.
MP&L NUCLEAR LICENSING & SAFETY ACTION TRACKING MANAGEMENT SYSTEM RECENT MP&L LICENSING ACTIVITIES PAGE: 4 STE: 10/21/87* i EBQITIAL DATE NRC RE0 VEST DATE
'8L CO22ES. NUM RESPONSE MPLL CORRES. NUM TOPIC OF SUBMITTAL DESCRIFi10N GP&L ID NUM NEEDED TAC NUMBER 8::::::::::::: :::::::- :::::::::::::::: ::::::.::::::::::::::: ::::::: :::::::::::::::::::::::::::::::::::::::::::::: ::::::::::::-
)/02/87 03/13/87 NUREG-Il50 SUBMIT SERI COMMENTS ON BRAFI NUREG-Il50 TO THE NRC.
%M-87/0187 FED. REG.
)70301
)/07/87 10/06/87 PHYSICAL SECURIll F:ENT SUBMIT AECM ON REPORT OF PHYSICAL SECURJTY EVENT.
i@M-87/0191 GGNS SECURITY .
) 70614
)/09/87 // CYCLE 3 RELOAD PCOL SUBMIT PCOL FOR CYCLE 3 RELOAD lC0-87/0189 X
)70633 D/12/87 05/07/07 EPP SUBMITTAL SUBMIT EPP 10-S-01-20 REY. 5 TO THE NRC.
[C0-87/0188 NLAP 2.8 170601 0/12/07 // MONTHLY OPERATING REPORT SUBMIT MONTHLY OPERATJHG REPORT FOR SEPTEMBER 1987
[CM-87/0192 y .,
70634 !
D/16/87 07/31/87 ATWS SUFMIT DESCRIPTION OF PROCEDURE TO TEST BACIUP SCR
[CM-87/0193 MAEC-87/0186 INCLUDING INITIATING CIRCUliRY DURING EACH REFUELING OUTAGE.
D 70530 D/16/87 09/04/87 LER SUBMIT UPDATE TO LER 87-013: VENTILAi]DN DUCT SECTIONS
!CM-87/0195 AECM-87/0172 PROVIDE TORNADO DEPRESSURIZAi!0N ANALYSIS RESULTS. l D 70579 9/16/87 09/17/87 LER SUBMIT LER 10 NRC CONCERNING RWCU ISOLATION.
[CG-87/0197 IR 87-9-5
)70620
\
Attachment 3 FORECAST (NEXT 90 DAYS) l i
4
- -"----" - - - - ' ""--""--"""----'--"--''----------------------------------s-dl
.. . _ E . - "--
. MP&L NUCLEAR LICENSING & SAFETY FORECAST MF&L LICENSING ACTIVITIES PAGE: 1 PATE: 10/21/87 ACTION TRACKING MANAGEMENT SYSTEM SCHEDULED DATE NRC REQUES1 DATE MP&L ID NUM RESPONSE MP&L C0FRES. NUM TOPIC 0F SUBMITTAL DESCRIPTI0h NEEDED TAC NUMBER SUBMIT TO NRC TECH SPEC CNANGE REGARDING 3.0.4 ONE-TIME 10/21/87 YES // TECHSPECS 2D70642 X EXCEPTIONS 09/15/87 ATWS SUBMIT AECM WITN RESPONSES TO NRC ATWS RAI 10/22/87 YES ID 70586 PMI-67/5278
// TECHSPECS SUBMIT 10 NRC TECH SPEC CHANGE TO REQUEST TO REMOVE SPECIF 10/22/87 YES ID 70643 X SLCS RELIEF VALVE SEIP0lNT 10/23/87 YES 10/16/87 SIMS SUIMIT ADDITIONAL SIMS ITEMS 10 NRC.
ID 70635 PJR 10/23/87 YES // TECH SPECS SUBMI110 NRC TECH SPEC CHANGE REGARDING RWCU VALVE POWER ID70644 X SUPPLY 10/30/87 YES // FUEL SUBMIT MATERIAL STATUS REPORT ON $NM DEPLETED U & NATURAL ID61339 NLSAF 2.4 U TO DOE.
10/30/07 YES 09/30/87 INSPECTIONFEES SUfMIT INSPECTION FEES IN PAYMENT OF INVOICE ID 70610 MAEC-87/233 10/30/87 YES 10/01/87 10 CFR 171 PAYMENT SUBMIT 10CFR171 FISCAL YEAR 88 PAYMENI VIA ELECTRONIC FUNL ID70611 MAEC-87/234 TRANSFER.
l 10/30/87 YES 10/01/87 LER SUBMIT LER TO NRC CONCERNING RADIATION SURVEYS EXCEEDING 1 1970623 IR87-10-2 REQUIRED 24 NR FRE0VENCY.
11/01/87 YES 07/01/87 NEUTRON MONITORING NOTIFY NRC 0F SIGNIFICANT CHANGES IN IWROG SCHEDULE FOR N" ID 70605 AECM-87/0018 LICENSING TOPICAL REPORT.
11/04/87 YES 10/05/87 LER SUBMIT LER TO NRC CONCERNING SURVEILLANCE REQUIREMENT ON ID 70524 IR87-10-4 DRYWELL STRUCTURE NAY NOT HAVE BEEN COMPLETELY PERFORMED.
FCP REQUEST FOR ADDi'l INFO SUBMIT RESPONSE TO REQUEST,FOR ADDITIONAL INFORMATION ON 11/12/87 YES 10/07/87 ID 70615 MAEC-87/0249 PCP WET SOLID WASTE CONTRACTOR l
MP&L NUCLEAR LICENSING t SAFETY FORECAST MP&L LICENSING ACTIVITIES PAGE: 2 I DAlt: 10/21/87 ACTION TRACRING MANAGEMENT SYSTEM l:::::::::::::::: :::::::: :::::::::::::::: :::::::::::::::::::::::::::::: ::::::::::::::::::::::::::::::::::::::::::::::::::::::::::-
SCHEDULEDDATE NRC REQUEST DATE MP&L ID NUM RESP ^NSE MP&L CORRES. NUM TOPIC 0F SU6MITTAL DESCRIPTION i
NEEDED TAC NUMBER 11/13/07 YES // MAPPGAS/ PROPOSAL SUEMii FOLLOWUP SPECIAL REPORT RE: REPORIAf!Ll1Y l DETERMINAi!ONOFMAPPGAS/PROPANESTORAGEISSUE.
ID7D491 X 11/15/87 YES 04/23/87 U2 CF EXTENSION SU6MIT INf0RMAil0N RE U2 EQUIPMENT PRESERVATION AND OUAll!
ID 70299 AECM-87/2-002 ASSURANCE PER COMMITMENT.
11/25/87 YES // 50.59 REPORTING SU6M!i NOVEM6ER 50.59
SUMMARY
REPORT TO MRC.
ID 70506 10CfR50.59 11/30/87 YES 08/04/86 NYDROGEN CONTROL PREPARE AND SU6M1100AFTERLY STATUS REPORT SEPTEM6ER 1987 ID 70380 LICENSE COND. ' DEGRADED CORE ACCIDENT NTDR0 GEN CONTROL PROGRAM
19 70607 10CFR50.71(e) 01/15/88 TES 06/24/B7 AS-lUIL1 DWG CERT SU6MIT REPORT 10 NRC DESCRIBING AS-BUIL1 DRAWING REVIEW ID 70425 Mil-87/0049 EFFORT AND PROVIDING CERTIFICATION THAT DRAWINGS ARE CONSISTENT WliH AS-tUlli PLANT.
1 m._ ____m________.____.____.___._.____.m_ _ _ _ _ . _ _ . _ _ , _ _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ . _ t . . _ _ _ _ . _ _ _ _ ..___..____m_._.______m.___.m._m
_ __m___ .m _ _ _ _ _ _ _ _ _
c' o Enclosure ~1 i I
l ATTENDEES i NRC SERI MEETING 10/15/87 NAME AFFILIATION i
l W. Koo NRR/ DEST /MTEB' j
~
I. Bukulmez NRR/ DEST /MTEB/ Assignee M. L. Crawfori SERI, Nuclear Licensing G. C. Sandlin SERI, Nuclear Licensing R. S. Lewis SERI, Nuclear Plant Eng. l 1
S. C. Mortenson General Electric - NEB 0 J. W. Self k neral Electric - NEB 0 R. A. Courtney SERISupv.(NDE)
M. Hum ,
NRR/MTEB l
lF.Litton NRR/MTEB 1 l W. Hazelton NRR/MTEB l
l L. Kintner NRR, Project Manager l
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- a. o Enclosure 2 I-NRC - SYSTEM ENERGY RESOURCES, INC.
REACTOR PRESSURE VESSEL VOLUMETRIC EXAMINATION LIMITATIONS MEETING
.Bethesda, October 15, 1987
- 1. INTRODUCTION '(Crawford)
II. DESCRIPTION of GGNS RPV (Sandlin)
III. CODE AND REGULATORY COMMITMENTS (Sandlin)
IV. CODE AND REGULATORY EXAMINATION REQUIREMENTS (Lewis)
V. EQUIPMENT USED IN EXAMINATIONS (Self/Mortenson)
VI.
EXAMINATION T'ECHNIQUES (Lewis)-
VII. TYPICAL INTERFERENCES ASSOCIATED WITH A BWR EXAMINATION (Lewis)
VIII. AUTOMATED SCANNERS AND THEIR INTERFACE WITH PLANT (Self/Mortenson)
SYSTEMS AND STRUCTURES IX. RELIEF REQUEST NO. I-00014 (Courtney/ Lewis)
X. RELIEF REQUEST.NO. I-00015 (Courtney/ Lewis)
XI. REVISION TO RELIEF REQUEST NO. I-00004 (Courtney/ Lewis)
XII.
SUMMARY
(Crawford)
J14 MISC 87101301 - 1
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1 II. DESCRIPTION of GGIS RW i
o B4R 6, !%RK III CONIAD@Efr 1
o 'IHE RW IS CONSTRUCTED OF (SEE FIGURE 1):
o 4 Shell Rings i o 'Ibp aM Bottm Head j o 'Ibp Flange ard Head Flarge o 35 Full Penetration Welded Nozzles o 4 Partial Penetration Welded Nozzles o 5 Shell Cironferential Seams o 14 Shell Vertical Seams ,
o 4 Bott e Head Seams l o 7 Top Head Seams o 32 Nozzle to Safe Erd Welds o 8 Safe EM to Safe End Dctension Welds o RW OUISIDE DIAMEIER IS 22' 2" o BIOI.OGICAL SHIEID MAIL INSIDE DIAMEIER IS 28' 8"(SEE FIGURE 1) o CIEARANCE BEIWEEN 'IHE RW AND SHTvrn WAIL IS 3' 3" o BIOIDGICAL SFTErn WAIL CDITIADIS PENETRATIONS WITH FDVEABI.E DOORS FOR Anrm 'IO RW ICZZIES AND PIPDIG.
o 'IHE BIOIDGICAL SHTTTn NAIL TERMINATES AT EI.EVATION 173' 3",
(SEE FIGURE 1).
o ACCESS 'IO 'IHE AICTUIUS AREA IS PROVIDED 'IHROUGH A MAtMAY AT ELEVATICH 124' 6", AND FRCH THE 'IOP OF THE SFTFrn HAIL.
o A PERSONNEL 1%N IIFT NAS DISTAT.Trn DURDIG RF01 'IO MINIMIZE STAY TIME Di 'IHE A101UIDS AREA.
o TDGORARY SCAFIDIDING AND IADDERS ARE UTILIZED WITHIN 'IHE Al@lUIUS
'IO ASSIST ACCESS.
nrepres page 3 2,
4 S l
III. CODE AND REWIATORY.CCMTIMENTS o 10 CER 50.55a(g)(4)(i) o BASE CDDE: ASME SECTICH XI 1977 EDITICN, THROUGH AND INCLUDING SGHER 1979 ADDENDA, WI'IH IATER EDITIONS AS SHOWN BEIN:
~
1980-WINTER 1980 ADDENDA, IWB-2500-1, EXAM CATEDORY B-F 1983-SGMER 1983 ADDENDA, IWB-2500-1, EXAM CATEGORY B-D (Relief Recpest I-00013) o REGULAIORY GUIEE 1.150, REVISICH 1, "ULTRASCNIC TESTING OF REACIOR VESSEL WELDS DURING PRESERVICE AND INSERVICE INSPECITCN" i
(Provides additional gnielal4nes on inspection of RP7 w.lds, UT)' 'f o NUREG 0619, REVISION 1, "BWR FEEDWATER NOZZLE AND CONIROL ROD ERIVE REIURN IJNE !OZZIE CRACKENG" (Provides additional gnicialines en inspection of FW nozzle inner radius, CRD return line is capped on unit I)
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nrepres page 4 y
_- _ ____ - a
IV. 000E AND REGUIA'IORY EXAMDIATION REQUIREMENTS o REGUIA'ICRY GUIDE 1.150, REVISIN 1,- REQUIRES:
o- RW'S :to be periMb11y examined by volumetric techniques in a haxi with Section XI of the ASME Code, which is ir - wrated by reference.
o Section 3.0 of the RBG. Guide provides referarce to ASME XI, IWA 2000, for scope -and extent of the ultrasonic examinations.
o ASME SECTION XI o IWA-2000, provides general requit w.bs and examination inethods.
o IWA-2200, requires the examination methods in table IWX-2500-1 to be used as specified.
o IWA-2400, provides two schedules for choice, pregcuu A or B, GGNS utilizes pr%5cun "B".
o IWB-2412, " INSPECTION PROGRAM B", requires examinations to be ocmpleted in accordance with IWB-2412-1 (see figure 2),
exc yL for those examinations that may be deferred until the end on an interval.
o Table IWB 2500-1 identifies welds arrl saw=rLs by grouping them into examination categories, and further divides them by item no.
nrepres page 5 g
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J IV. 00CE AND REGUI.AIGT DOMDUTION Fewar23NIS - 'I (ocntinued) o . Table IWB 2500-1 identifies 3 examination categories a-lated with volumatric examinations of a BWR RW:
- 1) B-A, Pressure retaining welds in r=ar+ra vamaals
- 2) B-D, Full p.r Lation welds of nozzles in vessels
- 3) B-F, Pressure retaining dissimilar metal welds o Examinaticri Category B-A (see figure 3) o Shell welds, cirannferential and longitudinal o Head welds, circumferential and meridional o Shell to flange welds o Head to flange welds o Deferral of certain "B-A" welds until the end of the ten year interval is possible, (see figure 3) . .
o Examination Category B-D, p. y am B,-(see figure 4) o Nozzle to vessel welds ~
o Nozzle inner radius (NUREG 0619)~
o Due to examination techniques of a BWR, deferral is not allowed (see figure 4 notes) o Examination Category B-F, (see figure 5) l o Nozzle to safe end welds i
o Deferral is not allowed (see figure 5)
I o IMA-2232, requires class.1- and 2 vaaaal welds in ferritic nat'l greater than 2 in. in thickness to be examined in 2 accordance with Article 4 of ASME, Section 5.
s I
i i) nrepres page 6 5 :
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1 1
V. EDUIIMENT USED IN EXAMD&TIONS )
o AUITATED RW INSPECTION SYSTD15 i
o Blue Box (General Electric) i o Ultra Image, Smart UT System (General Electric)
I o Blue Box Renote Inservice System o Portable system utilizing vessel and nozzle scanners.
o h basic scanner assembly package consists of a lucite block containing the ultrasonic tranMans. Channels are provided allowing water to flow urder the tranaAner package to serve as an air tight m' plant (see figure j 6).
o h scanning vehicle is attached to the vessel-wall by four sets of individually mounted magnetic wheels.
'Ibese wheels can be rotated to various positions on the RW (see figure 7)..
o Because the scanning vehic'le is operated behind the shield wall, various gnManoe systems are used to j control the direction of the scanners movement. Among i these are; an acoustic triangulation system, distance l and direction encoCau.= and TV monitors, l o 'Ihe nozzle scanner is assembled on a portable track that attaches to the nozzle. 'Ihe vehicle utilizes magnetic wheels and rotates arourd the nozzle (see figure 8).
o To examine the required volume, the scanner is ,
manipulated across the vessel areas to the extent possible. i t
l o Ultra Image (see figure 9) l o 'Ihe Ultra Image has been utilized to examine the nozzle 1
i to safe end and safe end to safe end extension welds. i o Scanner accambly attaches to safe end or pipe by a track accambly (see figure 10).
o Scanning is acocanplished similar to nozzle device A & ccaA above.
r nrepres page 7 ;
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V. EQUIPMDrr USED IN EXAMINATIONS (contimed) o TRANSDUCE lRS FCR BON MANtRL AND ALTKt9TED SYSTEMS o trarwham are used to direct the ultrasardc sound'into the .
examination volurre. '
o Typical L.custar characteristics are:
o Naninal frequency of 2.25 Mhz o 02mnon angles are 0, 45 and 60 %A es o Tran=t a m are mus-ted to the instrument through a Series of mavIml cables.
o Liquid couplants are utilized between the trarwhar arxi the scannirxy surface for maintaining an air tight contact.
o Typical sizes of a trarwhar are shown in figure 11.
. +
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nrepres page 8 '1 ;
4 8 i
l VI. EXAMINATION TECHNICUES l
o ASME SECTION V, ARIICIE 4 o 'Ihe volume of weld ard base mat'l to be examined shall be as requimd by the referencing code section (ASME, SEC. XI, IWB-2500-1, see figures 12 throogh 18) o Two argle beams. having nminal angles of 45' and 60' with respect to a perpendicular to the examLm tion surface, shall be generally used.
o REG. Guide 1.150 also states that at least one beam angle should be perpendicular ( 15') to the weld / parent material interface (see figure 19).
o Scanning of the examination volume shall be carried out from 1
both sides of the weld on the same surface (see figure 20) i o the examination volume shall be scanned with angle beam search units directed both at-right argles to the weld axis
( Mx:an) and alorg the weld axis (P-scan), each examination shall be performed in two directions.
I o T-scan, Ultrasonic beams must pass through all the weld metal. 'Ihe adjacent base metal in the examination volume must be completely scanned by two argle beams, but need not be completely scanned by both angles fr a both directions l (see figure 21) . .
I o Nx:an, Search units shall be ad2ned parallel to the axis of the weld. The ultrasonic beam must pass through all of the examination volume from two directions at 180' to each other (see figure 22).
l o O' or straight beam examinations shall be perforned on the entire volume of weld metal and adjacent base material to the extent required by the referencing code section.
I nrepres page 9
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VII. TYPICAL INTERFERENCES ASSOCIATED WI'Hf A BWR EXAMINATION o AI2100GH EE PTJNDAMENIAL IESIGN OF 'IHE MARK III CENIAINMENT ELIMINATED WE INTERFERENCE POSED BY WE BIOIOGICAL SKIEID WALL IN PROXDETY 'IO EE RPV, INHERENT INTERFERENCES IXJE 'IO RW DESIGN INHIBITS FULL UI2RASONIC EXAMINATION (no Relief Request have been generated as a result of shield wall interferences).
o RW DESIGN INTERFERENCES INCIDIE WE FDLIDWING:
o Radiused areas which interrupt Ls+ tar interface with the scanning area. 'Ihis interruption causes a separation between the tra W m r and the vessel surface air ti@lt contact.(see figure 23).
o Inherent obstructions that prevent placing the L-s +t a r at required positions to obtain the m aary "W" dimensions for examining the full examination volume (see figure 24). ]
l i:
o REGUIA'ICRY GUIDE 1.150 . INDICATES 'IHAT WHEN EE REQUIRED VOIDMES ,
HAVE NOT BEEN EXAMINED FOR ' DIE REASONS LISTED BEIDW, 'IHE LICENSEE i IS REQUDtED 'IO APPIX FOR REIZEF IN ACCDRDANCE WITH 50.55a of- 10 CFR.
o Near-field or other surface effects i o volumes near interfaces between cladding and parent metal: -J o volumes shadowed by laminar material defects !
o Volumes shadowed by part geuw hy: ;
o Volumes inaccessible to the L c++ m e '
o Volumes affected by elwLudc gating '
o volumes near the surface opposite the km+ tar - .!
I J
r nrepres page 10 i
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1 1
1 VIII. AUIO1ATED SCANNERS AfD THEIR INTERFACE '
WI'III PI. ANT SYSTDIS AND mmCIVRES ;
. j o BASED ON 'IHE USE OF THE RDME 'IRACKLESS SCANNER IOR VESSEL hT1DS AND ' DIE N0ZZLE SCANNER, AIONG WITH 'IIIE IMPROVED ACCESS OF 'IIIE MARK III CONTAINhETT DESIGN, THE VESSEL WELDS HAVE . ADEQUATE ACCESS FOR OPTIhD.!. '
EXAMINATIONS. (SEE FIGURE 25)
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inspection Calendar Years of Examinations Examinations -
Interval Plant Service Completed, % Credited, %
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- "T-Scan" Transducer Package FIGURE 6
^ SHEET 2 0F 3
'~ l} ,
t i
DtTtEMAL SUff%RY WEID SEAM ut2rryAL ATTNED i
nozzle to shell '
N1A, N1B, N2A, No N2B,' N2C, N2D, NO N2E, N2F, N2G, No N2H, N2J, N2K, No N2M, N2N, N3A, No N3B, N3C, N3D, NO N4A, N4B, N4C, No N4D, N4E, N4F, NO NSA, N5B, N6A, No N6B, N6C, N7, N8, NO N9A, N9B, N10, NO N16 NO I shell welds:
DA, DB, DC, DD, YES AD, BB, BC, BA, YES W, B7, BK, M, YES W, BP, BR, YES
N1A, N1B, N2A NO
'IERU N2N, N4A No
'1ERU N4F, NSA, NO NSB, N6A, N6B, NO 1 l N9A, N9B, NO l
nrepres page 11 ,
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LONGITUDINAL RANSDUCER MATER l'
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( CIRCUMFERENTIAL WELD
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FIG. IWB 2500-1 VESSEL SHELL CIRCUMFERENTIAL WELD JOINTS FIGURE 12' O'
4
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CL A00 LNG i
7ECTION I
W77 FIG. IWB-2500-4 SHELL-TO-FLANGE WELD JOINT l l S78 l W78 ,
l FIGURE 15 i l
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th. IW8 2500-5 Si!CTION XI - DIVISION I l - 's B
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m t
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a )
r, sheit for head) thickness rj
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A-B-C-0-E-F-G-H i
I EXAMINATION REGION l Note (til EXAMIN A TION VOLUME INote (2))
Shell(or head) ad;oining region
- C-D E-F Attachment weld region B-C-F G -
Norrie cylinder region A-0 G.H Nozzle ensede corner region M N-O P l
NOTES: l (il Examination regions are identified for the purpose of diff erentiating the acceptance standards in IW84512.
(2) Examination volumes may be determined either by direct measurements on the component or by measurements based on design drawings.
FIG. IWB-2500-7(b) N0ZZLE IN SHELL OR HEAD (Examination Zones in Flange Type Nozzles Joined by Full Penetration Butt Welds)
FIOURE 17 l i
o --
REQUIREMENTS FOR CLASS I COMPONENTS Fig. IWB.25004
, SURF. EX AM. AREA A-B i PROFILE OF VALVE BODY, '
\(io. VESSEL NOZZLE, OR g , in.g , ,
7 p in. [ PUMP CONNECTION
/-
A,s ,s 0 i l J de I INNER SURFACE NOM. PIPE . SIZE LESS THAN 4 IN.
1
, SURF. EXAM. AREA
^
A-B PROFILE OF VALVE BODY,
';' 4 VESSEL NOZZLE, OR
<- l .-+ -
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NOM. PIPE SIZE 4 IN. AND GREATER S79 FIG. IWB-25004 SIMILAR AND DISSIMILAR METAL WELOS IN PIPING FIGURE 18
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. Enclosure 3
' GRAND GULF NudLEAR STATON D1 SERVICE DISNQ4 N7TS INSERVICE INSPECTION SECTION 4 g3/g g ",E TEN YEAR PROGRAM RFT M REQUEST 1 GPRID GULF NUCIEAR SIATIGi UNIT 1 RFT M REQUEST NO. I-00015 PAGE 1 of 3 INSERVICE INSPECTION OF REACIOR PRESSURE VESSEL i WEIDS I. Cuuporent: Reactor pressure vessel (RW) wuponents, welds and associated base material identified in table 1 of this relief request.
II. Code: 'Ibe unit i reactor pressure vessel was designed and fabricated to ASME Section III, class 1 requirements. Applicable inservice inspections are to be performed in accordance with Regulatory Guide 1.150 Revision 1 and ASME Section XI,1977 Edition with Adderda through and including Summer 1979. Also, Relief Request No. I-00013 pennits the use of ASME Section XI, 1983 Edition with the Summer 1983 Adderda, Figure IWB-2500-7(b) for identifyirs the Code required examination volume.
III. Code Requirements: Table IWB 2500-1, Deamination Category B-D, B-A and B-F, requires specified volumes to be exarined volumetrically at specified periods during the ten year interval. Included in this volume is varying degrees of base material adjacent to each weld that also requires examination.
IV. Information to Tale to gecmtric configurations of the CGIS Unit 1 support the reactor, certain code IW examination detennination that volunes, as depicted in ASME Section XI, cannot be the code examined to the extent of obtaining full code
. require:mnts are coverage. Table 1 provides a listire of the impractical: affected c.mpts ard reactor pressure vessel I welds with a detailed description of the cause and degree of the limitation.
Relief Request Number I-00014 provides engineering rational addressing the limitations associated -
with the nozzle to vessel welds. 'Ibe Mc'rsions provided prior operating plant experience to justify that no further e.xarinations were r-my ard additionally this was justified by recognizing that the feed rater nozzles are the limiting case. Although 100% of the code volumes were not examined for the nozzle to vessel velds, sufficient examination coverage was obtained to detect any potential cracPirg.
'I l
GRAND GULF NUCLEAR STATION INSNC INSPECTIGi NE INSERVICE INSPECTION SECTION 4
$3/ g ",$ TEN YEAR PROGRAM pnm RDQUEST GPAND GUIE NUCIEAR S'IATION .
UNIT 1 FN M RDQUEST NO. I-00015 PAGE 2 of 3 IV. Information to A study of the velds listed in table 1 has support the shown that these weld locations are also determination that bounded by the feedwater nozzle rHe_":sions.
the code 'Ihe stresses due to any expected loadings and requirements are conditions at these locations are bounded by impractical: those at the feedwater nozzle locations.
(continued) Supporting the c.vimpt of the bounding is the fact that no indications have been found at any of the partially examined locations. In addition, it should be noted that a partial examination of each weld was obtained khich included either all or a portion of the reacter pressure vessel inner surface. -
V. Specific relief Pemission is requested to perform ultrasonic requested: examinations within the limitations described in table 1 of this relief request.
VI. Reasons sty relief Relief as described within should be granted should be granted: for the follcuing reasons:
- 1. 'Ihe entire reactor pressure vessel was subjected to an ASME Section III hydrostatic test after fabrication.
- 2. 'Ibe entire reactor pressure vessel will be subjected to system leakage test at each refuelirrg outage and a system hydrostatic test each inspection interval in accordance with the requirements of ASME Section XI.
- 3. 'Ibe subject selds were volumetrically examined in acrordance with ASME Section III during fabrication.
h;
o .
I GRAND GULF NUCLEAR STATOrd g g gg 7pg g g; gg l O INSERVICE INSPECTION SECTION 4 !
jj7 g "/d TEN YEAR PROGRAM Pn m RD;7 JEST l
GRAND GUIT NUCIEAR STATIGi UNIT 1 FDM RD20EST NO. I-00015 PAGE 3 of 3 V1. Reasons khy relief 4. Eere is no history of service induced should be granted: flaws in these areas of the reactor pressure vessel *other than those of the '
feedwater nozzles M s W in Relief Request Number I-00014.
l l S. We areas of the reactor pressure vessel l beirq examined are the limitirg areas.
- 6. We potential for initiation arri propagation of crackiry has been die lscM assuming both fatigud and stress corrosion crackiJg rechanisms. It was concluded by the use of limitiIn analyses results performed for the feedwater nozzle blend radii, that cracking is unlikely at G1and Gulf nozzle / vessel-weld locations. In fact, even if it was hypothesized that these postulated cracks went undetected, a cr.ack leryth of 58 inches was reqaired before rapid crack grcuth were to occur during normal operation. It is unlikely that cracks of this size would go undetected. Eerefore, a nigrdficant leak before break margin exists.
VII. Alternate testirg: None t _ __- -.
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GRAND GULF NUCLEAR STATON INSERVICE INSPECTION DISNCE DISPEGON Nm SECTION 4
$3[d%jNc. TEN YEAR PROGRAM prT m REQUEST GRAND GULF NUCIEAR STATION UNIT 1 ,
FFTM REQUEST NO. I-00015 N1 -
RECIRCULATION OUITEr NOZZIE 'IO SAFE DID WELD 12MITATIONS f.-
FLOW = N 45'SW NOZZLE i SAFE.END INCONEL I BUTTER NI -
Total code volume at a cross sectional view is .95 in2 o Automated techniqaes utilizing a 45' shear wave obtains two directional coverage of an area equal to .17 in2, o Also, a 45' and 60' refracted longitudinal (RL) wave is utilized that obtains one directional coverage of the entire code volume scanning from the nozzle side.
o 'Ihe cross hatched area . received the one directional coverage from the nozzle side, the reraining area was examined from two directions utilizing the shear wave.
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o Manual examinations will provide two directional coverage of the weld and nozzle base material, the available "W" dimension on the safe end side of the weld is insufficient to obtain full coverage of the efe end raterial. -
FIGimE 14
GRAND GULF _ NUCLEA3 STATON g INSERVICE INSPECTION SECTION 4-g"gg"," TEN YEAR PROGRAM RMM RD20EST GRAND GUIT NUCEAR STATION UNIT 1
- RET M REQUEST No. I-00015 N2 ,
RECIRCITIATICH INET N0ZZLE 'IO SAFE IND WEID IJMITATIONS f
1 FLOW r-SAFE END NOZZLE INCONEL BUTTER f INCONEL BUTTER -
60*RL /
745'RL a
Total ocde volume at a cross sectional view is .846 in2.
~
o Automated techniques utilized a 45* and 60* RL wave for the examination of the N2F and N2H to obtain complete code volume coverage frun one direction with both angles, f o '!he re:naining N2 nozzles (A,B,C,D,E,G,J,K,M,N) were examined .
cmpletely fran one direction with only the 60* due to excessive noise received with the 45' tranchani; -l 1'
o Manual examinations can provide two directional coverage of the area represented by the y hatching, this would improfe total-code coverage to .271 in -or 32% for the 60* and .642 in or-75.6% for the 45*.
o If _ the presently available 45* transducers are improved to reduce noise levels, future examinations' will include the 45' for improved coverage.
FIGURE 15 .
GRAND GULF NUCLdAR STATCN INSERVICE INSPECTION SECTION 4 g8'gj7",$. TEN YEAR PROGRAM prr m REQUEsr GRAND GUIE NUCLEAR STATION UNrr 1 RELIEF REQUEST NO. I-00015 N4 '.
FEED h7CER INIET NOZZLE 'IO SAFE DO WELD LIMITATIONS SAFE END NOZZLE !
FLOW -
INCONEL BUTTER INCONEL BUTTE $ '
'60* R L /45'RL 1
1 Total code voltrae at a cross sectional view is .70 in2 o Automated technigdes utilizirg a 45' and 60' RL wave obtained ccreerage of the code volume frun one direction only (safe erd side),
o ions for Manual the areaexaminations will provide identified above coverage by the cross fran .36 hatchire, two i%nor 51.4%
of the total ccde volume. {
FIGURE 16
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GRAR$D GULF NUCLEAR STATON gg g gg INSERVICE INSPECTION SECTION 4 sesvru turo"' TEN YEAR PROGRAM RELD:F RDRUEST sesouncts, suc.
GPAND GUIE NUCIIAR STATION UNIT 1 RELIEF REQUEST NO. I-00015 N5 !
CDRE SPRAY 'IO SAFE END WEID 12MITATIONS
/
I l SAFE END N0ZZLE FLOW ___ INCO.NEL BUTTER 60'RL 45'RL Total code volume at a cross sectional view is .72 IN2 l
Autanated techniques provides a 45' shear wave from the safe end side o two directional coverage of an area equal to
.33 in or 46.6% of the total code volume.
Also, a 45' ard 60* RL wave examination from the safe end side is performed obtainirg one directional coverage of the total code volume. Area receiving examination from one direction only is 53.4%
of the ccde volume.
7 Manual examinations with RL wave will increase two directional N coverage by 18%.
FIGURE 17 g
, o G8tAND GULF NUCLEAQ STATON ,
INSERVICE INSPECTION SECrION 4 jg/g""Q ,
TEN YEAR PROGRAM prr m REQUEsr GRAND GUIE NUCLEAR STATION UNIT 1 RFrm RD20EST NO. I-00015 N6 .
RESIDUAL HEAT RDOVAL / IDW PRESSURE ' CORE DUECrION SAFE D1D 'IO NOZZIE WELD I2MrIATIONS SAFE-END NOZZLE FLOW > _
INCONEL BUTTER I
- 60* RL / 45" R L
'Ibtal code volume at a cross sectional view is .93 in2 'I, 1
Autanated technigaes provides a 45* shear wave examination from the safo end side obtaining two directional coverage of .34 in 2 or 36.6% of the total code volume.
Also, 45' and 60' RL wave examinations performed from the safe end j side obtains one directional cxwerage of the total code volume; l area receiving one directional coverage only is 63.4% OR .59 D;2 '
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Manual ptions will incmase two directional oeverage'by 9.7%
or .09 in .
I EIGURE 18 hf. -
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GRAND GULF NUCLEAR STATON p g g pg g g g INSERVICE INSPECTION SECTION 4 jgrg y "$ TEN YEAR PROGRAM prr m REgges7 GRAND GUIF IUCITAR SIATION UNIT 1 PFT M RD20EST NO. I-00015 N9 -
JET RMP DETRUMDTIATION ICZZIE 'IO ' SAFE DO WELD N
FLOW : --
NOZZLE SAFE-END INCONEL BUTTER [~
\ 45'RL Total code volume at a cross sectional view is .29 in2 j Autmated techniques provides a 45' shear wave examination from the safe end side ob2aining two directional coverage of .10 in2 or 34.5% of the total code volume.
Also, 45' ard 60' RL vave examinations performed from the safe end L side obtains one direc'.onal coverage of the total codg volume; area receiving one directional coverage only is .19 in or 65.5% 1 of the total code volume.
"ainations will increase two directional coverage by 27.5%
FIGURE 19
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. r GRAND GULF NUCLEAR STATON INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 gj'gj7',$. TEN YEAR PROGRAM RELIEF REQUESTS REVISION 2
- PAGE PAGE 1 of 6 GRAND GULF NUCLEAR STATION UNIT 1 REQUEST FOR RELIEF NO. I-00004 INSERVICE INSPECTION RPV LOWER HEAD-TO-SHELL WELD A-A I. Component: The lower one-half of Unit I reactor nressure vessel lower head-to-shell weld A-A.
II. Code: The Unit I reactor pressure vessel was designed and fabri-cated to ASME Section III, Class 1 requirements. Applicable inservice inspections are to be performed in accordance with the ASME Section XI, 1977 Edition with addenda through and including Summer 1979 Addenda.
III. Code requirements: The upper portion of this weld is a circumferential shell weld and is required to be volumetrically examined for essentially 100% of the weld length once during the first 10-year inservice inspection interval, in accordance with ASME Section XI, Table IWB-2500-1, Category B-A, Item Bl .11.
The lower portion of this weld is a circumferential head weld and is thus required to be volumetrically examined for essentially 100% of the veld length, once every 10-year in-service inspection interval, in accordance with ASME Section XI, Table IVB-2500-1, Category B-A, Item Bl.21.
IV. Information to The A-A weld joins the lowest ring of circumferential shell support the deter- plates on the reactor pressure vessel (RPV) to the RPV bottom mination that the head and is located 80.66 inches above vessel zero. The code requirement bottom of the' core is located at 216.31. inches above vessel is impractical: zero. The weld is approximately 135.65 inches below the bottom of the core. 'In addition, the weld is approximate 1v 91.2 inches below the centerlines of the recirculation pump suction nozzles (N1 nozzles) and approximately 98.4 inches below the centerlines of the recirculation pump discharge nozzle (jet pump suction nozzles-N2).
The upper portion of the A-A weld is a typical circumferential shell weld. Automated ultrasonic examination procedure and equipment have been developed which will permit the required inservice volumetric inspections to be performed remotely.
The lower portion of the A-A weld is a circumferential head weld. Due to the curved geometry of this portion of the veld, automated means for ultrasonic examination of this portion of the weld have not been developed; thus, this portion of the veld must be ultrasonically examined by manual procedure, e
32)
NVPMSP ISI I-00004-
GRAND GULF NUCLEst ETATON INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4 RELIEF REQUESTG REVISION 2 8ffi"j$ TEN YEAR PROGRAM PAGE PAGE 2 of 6 l l
GRAND GULF NUCLEAR STATION UNIT 1 REQUEST TOR RELIEF NO. I-00004 (Continued)
INSERVICE INSPECTION RPV LOVER HEAD-TO-SHELL VELD A-A IV. Information to The containment design of Grand Gulf Nuclear Station Unit I-support the deter- is designated Mark III. A feature of this design is that an mination that the annulus space of approximately 30 inches width exists between code requirement the reactor vessel outer circumference and the biological is impractical: shield wall inner circumference. The examiners must enter (continued) this annulus space to perform manual ultrasonic examination of the A-A weld. Contact radiation levels on, and area radiation levels near, the recirculation inlet and outlet nozzles, recorded at other BWR plants during the first three to six years of reactor operation have been in the range of 200 mR/hr to 2000 mR/hr. We anticipate the area radiation levels at the A-A weld to be approximately the same as those near the nozzles due to their proximity to each other, the constricted space in annulus, the proximity to the core, which is treated as an area source, and possible reflection from the metallic insulation on the inner surface of the biological shield wall. For purposes of estimating exposure, we have assumed an area radiation level at the A-A weld of 800 mR/hr at the end of the first 40 month inservice inspec-tion period. The level is expected to increase as the plant ages.
Due to the large amount of veld area required to be examined and the nature of the radiation sources in the area, shielding is not practical. Such shielding "ould need to shield the entire body, would be heavy and dif ficult to move and would require significant exposure to erect and move.
Based on the results of the examinations performed during the preservice inspecti'ons, it is estimated that 16 man-hours will be required to perform the required manual ultrasonic examinations. This time does not include the time required for personnel to enter and exit the annulus space; however, it does include an allowance for the extra time required by personnel due to wearing protective clothing and for mapping three recordable, but not reportable indications, which were found during preservice inspections.
We estimate that the manual ultrasonic examination of the A-A weld will require approximately 12,800 millirem of personnel exposure. Entry and exit of the annulus region plus support personnel exposure during the examinations is estimated to require an additional 1,700 milliree for a total estimated exposure of 14,500 millirem. (,
NWP,MSP ISI I-00004
GRAND GULF NUCLEAR STATOR INSERVICE INSFECTION RFOUIREMENTS
. INSERVICE INSPECTION SECTION 4 l "8/gjf/J. TEN YEAR PROGRAM RELIEF REQUESTS REVISION 2 j pAGE GRAND GULF NUCLEAR STATION PAGE 3 of 6 UNIT 1 REQUEST FOR RELIEF No. I-00004 (Continued)
INSERVICE INSPECTION RPV LOWER HEAD-TO-SHELL WELD A-A V. Specific relief Permission is requested to' delete all ultrasonic' inservice requested: inspections of the lower one-half (Category B-A, Item Bl.21 requirement) of.the entire circumference of the A-A weld, except as noted under alternate examinations.
VI. Reasons why relief Relief from.the ultrasonic inservice inspections of the A-A should be granted: veld is requested for the following reasons.
- 1. The upper one-half (Category B-A, Item Bl.11) of the A-A weld var examined by remote ultrasonics as a preservice inspection in accordance with ASME Section XI and no re-cordable indications were found.
- 2. The lower one-half (Category B-A, Item Bl.21) of the A-A veld was examined by manual ultrasonics as a preservice
- inspection in accordance with ASME Section XI and a total of three recordable, but not reportable, indications were
" found. The examination report shows that the indications are outside the heat affected zone of the veld.
- 3. The entire reactor pressure vessel was subjected to a hydrostatic pressure test in accordance with ASKE Section III, 4 The upper one-half of the A-A vel / will be examined by remote ultrasonics during the first inservice inspection interval in accordance with the requirements of ASME Section XI. -
- 5. The entire reactor pressure vessel will be subjected to a system leakage test at each refueling outage and to a system hydrostatic test each inservice inspection interval in accordance with the requirements of ASME Section XI.
VII. Alternate Testing: Instead of examining the entire lower one-half of the A-A weld, we propose to perform manual ultrasonic examinations' only of the section of the weld in which the'three recordable indications were found (approximately a 12 inch by 12 inch surface are , once,ggy inservice inspec_ tion interval.f The manual examinaftons vi1TTe"Yerf ormed to
/"Ehe extent possible in consideration with the discussed' limitations. With the vessel support skirt being located 6 inches below the A-A seam, the maximum obtainable "V" 1
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NKPMSP 151 1-00004
1 . T GRAND GULF NUCLEAR STATOiB INSERVICE INSPECTION REQUIREMENTS -
INSERVICE INSPECTION SECTION 4' 8l8'i"j,"$$ TEN YEAR PROGRAM RELIEF REQUESTS REVISION 2 PAGE GPJLA'D GULF NUCLEAR STATION PAGE 4 of 6 UNIT 1 REQUEST FOR RELIEF NO. 1 60004 (Continued)
INSERVICE INSPECTION RPV LOWER HEAD-TO-SHELL WELD A-A VII. Alternate Testing: dimension is also 6 inches, this prevents both the 60' (Continued) and 45' T-Scans from examining the total veld volume (see figure 2). The three recordable indications were
> recorded in the base material of__the head __ utilizing th O' se n. Te vill monitor the size of the indications and, any of the indications appears to be increasing in size, we vill evaluate the indications and take appropriate actions, which may include ultrasonic examinations of other sections of the veld. The anticipated exporure for performing the alternative examination would be less than 500 nillirem.
NVPMSP ISI I-00004 .
i, . a GRAND GULF NUCLEAR ETATON INSERVICE INSPECTION REQUIREMENTS O
srstru twaar INSERVICE INSPECTION SECTION 4 I RESovects, INC. TEN YEAR PROGRAM RELIEF REQUESTS REVISION 2 )
PAGE l 1
GRAND GULF NUCLEAR STATION PAGE 4A of 6 t' NIT 1 REQUEST FOR RELIEF NO. I-00nO4 (Continued)
INSERVICE INSPECTION RPV lok'ER HEAD-TO-SHELL WELD A-A VIII. NRC Discussion The follovfug statements, conclusions, recommendations, Statements etc. have been adopted ~by the NRC and are to be considered part of this request-for-relief',s approval:
Since a 12" by 12" patch of the A-A veld can be examined with manual volumetric methods without excessive radiation exposure and since monitoring an additional 12" by 12" patch where no flaws had occurred prior to PSI would give a measure of the condition of the remainder of the veld, we recommend that an additional 12" by 12" patch of the A-A veld be volumetrically examined. The second or reference patch should be at 1 east 90* from the patch containing the flaws.
Therefore, relief is recommended as requested provided:
(a) The upper portion of the A-A veld is volumetrically examined over'100" of the veld length, (b) The manual volumetric examinations, over a 12" by 12" area, of the reportable defects and a reference patch in the lover nortion of *.he A-A veld are performed and evaluated, and (c) the Code-required symtem premaure tests are performed.
The requested relief has been recommended based on the impracticality of conducting manual ultrasonic examinations in radiation fields estimated to exist in the examinations area. If actual radiation fields are lower, for example if the core were removed, more extensive examinations should be conducted.
It is further recommended that improvements in automated ultrasonic inspection technology be monitored and that the entire length of the lower portion of the A-A veld be examined if techniques become available during the 10-year interval, i
b n t%b t Abi 1 -ij v u v - !
4 GRAND GULF NUCLEAR STATION INSERVICE INSPECTION REQUIREMENTS INSERVICE INSPECTION SECTION 4
$8/g/j",E TEN YEAR PROGRAM RELIEF FEOUESTS REVISION 2 PAGE PAGE 5 Or 6 GRAND GULF UNIT ONE BOTTOM HEAD TO RING es 1
- 7. 6" SHELL RING # 1 C ' # U U'"U u
y RING 881 10 y4 =e l'
o o
~ ' BOTTOM HEAD
}
_ l i W :D Percentage of Code Required Volume (CRV) that vill be examined being planned volumetric methods for Seam AA:
Upper Portion: 100% UT by remote ultrasonics.
Lover Portion: 1.43% UT by Manual ultrasonics due to perservice of three
. (3) Recordable Indications.
Y hVPMSP ISI l-00004 O
, , n GRA%D GULF NUCLEAR STATod D D ON SMg INSERVICE INSPECTION SECTION 4 gj'g/jf'," TEN YEAR PRCGRAM N REQUEST PAGE 6 OF 6 4
9 WELO A A l
8 60 l
45
/
SHELL RING #1 f. l Nk i
i BOTTOM HEAD l '
)
I i
l l WELD AA SCANNING LIMITATIONS FROM BOTTOM
^
HEAD SIDE FIGURE 2 1
1 0
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