ML20054E684
| ML20054E684 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/04/1982 |
| From: | Beckham J GEORGIA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20054E683 | List: |
| References | |
| TAC-48328, NUDOCS 8206140065 | |
| Download: ML20054E684 (15) | |
Text
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. 3y3 P.eem 4 < < s Artes G(:m a 3NCs Te cW+ 4?4 FN 7020 Va ! g Ad?M' Pest otte Bn 4545 Ara~a Gem;a 303R June 4, 1982 GeorgiaPower
- #0 J. T. Beckham. Jr.
V!ce Pres.cen' a-d Gue'a' Mara;;e' Nciea' Gerera's U. S. Nuclear Regulatory Commission
REFERENCE:
Office of Inspection and Enforcement RII: JP0 Region II - Suite 3100 50-321 101 Marietta Street, tM Atlanta, Georgia 30303 ATTENTION: Mr. James P. O'Reilly GENTLEMEN:
Georgia Power Company (GPC) herein submits as Attachment 1 our plan for augmented inservice inspection (ISI) of certain componente to address our interest in Intergranular Stress Corrosion Cracking (IGSCC). Our concerns with IGSCC were heightened by the water chemistry transient and resultant chloride intmslon which occurred at Plant Hatch, Unit 1 on April 24, 1982.
Attachment 1 identifies the components to be examined as a result of this incident and discusses the ISI plan. Items 1 through 15 of Attachment 1 were presented to members of the PRC Region II staff for review in a meeting held at tRC Region II offices on May 25, 1982 to discuss the water chemistry transient and resulting chloride intrusion. The staff indicated that they wished to review in more detail our program in connection with the referenced NUREGs.
In a subsequent phone conversation held on May 28, 1982, concerning our l proposed augmented inservice inspection program, your staff indicated that I the stainless steel portions of the residual heat removal (RW) System (i.e., Class 1 R$ Injection and Suction piping) and the reactor water cleanup (RWCU) System (i.e., Class 1 RWCU Suction piping) should be examined as well. GPC personnel acknowledged that although the subject piping was not included in the program as presented, it was GPC's intention to examine the RWCU and RHR piping per NUREG-0313, Rev. I requirements. Attachment I has been revised to incorporate the subject RWCU and Rm piping and are identified as Items 16 through 18. GPC representatives indicated that although twelve (12) RWCU suction piping welds were examined during the 1981 maintenance / refueling outage that six (6) of those welds would be re-examined over the next two refueling outages.
It was also suggested by the PRC staff during the subject telephone conversation that the HPCI, RCIC, and RWCU connections to the Feedwater System should also be examined. GPC personnel indicated that the subject connections to Feedwater were carbon steel and not subject to examination because of the chloride intrusion.
8206140065 820607 PDR ADOCK 05000321 0 PDR
GeorgiaPower A U. S. tAJclear Regulatory Commission Office of Inspection and Enforcement Region II - Suite 3100 June 4, 1982 Page Two A concern was raised by the MC staff regarding possible low flow or stagnant conditions with piping runs containing pumps, valves, and/or fittings which could trap " residual" material thereby increasing the possibility of cracking. Those components which are judged to be susceptible to cracking are either high flow (e.g., Recirc System) or are examined at such a frequency (e.g., R m System Injection and Suction service-sensitive piping examined in accordance with NUREG-0313, Rev. 1) that such concerns should be alleviated. Other systems not presently judged susceptible to IGSCC and located in low flow areas where the potential for trapping " residual" material exists will be evaluated.
Attachment 1, as formally submitted by this letter, addresses the planned augmented inservice inspection for the 1982 maintenance / refueling outage. Attachment 2 summarizes the components, the examinations planned, and how the ISI program has been augmented.
GPC hereby advises WC that radiological conditions may impact the examinations proposed. If radiological conditions do not permit examination of a specific component, MC will be contacted and relief will be requested from examination of that component.
If you have any questions in this regard, please contact this office.
Sincerely yours, l
WW 7f n 7:L J. T. Beckham, Jr.
er 1 pJAE/mb Attachnents l
xc: H. C. Nix, Jr.
R. F. Rogers, III Director, Office of Nuclear Reactor Regulation
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ATTACH 4ENT 1 1
AUGMENTED INSERVICE INSPECTION RESULTING FROM WATER CEMISTRY TRANSIENT AT PLANT HATCH UNIT 1 i
titC 003ET 50-321 l
06/04/82 l
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I As a result of the water chemistry transient and resultant chloride intrusion ircident at Hatch Unit 1, the following components will be examined as discussed herein:
- 1. Control Blades A control blade (material type 304 stainless steel) has been removed for examination by neutron radiography. Any additional removal of control blade (s) for examination will be contingent upon the results of testing performed by E on the above mentioned control blade.
- 2. InstIbment Nozzles, Core Differential Pressure Nozzle, and Jet Pump Instrumentation Nozzles Ultrasonic examinations of the stainless steel (Type 304) safe end welds on the instrt.rnent nozzles and core differential pressure nozzle were originally considered; however, due to their size (2-1/2" and 2-5/8", respectively), ultrasonic examination is not practical. Pipe curvature, thin wall thickness, and ultrasonic beam deflection in the component examined would contribute to a poor examination and would cause the examination results to be extremely difficult to interpret. General Electric (GE) concurs and has recommended, in lieu of the ultrasonic examination of the subject nozzles, that they be flushed. In addition, they recommend that a visual examination be done during the upcoming 1982 maintenance / refueling outage.
Ultrasonic examination of the stainless steel (Type 304) safe end welds on the Jet Pung Instrumentation Nozzles has been recocrnended by GE. Since the Jet Pump Instrumentation Nozzle safe end welds have not been examined previously by Georgia Power Company (CPC),
an ultrasonic test calibration standard will have to be designed and fabricated. The necessary calibration standard will be designed and fabricated tentatively for use during the 1982 maintenance / refueling outage. It should be noted that for this particular ultrasonic examination, full coverage (i.e., 10%
examination coverege of the weld from the nozzle side od safe end sice) is not expected because of the safe end configuration.
tumerous jet pump instrumentation lines are connected to the safe en0 and will limit the amount of weld examined. Preliminary review indicates that the examination can only be perfomed from the nozzle side and examination coverage may be limited there also.
f included in the Long-Tem Inservice Although not currently Examination Plan for Hatch Unit 1, the subject examination will be added and performed in accordance with the reQJirements for nonconfoming, nonservice-sensitive stainless steel piping and components as discussed in NLREG-0313, Revision 1.
- 3. Shroud Support The shroud support, an Alloy 600 (inconel) cogonent, will be visually examined by CPC using remote underwater television viewing during the 1982 maintenance / refueling outage. In the event that there are not any rejectable indications, the examination frequency will continue with that currently used (i.e., next re @larly scheduled examirAtion at the end of Cycle 6, and subsequent refueling outages at approximately three yeer intervals thereafter) for examination of ASE Category B-N-1 components. The existing plant. procedure (s) for invessel inservice inspection will be reviewed and revised as necessary to incorporate this component into the invessel examinations.
- 4. Jet Pump Bea?.s The Alloy 600 (inconel) jet pump beams are currently inspected using ultrasonics each refueling outage in accordance wit. E Service Information Letter (SIL) 330. E proceduIt TP508.0642 (Revision A) is used for this ultrasonic examination.
- 5. Shroud The shroud, a Type 304 stainless steel cortponent, will be visually examined by GPC using remote underwater television viewing during the 1982 maintenance / refueling outage. In the event that there are not any rejectable indications, the examination fre w ency will continue with that currently used for examination of ASE Category B-N-1 components. The existing plant procedure (s) for invessel inservice inspection will be reviewed and revised as necessary to incorporate this component into the invessel examinations.
- 6. Recirc Inlet Pezzle Safe End Ultrasonic examination of the Type 304 stainless steel Recirc Inlet Nozzle safe end welds has _ been reconsnended by E and will be performed in accordance with tOREG-0313, Revision 1 rewirements.
The frecuency of inspection of these welds has been discussed previously with tRC-rER in our letter dated June 29, 1981 which stateo GPC's position concerning inplementation of tJPEG-0313, Revision 1. Welds for two (2) nozzle safe ends will be examined using inechanized ultrasonics during the 1982 maintenance / refueling outage.
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- 7. Recirc Inlet Thermal Sleeve Ultrasonic examination of the Recirc Inlet Nozzle themal sleeve attachment welds will be performed during the 1982 maintenance / refueling outage as ciscussed in our June 29, 1981 letter to MC-mR concerning NUREG-0313, Revision 1 iglementation. For only the 1982 outage,100E of the welds will be examined in lieu of the 50K as identified in the subject letter in order to establish a baseline. It is anticipated that E will perform these examinations using their procec1Jre TP508.0484, Revision B or equivalent procedure dependent upon pad weld meterial encountered. Future examinations of the thermal sleeve attachment welds will be in accordance with the frequency discussed in our June 29,1981 letter to E C-tER.
- 8. Recire Outlet Nozzle Safe End E has recomended that ultrasonic examination of the Type 304
- stainless steel ReciIt Outlet Nozzle safe end welds be examined.
One (1) of the safe ends will be examined using mechanized ultrasonics curing the 1982 maintenance / refueling outage. This and future examinations will be performed in accoIdance with t4 BEG-0313, Revision 1 require ents, and our June 29, 1981 letter to PEC-tER.
- 9. Steam Dryer Support Bracket The steam dryer smport bracket, a cast austenitic stainless steel (CF-M) component, will be visually examined by GPC using remote underwater television viewing during the 1982 maintenance / refueling outage. In the event that there are not any rejectable indications, the examination frequency will continue with that currently used for examintion of ASE Category B-N-1 components.
The existing plant preocedure(s) for invessel inservice inspection will be reviawed and revised as necessary to incorporate this component into the invessel examinations.
- 10. Core Spray Eracket Luc The core spray backet lug, a cast austenitic stainless steel (CF-H) component, will be visually examined by GPC using remote underwater television viewing. Plant procedures will be reviewed and revised to incoIporate the bracket lug examinations into the procedure for core spray sparger visual examination reQJirec each refueling outage by tEC I&E Bulletin 80-13.
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- 11. Stub Tube E's recommendation for examination of the stub tube is interpreted to mean that the Alloy 600 (inconel) nozzle cap on the unused 3" CRD Hydraulic System Return Line Nozzle. An ultrasonic examination of the subject weld (s) will be performed during the 1982 maintenance / refueling outage. Although inconel was not addressed in M. REG-0313, Revision 1, future examinations of the subject welds (s) will be performed in accordance with the requirements for r:onservice-sensitive materials as discussed in the subject NLREG.
- 12. CRD HSR Nozzle Ultrasonic examination of ,the CRD Hydraulic System Return line Nozzle safe end (Type 304 stainless steel) has been recommended by E. A records review and field verification are expected to indicate that the safe end has been removed and, therefore, no examination would be required.
In the event that the review indicates that the safe end still exists, GPC will examine the necessary welds during the 1982 maintenance / refueling outage. Examinations would be perfomed two more times at an interval of 36 months (plus or minus 12 months) coinciding with a refueling outage. If after the three examinations, no rejectable indications are observed, safe end weld examination will revert to an 80-month schedule as allowed by NLREG-0313, Rev.1 for nonconfoming, service-sensitive piping and components.
examined for evidence of leakage during the bolt-up pressure test.
l The examination would include the outer CRD housings. Due to poss'_cle accessibility difficulties with high radiation and themal conditions, GPC will perform the normal pressure test prior to start up of the unit and monitor the stops for any abnormal leakage.
- 14. Recire Pipinc System Type 334 stainless steel piping welds will be ultrasonically examined in accordance with NUREG-0313, Revision 1 reouirements as discussec in our letter dated June 29, 1981 to NRC-NRR regarding implementation of the subject MREG.
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Sixteen (16) welds consisting of twelve (12) nonservice-sensitive and four (4) service-sensitive welds as identified by PUREG-0313, Rev. I guidance and the existing inservice inspection program will be examined during the 1982 maintenance / refueling outage. Plant design agencies will be consulted to detemine which welds have the higher stress value and a sample examined accordingly. This and all future Recire piping weld examinations will be performed in accordance with PUREG-0313, Revision 1 and our letter dated JJne 29, 1981.
- 15. Feedwater Nozzle Blend Racius Ultrasonic examination of the SA508 carbon steel Feedwater Nozzle Blend Radius will be performed during the 1982 maintenance / refueling outage. It should be noted that this examination along with the safe end welds and center bore section examinations are due this upcoming refueling outage based on requirements of NUREG-0619. The stainless steel cladding was zumoved from the subject nozzles during the 1979
, maintenance / refueling outage. The subject NUREG requires that those plants having removed the cladding and having triple sleeve, double piston, feedwater spargers ultrasonically examine the safe ends, center bore section, and clend radius every second refueling outage. This and all future examinations will be performed in accordance with NUREG-0619 requirements.
- 16. RWCU Suction Piping Ultrasonic examination of the Type 304 austenitic stainless steel welds on the RWCU Suction Piping will be performed during the 1982 maintenance / refueling outage. Six (6) welds previously examined during the 1981 maintenance / refueling outage will be re-examined.
Those welds will be reexamined over the ' ext two refueling outages. Future examinations will be perfomed in accordance with NJREG-0313, Rev. 1 requirements for nonconforming, nonservice-sensitive piping and components and our letter dated June 29,1981.
- 17. R m Injection Piping Ultrasonic examination of the Type 304 austenitic stainless steel welcs on the R$ Injection Piping will be perfomed during the 1982 I maintenance / refueling outage. A total of six (6) welds .will be examined on the "A" and "B" R$ loops. This and all future RP Injection Piping weld examinations will be perfomed in accordance with NUREG-0313, Revision 1 requirements for nonconfoming, service-sensitive piping and components and our letter dated June 29, 1981.
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- 18. R$ Suction Piping Ultrasonic examination of the Type 304 austenitic stainless steel welds on the R$ Suction Piping will be perfomed during the 1982 maintenance / refueling outage. A total of five (5) welds will be examined. This and all future R $ Suction Piping weld examinations will be performed in accordance with f4JREG-0313, Rev. I requirements for nonconfoming, service-sensitive piping and components and our Nne 29, 1981 letter.-
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ATTACHENT 2 SIM4ARY OF AUG4ENTED INSERVICE INSPECTION FOR HATCH UNIT 1 1982 REFUELING OUTAGE 2 C DOCKET 50-321 06/04/82
Page 1 HATCH 1 1982 AU PENTED ISI ,
EXISTING ISI ITEM FROG. REQ. FOR 1982(1) AUGNENTED 1982 PfiOGRAM CD*4ENTS ,
- 1. Cnntrol Blade tb See comments. Any additional removal of control blade (s) for exami-nation will be contingent upon the results of testing performed by GE on the control blade referenced in
.the augmented inservice inspection program.
- 2. Instr. tbzzle S.E. tb Six (6) Instr. Nozzles (VT) Jet pump instrumentation Core Dif. Pres. thzzle S.E. No One (1) Core Def. Pms. Nozzle (VT) nozzle safe end weld exams J.P. Instr. Nozzle S.E. tb Two (2) J.P. Instr. Nozzles (UT) will have limitations.
Welds will be examined to the extent practical using ultrasonics. Future exams to be performed in accor-dance with MJREG-0313, Rev.
1 for nonservice sensitive components.
- 3. Shroud Support ib VT of shroud support by means lf no rejectable Indications of remote underwater TV viewing are observed, comonent will be reexamined at end of cycle 6 per existing ASME schedule. Unit presently nearing end of cycle 5.
- 4. Jet Pump Beams tb UT of twenty (20) jet pump Twenty (20) beams examined beams each refueling outage in accordance with GE SIL 330 recommendations.
- 5. Shrnod tb VT of shroud by means of remote If no rejectable indications underwater TV viewing are observed, component will be reexamined at end of cycle 6 per existing ASME schedule. Unit presently nearing end of cycle 5.
Page 2 HATCH 1 1982 AUGHENTED ISI (Continued) .
EXISTING ISI ITEM PROG. REQ. FOR 1982(I) AUCENTED 1982 PR001AM CDmENTS
- 6. Recire Inlet No UT examination of two (2) safe The two safe ends were Nozzle Safe End ends (1 each loop) examined previously (i.e.,
1977 refueling). Examina-tion to include 2 0-F and 4
- B-J category safe end welds.
- 7. Recirt inlet No UT of 100% of thermal sleeve Fifty percent (SOE) to be Nozzle Thermal attachment welds (i.e., 10 reexamined within 3 years 1 Sleeve welds to be examined). 12 months in accordance with PaJtEG-0313, Rev. I as previously commited by GPC.
- 8. Rectre Outlet No UT examination of one (1) All code req'd. exams com-Nozzle Safe End safe end pleted for this component.
Safe end to be examined Ut'd pmvlously during 1977 refueling. Examination to include 1 B-F and 2 0-J category safe end welds.
- 9. Steam Dryer No VT of steam dryer support If no rejectable indications Support Bracket dryer support bracket (s) are observed, component will by means of remote underwater be reexamined at end of TV viewing. cycle 6 per existing ASME l schedule. Unit presently nearing end of cycle 5.
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- 10. Core Spray No VT of core spray bracket lug (s) Core sprey sporgers Bracket Log by means of remote underwater examined every refueling TV viewing. outage in accordance with PRC I&E Bulletin 80-13.
Bracket lug (s) will be added to the required .
sparger examination.
Page 7 Q HATCH 1 1982 ALGENTED ISI (Continued)
EXISTING ISI ITEM PROG. REQ. FOR 1982(1) AUGENTED 1982 PR0mAM QM4ENTS
- 11. Stub Tute No UT of GD HSR nozzle Future cap-to-nozzle weld stub tube (nozzle cap) exam. To be performed in accordance with NUREG-0313 Rev. I for nonservice-sensi-
- tive piping and components.
- 12. CR0 HSR thrzle No See Comments. Records review and field verification expected to indicate safe end has been Irmoved and, themfore, no examination will be required. If review Indicates safe end still present, safe end welds will be examined using ultrasonics. The subject welds would then be reexamined within 3 years 1 12 months in accordance with MJREG-0313, Rev.1 for service-sensitive pipiry and conponents.
- 13. CRD Housing No Perform normal system Possible accessibility dif-pressure test prior to ficulties with high radia-startup of unit after tion and thermal conditions mfueling and monitor sumps may preclude visual examina-for abnormal leakage. tir during bolt-up presure test of outer CRD housing as recc ;.ided by E.
Page'4 HATCH i 1982 AUGMENTED ISI (Continued) ,
l EXISTIts ISI CDNENTS PROG. REO. FOR 1982(1) AUGMENTED 1982 PROGIAM ITEM
category welds and deemed service-sensitive welds are those ASME cate-PT of 5 B-K-1 per NUREG-0313, Rev. 1 gory 8-J piping welds for category welds (total , terminal ends (i.e. , pipe-12 welds) to-safe end welds) which will be examined under Item 6 (RC Inlet nozzle safe end) and Item 8 (RC outlet nozzle safe end). Future recirc piping examinations to be performed in accordance with f4JREG-0313, Rev. 1 for nonservice-sen-sitive, and service sensitive piping and comonents, as appropriate.
l No UT of 4 feedwater nozzles blend All feedwater nozzles
- 15. Feedwater Nozzle examined in accordance with Blend Radius radius NUREG-0619. Nozzle center bore section and safe ends also to be examined duriry l')82 refueling outage to
! meet subject NUREG i
' requirements.
l Yes, UT of 1 B-J UT of 4 B-J category welds Three (3) of the 4 addi-
- 16. CWCU Suction tional welds to be examined l Piping category weld were examined previously during the 1981 refueling.
The additional welds will be chosen in accordance with PAREG-0313, Rev. 1, Item IV.B.1.b.(2).
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Page i IMTCH 1 1982 AUGMENTED ISI (Continued)
EXISTING ISI FHOG. REQ. FOR 1982(1) AUCPENTED 1982 PROPAM COMENTS .
ITEM Three (3) additional welds examined during the 1981 refueling will be re-examined at the end of
. cycle 6 (tentatively 1984).
No UT of 2 B-F category welds The PUEG-required subject
- 17. Rift Injr ction Pipirw] and 4 B-J category welds deemed service-sensitive welds will service-sensitive per NWEG- be reexamined within 3 years 0313, Rev. 1. (total 6 welds + 12 months in accordance on "A" and "B" loops of Rm with NUEG-0313, Rev. I re-per NUREG guidance). quirements.
UT of 1 B-F category welds The PUEG-rewired subject
- 18. RFil Suction No service-sensitive welds will Piping and 4 B-J category welds deemed service-sensitive per NUREG- be reexamined within 3 years 0313, Rev.1 (total 5 welds + 12 months in accordance per NUREG guidance). with NUREG-0313, Rev. I re-quirements.
(1)From Hatch Unit 1 Long-Term Inservice Examination Plans transmitted to WC Region II by Georgia Power Company letter dated August 29, 1980.
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