ML20210C411
| ML20210C411 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 08/08/1986 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RTR-NUREG-CR-3053 IEB-80-08, IEB-80-8, SL-865, NUDOCS 8702090383 | |
| Download: ML20210C411 (10) | |
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(3 on b-ib 6 6 Mailing Address:
Fbst Office Box 4545 Atlanta, Georgia 30302 06 MG N diU Georgia Power t.t aue.,
tre sourten eurre sniem Manager Nuclear Safety SL-865 and ucensing 2775N August 8,1986 U. S. Nuclear Regulatory Commission
REFERENCE:
Office of Inspection and Enforcement RII: JNG d.
Region II - Suite 2900 90:?2f/50-366 V 101 Marietta Street, NW gd&E4eMetty Atlanta, Georgia 30323
- T-087NRC~*^*
NUREG/CR-3053 ATTENTION: Dr. J. Nelson Grace Gentlemen:
The following information is being provided by Georgia Power Company (GPC) in response to NRC NUREG/CR-3053, "Closecut of IE Bulletin 80-08:
Examination of Containment Liner Fenetration Welds."
Although not required by regulatory requirements, GPC is submitting the enclosed information in order to assist in the closeout of NRC I&E Bulletin 80-08, " Examination of Containment Liner Penetration Welds," issued on April 7, 1980, for Plant Hatch Units 1 and 2.
NUREG/CR-3053 did not require any response from licensees, since it was not issued by the NRC through an implementation letter.
NRC I&E Bulletin 80-08 was issued as the result of primary containment liner penetration weld defects found during an NRC inspection at another licensee's facility and subsequent followup investigations at other licensees' facilities for similar weld defects.
The purpose of the bulletin was to acquire information from all facilities to determine the generic impact of the primary containment liner penetration weld defect problem.
GPC provided information ' for Plant Hatch Units 1 and 2 relative to the bulletin by letters dated July 7,1980; August 5,1980; November 3,1980; August 10, 1981; and November 18, 1983.
The NRC issued NUREG/CR-3053 in July 1984.
The NUREG was prepared by an l
NRC contractor, Parameter, Inc., and was based upon the collection of l
information acquired from the NRC Headquarters' files regarding facility responses to the bulletin and inspection reports.
It was stated in the NUREG that no solicitation was made for additional information from the NRC Regional Offices.
The purpose of the NUREG was to determine the closecut status of the bulletin for all facilities, to identify any remaining areas of ' concern, and to present proposals for further action to complete the closeout of the bulletin.
Recommendations contained in the NUREG offer a general plan to assist facilities in resolving any remaining areas of concern for those facilities not having a closed-bulletin status.
The Hatch units were noted in NUREG/CR-3053 as having an open status relative to l
bulletin closecut.
The NUREG indicated that additional justification would be required in order to close out the bulletin for Plant Hatch.
t 50 1
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-._RMMme(t D (1%W
en GeorgiaPower d U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II - Suite 2900 August 8,1986 Page Two Georgia Power Company and its. consultants have re-evaluated the GPC bulletin responses relative to the recommendations in NUREG/CR-3053 for closeout of the bulletin.
Enclosed herein as Enclosures 1 and 2 are the revised penetration tables for Hatch Units 1 and 2, respectively.
All known penetrations at Plant Hatch having a flued head and/or bellows assembly are listed.
No other high-energy lines that do not follow this penetration design except for 1-inch or smaller instrument or sample lines are known to exist.
In this case, the lines utilize instrument penetrations as shown in Figures 5.2-5 and 3.8-7 in the Final Safety Analysis Reports for Plant _ Hatch Units 1 and 2, respectively. The information provided in Enclosures 1 and 2 is intended to supplement information provided in our submittals of November 3, 1980; August 10, 1981; and November 18, 1983.
Also, in certain cases, 3
information is provided in the enclosures which modifies information i
provided in our November 3,
1980, submittal and is specifically noted.
i elsewhere in this submittal. -
Re-evaluation of the November 3,
- 1980, submittal indicated that some information could not be fully substantiated, since the response originator, who was employed by one of our consultants, is deceased. _ Accordingly, the penetration tables have been carefully re-evaluated and modified, as necessary.
To - the best of our knowledge, the information contained therein is accurate.
The enclosed information, alon with the aforementioned three submittals (as modified by this submittal)g, should enable the NRC to close out NRC I&E Bulletin 80-08 for Hatch Units 1 and 2.
It is our belief that by this submittal we have adequately' responded to each of the remaining areas of concern identified in the NUREG.
The penetrations having a flued head and/or bellows assembly are all high-energy lines except the Hatch Unit 1 service water lines.
High-energy lines are defined by NUREG/CR-3053 as systems having a maximum operating temperature exceeding 2000F and/or a maximum operating pressure exceeding 275 psig.
Several items in the enclosed tables require the following clarifications:
1.
For weld quality, we were only able to determine, based upon available information, whether the weldability of the base material and filler material is compatible and whether the welding requirements assigned (preheat and interpass temperature) are in compliance with applicable specification requirements.
Paragraph 1.3 of NUREG/CR-3053 suggests taking credit for weld efficiency factors to justify not performing radiography.
It should be noted that weld joint efficiency factors are not used in ANSI B31.7 or ASME Section III design.
2775N 700775
GeorgiaPower A U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II_- Suite 2900 August 8, 1986 Page Three 2.
Where weld material information (e.g., vendor-supplied, information not available) for determining weld quality, as discussed in item 1 above, was not available, radiography may have been performed by the vendor.
Weld quality was deemed to be acceptable where-radiography was performed by the vendor and was accepted.
3.
The enclosed tables contain several changes from the previous information provided to the NRC -in our submittal of November 3, 1980.
a.
' Penetration 36 (Hatch Unit 2) is not listed, because it is a spare with the bellows assembly never installed, b.
Penetration 17 (Hatch Unit 1) penetration sleeve material is SA-333, GR1.
c.
Penetration 14 (Hatch Unit 1) process pipe material is SA-312, T304L.
d.
Penetrations 13A and 138 (Hatch Unit 1) did not have RT or UT performed on the bellows assembly-to-penetration sleeve.
e.
Penetrations 20 and 44 (Hatch Unit 1) and Penetration 41 (Hatch Unit 2) are added.
f.
Penetrations 8, 10, and 17 (Hatch Unit 2) penetration sleeve material is SA-333, GR6.
g.
Penetrations 10 and 14 (Hatch Unit ?) did not have RT performed on the bellows assembly-to-penetration sleeve.
l 4.
Penetrations 20 and 44 for the Hatch Unit 1 service water lines have incomplete weld review, because the flued head material is not identified on any available documents, and the field stamp identifies a material that does not exist.
Al so,
no weld information is available for the flued head-to-penetration sleeve wel d.
It is likely that the weld information exists; however, we have been unable to locate it.
GPC will pursue the field data through the vendor.
If the field data should prove to be unavailable, GPC will perform nondestructive examinations (e.g., PT and/or UT) of the containment penetration assemblier, for these non-high-energy lines, where feasible, during the next scheduled 2775N 700775
4 O
O
'd v
GeorgiaPower d U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II - Suite 2900-August 8,1986 Page Four refueling outage.
Such examination (s) would entail the nondestructive examination of the pipe-to-penetration (flued head) weld outside containment and the accessible weld (s) of the flued head penetration assembly (e.g.,
bellows assembly-to-flued head, bellows assembly-to-containment sleeve) to verify containment penetration assembly integrity.
5.
Where weld quality cannot be determined, based upon either item 1 or 2 above, for certain components (e.g.,
process pipe-to-flued head) of Hatch Unit 1 penetrations 7A through D, 20, 42, and 44 and Hatch Unit 2 penetrations 7A through D, 41, and 42, GPC will perform nondestructive examinations (e.g., PT and/or UT) of the containment penetration assemblies, where feasible.
The examinations will be performed during the next scheduled refueling outage, as discussed in item 4 above, to verify containment penetration assembly integrity.
Should the NRC require any additional information in this regard, please contact this office at any time.
Sincerely, e$r@.
L. T. Gucwa JAE/mb Enclosures c(w):
Georgia Power Company Mr. J. P. O'Reilly Mr. J. T. Beckham, Jr.
Mr. H. C. Nix, Jr.
GO-NORMS U. S. Nuclear Regulatory Commission Director, Division of Reactor Construction Inspection Director, Office of Inspection and Enforcement Director, Office of Nuclear Reactor Regulation Senior Resident Inspector l
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ENCLOSURE 1 ( Continu2d )
PEhE1 RATIONS Niid SELLONS ASSEMBLIES AND/OR FLUE 0 HEA25 - MAICH UNii i SHEET 2 0F 3 IPENEil PROCESS PIPE 10 FLUED NEAD tlNTERNALI I
GUARD PIPE 10 FLUED MEAD 4
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INELDINELS IEIANINAil0N!8ACKI NELD i 8ASE I NELD INELDINELO BEXANIMATIONIIACKl NELD I SASE I NELD I i
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ENCLOSURE 2 ( Continu:d )
PENEIRATIon5 utiN SELLONS A55EnsLIES AN8/04 FLUE 0 NE A85 - NATCH UNIT 2
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e ENCLOSURE 2 ( Continued )
PERETR AI!ONS utfN.ELLout 455En8 LIE 5 AND/04 FLUED MEADS - MATCH UN!i 2 EMEET 3 SF 3 h0TES til PEhEIRAll04 TVPE AS BEFlhES IN MNP-2-FSAR-3.8.
(23 RT PERFOAMED CLRinS CUIA6E PER 6PC LETTER OF 8-80-08 FA0n J. T. SECEMAn. JR. TO h2C REGION 88.
436 h0 SELLOWS A55En8LY, FLUE 8 hEAS WELSED TO ELEEvt.
(48 BV SUPPLIER, thFORMAI!ON NOT AVAILASLE.
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t6n MELD Con 5IDERED ACCEPTABLE BASE 0 ON THE RE50LIS OF int RT.
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