ML20077M174
| ML20077M174 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 08/30/1983 |
| From: | Daltroff S PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| REF-SSINS-6820 IEB-83-02, IEB-83-2, NUDOCS 8309120248 | |
| Download: ML20077M174 (10) | |
Text
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6 PHILADELPHIA ELECTRIC COMPANY 2301 M ARKET STREET P.O. BOX S699 PHILADELPHIA PA.19101 SHIELDb L. D ALTROFF sta$rnic rn u"c son August 30, 1983 Docket No. 50-278 Dr. *homas E. Murley, Administrator Of fice of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19046
Subject:
Supplement II to Peach Bottom Unit 3 Response to I.E.
Bulletin No. 83-02
Reference:
1)
Letter to Dr. T.
E. Murley from S. L. Daltroff, dated August 9, 1983 (Response to I.
E.
Bulletin 83-02) 2)
Letter to D. G. Eisenhut (NRC) from S. L. Daltroff, dated October 1, 1981 (Response to Generic Letter 81-04, Peach Bottom Program for Mitigation of IGSCC Based on Guidelines of NUREG-0313, Revision 1) 3)
Letter to G. Lear (NRC) from J.
L. Hankins (PECo), dated December 20, 1977 (Peach Bottom Program For Mitigation of IGSCC Based on Guidelines of NUREG-0313, Revision 0)
Dear Dr. Murley:
As a result of a recent telephone conversation with Peach Bottom's NRR Project Manager, additional information was requested concerning Philadelphia ElEttric Company's response to I. E.Bulletin 83-02 for Unit 3 (Reference 1 above).
This letter will restate the additional information requested and provide our responses.
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Dr. Thomas E. Murley Page 2 Request 1:
Attachment A of your Auguat 9, 1983, submittal on I. E.
Bulletin 83-02 indicated that 37 welds in the recirculation and RHR systems had not undergone ultrasonic (UT) examinations.
Some of the unexamined welds were classified as
" conforming" welds; however, a specific number of these unexamined welds were not accompanied by information providing clarifications and/or justifications for these welds not being inspected.
Please provide the NRC staff with additional information concerning these uninspected, non-conforming welds including technical justification for not conducting inspection on these welds.
If high radiation or pipe size are to be used as a basis for justification, please provide suitable details of these bases for staff evaluation (refer to your october 1, 1981, submittal).
Response 1:
There were 17 Class I non-conforming welds in the recirculation and residual heat removal (RHR) system which were not volumetrically examined during the current Unit 3 outage.
These welds were not required by 1. E.Bulletin 83-02 to be examined since no crack indications were found during examinations of similar welds in other-areas of Unit 3.
In addition, these welds were also located in high radiation fields (at the time the decision was made, fields were as much as 8 to 10 R/ hour on contact).
Ten of these seventeen welds were located in areas requiring removal of large quantities of insulation.
The radiation associated with the total examination program (i.e., scaffolding, insulation, shielding, examination, etc.) was too high to justify the examination.
Five of the seventeen welds were small diameter I
weldolet to pipe w21ds which are not volumetrically examinable and which are not required to be examined by Bulletin 83-02.
Two of the seventeen welds were penetration to valve welds, which are unexaminable, due to physical constraints.
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Dr. Thomas E. Murley Page 3 The seventeen welds and their location are as follows:
Weld No.
Location Remarks 2-AS-9 Recirc.
"A" Loop Not examined Valve to Pipe due to high radiation 2-AD-12 Recirc.
"A" Loop Pump to Pipe 2-AD-13 Recirc.
"A" Loop Pipe to Valve 2-AD-16 Recirc.
"B" Loop Pipe to Tee 2-BS-8 Recirc.
"B" Loop Valve to Pipe 2-BD-ll Recirc."B" Loop Pump to Pipe 2-BD-12 Recirc.
"B" Loop Pipe to Valve 1
2-BM-3 Recirc "B" Loop Manifold to Valve 2-BM-2 Recirc.
"B" Loop Valve to Manifold 2-BD-16 Recirc."B" Loop Cross to Tee 2-AD-12/
Recirc.
"A" Loop Not volumetrically BPA Pipe to 4" examinable Weldolet 2-AD-15/
BPA 10-0-1/
RHR Suction 12-0 Pipe to 6" Weldolet 2-BD-ll/
Recirc.
"B" Loop BPB Pipe to 4" Weldolet
Dr. Thomas E. Murley Page 4 2-BD-14/
Recirc.
"B" Loop Not volumetrically BPB Pipe to 4" Weldolet examinable 10-IA-2 "A" RHR Return Isolatable Penetration to Valve weld; cannot be UT examined due to physical restriction.
10-IB-2 "B" RHR Return Penetration to Valve Moisture detection monitors have been installed on 30 selected welds on Unit 3 during its present refueling outage.
There were three criteria used to select welds for moisture detector installation:
First, all 15 welds that had been repaired during this outage (10-0-5, 10-0-6, 10-0-7, 10-0-10, 10-0-15, 2-AHK-2, 2-AHJ-2, 2-AHH-2, 2-AHG-2, 2-AHF-2,2-BHE-2, 2-BHD-2, 2-BHC-2, 2-BHB-2, 2-BHA-2) ; Second, the five weldolet welds that are uninspectable (2-AD-12/BPA, 2-AD-15/BPA, 10-0-1/12-0, 2-BD-ll/BPB, and 2-BD-14/BPB); Third, the ten welds in high radiation areas that were not examined (2-AS-9, 2-AD-12, 2-AD-13, 2-AD-16, 2-BS-8, 2-BD-ll, 2-BD-12, 2-BD-16, 2-BM-2 and 2-BM-3).
For location of these welds, see Attachment 1.
Request 2:
In your October 1, 1981, submittal pertaining to Generic Letter 81-04, you indicated that certain portions of the Unit 2 and 3 Core Spray and Unit 3 Reactor Water Clean-up Systems have undergone material replacement to mitigate intergranular stress corrosion cracking (IGSCC).
Would you please provide an updated summary of these systems pertaining to material replacement (from 304 to 316L Stainless Steel).
For those ASME Class I portions of these systems which have not undergone material replacement, please provide information on all welds (location and size) which have not been recently inspected in these systems.
Please provide any technical justifications for not conducting I. E.Bulletin 83-02 inspections on these welds.
Response 2:
In March of 1982, the 6" Type 304 Stainless Steel Piping in the Peach Bottom Unit 3 Reactor Water Clean-up (RWCU) System was replaced with ASME SA 312 Type 316L Stainless Steel from containment penetration N-14 up to, but not including, the 6" weldolet on the 20" RHR
4 Dr.-Thomas E. Murley Page 5 shutdown cooling suction line.
This modification aff ected welds 12-0-20 to 12-0-37 as shown on Attachment 2.
There are 3 welds, 12-0-17R, 12-0-18R, and 12-0-37, still remaining in the Class I portion of the Reactor Water Clean-Up Systems which are still non-conforming.
Welds 12-0-17R and 12-0-18R were not examined during the present Unit 3 outage because they cannot be UT-examined due to physical constraints.
Weld 12-0-37 is in an isolatable section of the piping and is not required to be examined by I. E.Bulletin 83-02.
Moisture detection monitors will be installed on these 3 welds before returning the unit to power operation.
During September, 1981, the 304 Stainless Steel portions of the 10" and 12" Core Spray Piping (Loops A & B) on Unit 3 were replaced with ASME SA 358 Type 316L material from the Reactor Pressure Vessel Safe Ends up to Valves 14 A & B.
The welds aff ected by this modification are shown as 14-A-43 to 14-A-28 on Attachment 3 and 14-B-42 to 14-B-28 on Attachment 4.
The portion of the A & B Loop Core Spray Piping between welds 14-A-12 and 14-A-02 on Attachment 3, and between welds 14-B-ll and 14-B-2 on Attachment i
4, remain non-conforming Type 304 Stainless Steel.
These welds were not examined during the present Unit 3 outage because this portion of the piping operated at a temperature less than 200 degrees F and, therefore, is not considered susceptible to IGSCC.
If you have any questions, please do not hesitate to contact us.
Very truly yours, e
cc: A. R. Blough, Site Inspector NRC Document Control Desk J. F. Stolz (NRC)
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