ML20078N164
| ML20078N164 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 09/15/1983 |
| From: | Kemper J 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 8310250419 | |
| Download: ML20078N164 (5) | |
Text
4 PHILADELPHIA ELECTRIC COMPANY 23O1 MARKET STREET P.O. BOX 8699 PHILADELPHIA, PA.19101 September 15, 1983 JOHN S. KEMPER Docket No. 50-277 VIC E #R ESID E NT ENGINEE RtNG AND RESE ARCH Dr. Thomas E. Murley, Administrator Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19046
SUBJECT:
Peach Bottom Unit 2 Response to I.E. Bulletin No. 83-02
Dear Dr. Murley:
I.E. Bulletin No. 83-02, concerning " Stress Corrosion Cracking in Large-Diameter Stainless Steel Recirculation System Piping at BWR Plants", dated March 4, 1983, required actions be taken by Philadelphia Electric Company, and that a report on these actions be submitted to the NRC before returning Unit 2 to service.
We have not completed all work on Unit 2.
- However, our schedule indicates that we will be able to return the unit to service by October 3, 1983.
In an effort to aid the NRC Technical Staff in the review of our response to this bulletin prior to the scheduled restart date, we are submitting a partial response now to provide as much lead time as possible.
Table 1 identifies all welds involving 304 stainless steel piping, of greater than or equal to 4 inches in diameter, that have not been ultrasonically examined during this outage on the following systemss a.
Reactor Recirculation System.
b.
ASME Code Class 1 portion of the Residual Heat Removal System.
c.
ASME Code Class 1 portion of the Core Spray System external to the Reactor Vessel.
d.
ASME Code Class 1 portion of the Reactor Water Cleanup System.
0310250419 7
l I
. ~ -
- 61 b
Dr.' Thomas.E.-Murley-Page 2 The " remarks" column of Table 1 indicates the basis for not performing an examination of the particular weld.
-There are two additional welds which have not yet been inspected.. These are the Reactor Water Cleanup System pipe to penetration weld (12-0-17), and the. pipe to outboard isolation valve weld (12-0-18), both of which are.outside of containment.
These welds are located in an area with contact readings as high f as.15 R/hr.
. Ultrasonic examination of the welds or installation of the moisture detection equipment will be evaluated based on the total man-rem exposure necessary.to perform the respective tasks.
d Moisture detection monitors are being installed on the five -non-isolatable IGSCC susceptible welds which could not be inspected during this outage.
These are welds 2-AD-12/BPA, 2-AD-15/BPA, 2-BD-ll/BPB and 2-BD-14/BPB in the Reactor Recirculation System and weld 10-0-1/12-0 in the Residual Heat Removal System.
~
As agreed' to on Unit 3, the moisture detection system will be operated as. stated in Attachment III to the May 23, 1983 letter f rom S.L. Daltroff to D.G. Eisenhut.
As we have discussed with your staff,' we do not intend to put any. reliance on the
.Drywell Radiation-Monitoring System for the detection of small
-primary system leakage.
Additionally,- we. propose to report moisture detection system problems-and alarms unrelated to actual leakage on a 30-day basis.
l If you have any questions, please do not hesitate to i-contact us.
Very truly yours,
i
(-
3 MBR:lm
- Attachments cc A.R. Blough, Site Inspector J.F. Stolz, NRC NRC Document Control Desk l
a 4-TABLE l-Unit-2 ~ Piping Welds Not Inspected During Summer 1983 Outage Weld No.
Location Remarks p
t 2-AS-1 Recirc "A" Loop.
Conforming - <.025 Carbon Nozzle to Safe-end
'2-AHF-5
- Recirc "A" Loop Conforming - <.025 Carbon Saf e-end ' to - nozzle 2-AHG-5
~ Reci rc ' " A" Loop Conforming - <.025 Carbon
. Safe-end to nozzle 2-AHH-5 Recirc "A" Loop Conforming - <.025 Carbon Saf e-end to nozzle L2-AHJ-5 Recire "A". Loop Conforming - <.025 Carbon Safe-end to nozzle 2-AHK-5 Recirc "A" Loop Conforming - <.025 Carbon Safe-end to nozzle 2-BPA-1A Recirc "A" Loop Conf orming - Heat Sink Welding Bypass weldolet to cap 2-BPA-10A Recirc "A" Loop Conforming - Heat Sink Welding Bypass weldolet to cap 2-BS-1 Recirc "B" Loop Conforming - <.025 Carbon l
Nozzle to safe-end
~2-BHA-5 Recire "B" Loop Conforming - <.025 Carbon Safe-end to nozzle BHB-5 Recirc "B" Loop Conforming - <.025 Carbon Safe-end to nozzle 2-BHC-5 Recirc "B" Loop Conforming - <.025 Carbon Safe-end to nozzle 2-BHD-5 Recirc "B" Loop Conforming - <.025 Carbon Safe-end to nozzle 2-BHE-5 Recirc "B" Loop Conforming - <.025 Carbon Safe-end to nozzle 2-BPB-1A Recirc "B" Loop Conforming - Heat Sink Welding Bypass weldolet to cap
.2-BPB-10A Recirc "B" Loop Conforming - Heat Sink Welding Bypass weldolet to cap
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2-AD-12/BPA Pipe to 4" cap Not volumetrically examinable 2-AD-15/BPA Weldolet weld due to configuration 2-BD-ll/BPB Pipe to 4" cap Not volumetrically examinable 2-BD-14/BPB Weldolet weld due - to configuration P
10-0-1/12-0 2RWCU weldolet
~ Not volumetrically examinable i '
to RHR Pipe weld due to configuration 10-IA-2 RHR Inj.
"A" Loop Isolatable weld, outside valve to pipe containment. Cannot be examined due to physical constraints.
lO-IB-2 RHR Inj.
"B" Loop Isolatable weld, outside Valve to pipe containment. Cannot be examined due to physical constraints
, 0-17
.RHR Shutdown Cooling Not volumetrically Penetration to pipe examinable due to Configuration lO-HS-3 to
.IGUt - Head Spray Not susceptible to lO-HS-6 IGSCC Operates < 200 degrees F.
lO-HS-9 to RHR-Head Spray Not susceptible to lO-HS-18
~
IGSCC i.
Operates < 200 degrees F lO-HS-19 to RHR - Head spray Welds are inaccessible 10-HS-27R since reactor head was not
{
removed. Piping will be replaced with 316L S.S. next refueling outage.
12-0-20 to Reactor Water Conforming - 316L S.S.
12-0-33 Clean-Up 14-A-2 to Core Spray "A" Loop Not susceptible to IGSCC A-12 Operates < 200 degrees F.
14-A-28 to Core. Spray "A" Loop Conforming - 316L S.S.
14-A-43 14-B-2 to Core Spray "B" Loop Not susceptible to IGSCC 14-B-ll Operates < 200 degrees F.
'14-B-28 to Core Spray "B" Loop Conforming - 316L S.S.
14-B-41
]
t COMMONWEALTH OF PENNSYLVANIA :
ss.
COUNTY OF PHILADELPHIA J.
S. Kemper, being first duly sworn, deposes and says:
That he is Vice President of Philadelphia Electric Company, that he has read the foregoing partial response to I.E.
Bulletin No. 83-02 f or Peach Bottom Unit 2 and knows the contents thereof; and that the statements and matters set forth therein are true and correct to the best of his knowledge, information and belief.
c24 S.1 - 4
/
Subscribed and sworn to
-11:
before me this l6 day 1
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Notary Publ'ic PATRICIA A. JG!.
Notary Pubi.e Fnita.. Fnaa. Co.
Ph Commission Expires Oct.13,1000