ML17199G612

Forwards Request for Addl Info Based on Review of 870302 & 23 Results of Augmented Piping Insp Program.Info Requested within 60 Days of Ltr Receipt

ML17199G612
Person / Time
Site:	Dresden
Issue date:	05/27/1987
From:	Muller D Office of Nuclear Reactor Regulation
To:	Farrar D COMMONWEALTH EDISON CO.
References
NUDOCS 8706030058
Download: ML17199G612 (3)

Text

Dockets Nos. 50-237/249 Mr. Dennis L. Farrar Director of Nuclear Licensing Commonwealth Edison Company Post Office 767 Chicago, Illinois 60690

Dear Mr. Farrar:

May 27,"1987

SUBJECT:

INSERVICE INSPECTION INFORMATION - FA.LL 1986 IGSCC INSPECTION Re:

Dresden Nuclear Power Station, Unit No. 2.

By letter dated March 4. and *23,.1987, you trans~i~ted'.the** results of the Dresden Unit 2 84-11 augmented.pipfog inspecti6n program.

By letter dated March 27, 1987 we indicated that our *preliminary review.-demonstrated that the information complied w-ith;the NRC accepted inspection plan, and that our detailed Safety Evaluation would be* issued when our r~view was completed.

We have completed our revi£7W and.find.that we need the infof'.mation identified in the enc.losed Request for'Additional Jnformation. *Please provide the infor-mation requested within 60 days of the. receipt. bf th.js letter, or provide a schedule to your. Dresden Project Manager;-. *

Enclosure:

As stated cc w/enclosure:'

See next page DISTRIBUTION

'.~Docket File >>

GHolahan CYCheng ACRS (10)

NRC PDR SNorris OGG-Bethesda

• PDIII-2 Plant OFFICIAL RECORD COPY PDIII-2:PMW MGrotehnuisO 5/1*-V/87 E~(_,

~ih~j Sincerely, Original si'gned by Byron Siegel/

Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects Local PDR.

MGrot~nhuis EJordan File PDIII-<<kv DMul~f'f'*

sir; /87 PDIII-2 Reading File DMuller JPartlow

Mr. Dennis L. Farrar Commonwealth Edison Company c~:

Mr. Michael I. Miller Isham, Lincoln & Beale Three First National Plaza.

Suite 5200 Chicago, Illinois 60602 Mr. J. E~nigenburg

.Plant Superintendent

• Dresden N~clear Power Station Rura 1 Route #1.

Morris, Illinois 6045Q U. S. Nuclear* Regulatory Commission

• Resident Inspectors Office Dresden Station Rural Route #1 Morris; Illinois 60450 Chairman

• Board of Supervisors of *

. Grundy. County

. Grundy County Courthouse

- Morris, Illinois 60450 Regional Administrator Nuclear Regulatory 'Commission, Region 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Michael E. Parker, Chief -

Division of Engineering.

Illinois Department of Nuclear Safety 1035 Outer Park Drive~ 5th Floor Springfield~ Illinois 62704 Dresden Nuclear Power Station Units 2 and 3

INSERVICE INSPECTION INFORMATION FALL 1986 INS.PECTION FOR DRESDEN, UNIT 2 REQUEST FOR ADDITIONAL INFORMATION

1.

Please provide the stress information and UT measured pipe wall thickness for weld PDIA-Dl4, so that the staff can calculate the crack growth and the allowable flaw depth for the subject weld.

2.

Weld PDIA-D14 was not listed in Attachment 2 to the submittal dated March 23, 1987.

Please explain.

3.

Two additional IGSCC.

Please and locations.

IGSCC welds.

RWCU welds were added to the list of welds susceptible to*

describe these two welds including weld identifications Explain why they were not listed in previous counts of

4.

There are 14 furnace sensitized safe ends in Dresden Unit 2.

How many were inspected in this outage? Please identify each ()f those welds.

5.

Weld PS2/20/4 was described as a elbow-pipe weld in page 2 of Attachment 3 to the submittal dated March 23, 1987.

Is it possible that this weld is a safe end-elbow weld?

6.

Referring to page 2.3 of NUTECH report ~r.:rnsmitted by l.etter dated March 23, 1987, please explain why the downsy~am as-built overlay thickness of weld 8-12 could not be taken.

Please provide a sketch of the weld overlay including the dimensions and its surrounding components.

7.

Referring to page 4.4 of the same NUTECH Report, please provide the minimum specified pipe wall thickness for each weld listed in Table 4.1-1.

8.

Referring to page 4.5 of the same NUTECH Report, please provide the overlay shrinkage data for welds 8K-13 and 8-12.

9.

Referring to page 5.10 of the same NUTECH Report, please provide the as-measured UT thickness data for each overlay repaired weld arid unrepaired welds.