ML061770492

Email: Fwd: Bolting Follow-Up (PA)

ML061770492
Person / Time
Site:	Oyster Creek
Issue date:	05/25/2006
From:	Hufnagel J Exelon Corp
To:	Veronica Rodriguez NRC/NRR/ADRO/DLR
References
TAC MC7624
Download: ML061770492 (8)

Text

FW: Bolting follow-up Page 1 of 2 D. Ashley - FW: Bolting follow-up From: <john.hufnagel @exeloncorp.com>

To: <vmrl @nrc.gov>

Date: 05/25/2006 11:00:32 AM

Subject:

FW: Bolting follow-up CC: <djal @nrc.gov>

Veronica, I know Donnie is heading out shortly or maybe has gone for the week. Would you please forward this to the reviewer (John Ma) if you can't confirm Donnie was able to do so? Also, if you get any feedback regarding the usefulness of this information prior to Donnie returning, perhaps you could let me know. Also, if appropriate, we could set up a call to discuss further with the reviewer.

Thanks.

- John.

--- Original Message---

From: Hufnagel Jr, John G Sent: Thursday, May 25, 2006 10:55 AM To: Donnie Ashley (E-mail)

Cc: Ouaou, Ahmed; Polaski, Frederick W

Subject:

Bolting follow-up

Donnie, Per our discussion, I wanted to forward to you a copy of the question/answer that covered this topic during the Audits. As you'll recall, this information has previously been docketed as part of the Q&A database information.

A few points to note:

" Monitoring of bolting including high strength bolting was discussed extensively during the AMP/AMR audits. CMTRs and other information was reviewed on-site during the process. The result was that the Auditor was satisfied with the monitoring program/activities as described in the LRA, and as noted in the response to Question AMR-176.

" The LRA provides quite a bit of information in the Appendix A FSAR supplement sections on Bolting Integrity and Structural Monitoring, and the Appendix B Program description sections on those same two programs, making it clear that AmerGen uses and plans to continue to use the Structural Monitoring program to manager/monitor bolting of all types.

Hopefully the attached Q&A will provide the reviewer with some useful information. Please pass this on to the reviewer and let me know if we want to discuss further. We can certainly set something up. Thanks.

- John.

<<Q&A 176.pdf>>

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FW: Bolting follow-up Creation Date 05/25/2006 10:59:43 AM From: <iohn.hufnagel @exeloncorp.com>

Created By: john.hufnagel @exeloncorp.com Recipients nrc.gov TWGWPO01.HQGWDOO1 VMR 1 (Veronica Rodriguez) nrc.gov OWGWPO01.HQGWDO01 DJA1 CC (D. Ashley)

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D. Ashley - O&A 176.pdf -Fia Pac~eeý_1 ill9 D. Ashley O&A 176.pdf JNRC Information Request Form Item No Date Received: Source AMR-176 10/31/2005 AMR Audit Topic: Status: Closed Bolting Materials Used in Structural Applications Document

References:

3.5.1-38 NRC Representative Morante, Rich AmerGen (Took Issue): Hufnagel, Joh Ouestion More information is needed about bolting materials used in structural applications at OCGS, including Group B13.1 applications. What are the bolting materials used? What are the nominal yield strengths and upper-bound as-received yield strengths? Describe the OCGS resolution of the bolting integrity generic issue, as it relates to structural bolting. Was any structural bolting identified as potentially susceptible to cracking due to SCC? Was any structural bolting replaced as part of the resolution?

Assigned To: Ouaou, Ahmed

Response

Responrse:

More information is needed about bolting materials used in structural applications at OCNGS, including Group B13.1 applications.

a) What are the bolting materials used?

Response

The review of plant design drawings, specifications, and NRC correspondence indicates that ASTM A-307, A-325, A-193 Gr.B7, A-1 93 Grade B8M, and A-490 bolts were used in structural applications.

The ASME Class 1 piping and component supports (Group B1.1), other than reactor vessel skirt support bolts, were furnished by Grinnell Corporation and identified on the hanger drawings as (H.S.)

without material designation. These were assumed to be A-193 Grade B7 or equivalent based on compatabfifty with Grinnell materials and support standards. The bolts for the reactor vessel skirt support are indicated as ASTM A-325 on the drawings.

b) What are the nominal yield strengths and upper bound as-received yield strengths?

Response: i In response to IE Bulletin 87-02, GPU performed chemical, hardness, and physical testing on sample of safety and non-safety related bolting and transmitted the results to NRC (Ref. 1). The test results for yield strengths are shown below:

D.,Ashley - Q&A 176.pdf Pg INRC Information Request Form Bolt Material Nominal Yield (PSI) Actual Yield (PSI)

A-193 Gr B7 105,000 121,212 105,000 140,000 105,000 139,030 105,000 132,113 105,000 127,858 105,000 125,418 105,000 151,960*

105,000 122,646 105,000 128,318 105,000 129,081 105,000 117,617 105,000 107,601 A-193 Gr B8M 30,000 67,961 30,000 84,577 30,000 84,210 30,000 86,248 30,000 63,157 A-193 Gr B8 30,000 85,539 A-193 Gr B8 30,000 96,938 A-307 36,000 Not tested A-325 81,000 127,842 A-490 130,000 See Below

• This test sample is not used in structural applications.

Since the response to the bulletin was provided, a review of the stocking of A-490 bolting was performed. Based on the history of stocking of A-490 bolting, it was determined bolts of this material were installed as part of a modification In the year 2000. These bolts were procured in accordance with the established specifications and installed as part of the Reactor Building Single Failure Proof Crane Modification.' The 7/8 inch diameter bolts were installed to secure a new stiffener clip between the reactor building superstructure column and the Reactor Building Crane Rail Beam. The bolting was installed to snug tight thus not subject to high prelaod.

c) Describe the OCGS resolution of the bolting integrity generic issue, as it relates to structural bolting.

Response

Oyster Creek implemented the following actions to resolve the bolting integrity generic issue:

D. Ashlev - O&A 176.pdf Page 30 Page 311 D.Ashley Q&A 176.pdf INRC Information Request Form

1. In response to IE Bulletin 87-02, "Fastener testing to determine conformance with applicable material specifications", GPU performed chemical, hardness, and physical testing on a sample of safety and non-safety related bolting to determine material conformance and transmitted the results to NRC (Ref. 1).

2. In response to JE Bulletin 87-02, Supplement 1, GPU performed an extensive review of the Supplier Quality Classification List (SQCL) and Contractor Classification List (CCL) and submitted the result to NRC (Ref. 2).

3. Oyster Creek established procedures that are based on the guidance and recommendations provided in NUREG-1339, "Resolution of Generic Safety Issue 29: Bolting Degradation of Failure in Nuclear Power Plants", EPRI NP-5769,"Degradation and Failure of Bolting in Nuclear Power Plants",

and EPRI 5067, "Good Bolting Practices". These include, All safety related fasteners are bought from vendors on GPUN OA approved vendor's list.

Fasteners are subject to receipt inspections designed to identify substandard/frau dulent items.

Suspect bolts are tested before they are released for use.

Approved lubricants are controlled by procedures. The primary lubricant at Oyster Creek is Chesterton, a nickel based lubricant that does not contain Molybdenum sulfate (MoS2).

Installation procedures provide instructions for proper tightening of bolted connections.

d) Was any structural bolting identified as potentially susceptible to cracking due to SCC?

Response

No. The reviewed documentation on the resolution of the generic bolting issue did not identify any structural bolting that is potentially susceptible to cracking due SCC.

e) Was any structural bolting replaced as part of the resolution?

Response

No. The reviewed documentation on the resolution of the generic bolting issue did not identify any instances where structural bolting was replaced to resolve the bolting issue.

Reference:

1. Letter from P. B. Fiedler (GPU) to W. T. Russell (NRC), "Response to NRC Compliance Bulletin 87-02; Faster Testing to Determine Material Conformance", dated February 26, 1988.

2. Letter from E. E. Fitzpatrick (GPU), "GPUN Response to Bulletin 87-02, dated February 26, 1988, NRC Bulletin 87-02, Supplement 1", dated July 25, 1988.

3. NUREG-1339, "Resolution of Generic Safety Issue 29: Bolting Degradation or Failure in Nuclear Power Plants", June 1990.

4. Generic Letter 91-71, Generic Safety Issue 29, "Bolting Degradation or Failure in Nuclear in Nuclear Power Plants".

5. EPRI NP-5769, "Degradation and Failure of Bolting in Nuclear Power Plants", Volume 1 & Volume 2, April 1988.

D. Ashlev - Q&A 176.pdf Page 41 41 D. Ashley Q&A 176.pdf Page INRC Information Request Form

6. EPRI NP-5067, "Good Bolting Practices", Volume 1 &Volume 2, December 1990.

LRCR #: LRA A.5 Commitment #:

IR#P:

Approvals:

PreparedBy: Ouaou, Ahmed 2/16/2006 Reviewed By: Ouintenz, Tom 2/16/2006 ApprovedBy: Warfel, Don 2/16/2006 NRC Acceptance (Date):