ML021560298

Request for Additional Information Weld KC-32 on High Pressure Core Spray Nozzle (Tac No. MB4869)

ML021560298
Person / Time
Site:	Nine Mile Point
Issue date:	06/05/2002
From:	Tam P NRC/NRR/DLPM
To:	Conway J Nine Mile Point
Tam P, NRR/DLPM, 415-1451
References
TAC MB4869
Download: ML021560298 (4)

Text

June 5, 2002 Mr. John T. Conway Site Vice President Nine Mile Point Nuclear Station, LLC P.O. Box 63 Lycoming, NY 13093

SUBJECT:

NINE MILE POINT NUCLEAR STATION, UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING WELD KC-32 ON HIGH PRESSURE CORE SPRAY NOZZLE (TAC NO. MB4869)

Dear Mr. Conway:

The U.S. Nuclear Regulatory Commission (NRC) staff received a letter from Mr. K. S. Grewal expressing his concern about a crack at Weld KC-32 joining the high pressure core spray nozzle safe end to the safe end extension on the reactor pressure vessel. On May 21, 2002, we communicated by e-mail (publicly available in ADAMS Accession No. ML021410517) our need for additional information to complete a response to Mr. Grewal. On May 29, 2002, we held a telephone conference with your staff to discuss the issues. After the conference call, the NRC staff finalized the questions into a request for additional information (enclosure).

As discussed with your staff, we would appreciate your response by June 14, 2002. If you need clarification, please call me at 301-415-1451.

Sincerely,

/RA/

Peter S. Tam, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-410

Enclosure:

As stated cc w/encl: See next page

ML021410517) our need for additional information to complete a response to Mr. Grewal. On May 29, 2002, we held a telephone conference with your staff to discuss the issues. After the conference call, the NRC staff finalized the questions into a request for additional information (enclosure).

As discussed with your staff, we would appreciate your response by June 14, 2002. If you need clarification, please call me at 301-415-1451.

Sincerely,

/RA/

Peter S. Tam, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-410

Enclosure:

As stated cc: See next page DISTRIBUTION:

PDI-1 R/F PUBLIC RLaufer PTam SLittle OGC WKoo YLi BPlatchek, RI ACRS Accession Number: ML021560298 *Faxed OFFICE PDI-1/PM PDI-1/LA EMCB EMCB/SC EMEB EMEB/SC PDI-1/SC NAME PTam SLittle WKoo TChan YLi KManoly RLaufer DATE 6/4 /02 6/4/02 6/4/02 6/4/02 6/4/02 6/4/02 6/5/02 REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO. 2 REGARDING WELD KC-32 ON HIGH PRESSURE CORE SPRAY (HPCS) NOZZLE

Reference:

Letter, K. S. Grewal to S. Collins of NRC, April 4, 2002 (1) Provide the results of ultrasonic testing (UT) performed in the spring 2002 refueling outage on weld KC-32, and compare the results with those of the previous post-MSIP

[mechanical stress improvement process] inspections.

(2) Describe the UT equipment and procedures used in the inspection of weld KC-32 in the 2002 refueling outage, and identify the differences with those used in previous inspections. If different equipment and procedures were used, discuss their impact on the results of flaw size measurements.

(3) For comparison purposes, provide information on the following items pertaining to the UT inspections performed on weld K-32 after implementation of MSIP.

(a) UT measurement uncertainties associated with the reported flaw length and depth during each post-MSIP inspection.

(b) UT qualification requirements of the procedures/equipment/personnel that were used in the inspection of weld KC-32 during each post-MSIP inspection.

(c) During each post-MSIP UT inspection, clarify whether the spring hanger for pipe support near weld KC-32 was pinned and describe the weight of shielding lead that were placed on the HPCS piping.

(d) An estimation of upper bound compressive stresses on the flaw in weld KC-32 resulting from the weight of shielding lead with unpinned spring hangers, and the potential impact to the results of UT inspection due to these compressive stresses. Specifically, discuss the differences in resulting compressive stresses between pinned and un-pinned spring hanger configurations.

(4) Describe the design basis fatigue usage factor limit for the HPCS system. In addition, provide information pertaining to the thermal stratification stress of the HPCS piping adjoining the reactor pressure vessel nozzle, if any. Furthermore, describe how this thermal stratification stress is considered in the crack evaluation.

Enclosure

Nine Mile Point Nuclear Station Unit No. 2 cc:

Regional Administrator, Region I Mr. Michael J. Wallace U. S. Nuclear Regulatory Commission President 475 Allendale Road Nine Mile Point Nuclear Station, LLC King of Prussia, PA 19406 c/o Constellation Energy Group 250 W. Pratt Street - 24th Floor Resident Inspector Baltimore, MD 21201-2437 Nine Mile Point Nuclear Station P.O. Box 126 Mr. Raymond L. Wenderlich Lycoming, NY 13093 Senior Constellation Nuclear Officer Responsible for Nine Mile Point Nine Mile Point Nuclear Station, LLC Mr. John V. Vinquist, MATS Inc. P.O. Box 63 P.O. Box 63 Lycoming, NY 13093 Lycoming, NY 13093 James M. Petro, Jr., Esquire Supervisor Counsel Town of Scriba Constellation Power Source, Inc.

Route 8, Box 382 111 Market Place Oswego, NY 13126 Suite 500 Baltimore, MD 21202 Mr. Paul D. Eddy Electric Division Mr. William M. Flynn, President NYS Department of Public Service New York State Energy, Research, Agency Building 3 and Development Authority Empire State Plaza Corporate Plaza West Albany, NY 12223 286 Washington Avenue Extension Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 C. Adrienne Rhodes Chairman and Executive Director State Consumer Protection Board 5 Empire State Plaza, Suite 2101 Albany, NY 12223-1556 Mark J. Wetterhahn, Esquire Winston & Strawn 1400 L Street, NW.

Washington, DC 20005-3502