ML023100166

From kanterella
Jump to navigation Jump to search

Request for Additional Information, Related to Relief Request
ML023100166
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 11/06/2002
From: Skay D
NRC/NRR/DLPM/LPD1
To: Katz P
Calvert Cliffs
Skay D, NRR/DLPM, 415-1322
References
-nr, TAC MB4013, TAC MB4014
Download: ML023100166 (4)


Text

November 6, 2002 Mr. P. E. Katz, Vice President Calvert Cliffs Nuclear Power Plant, Inc.

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

SUBJECT:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -

REQUEST FOR ADDITIONAL INFORMATION RELATED TO RELIEF REQUEST (TAC NOS. MB4013 AND MB4014)

Dear Mr. Katz:

In reviewing your submittal of February 7, 2002, concerning the subject relief request, the U.S. Nuclear Regulatory Commission (NRC) staff determined that it needs additional information to continue its review. The NRC staff discussed the issue with your staff on October 24, 2002. As we indicated during our conversation, we are enclosing the request for additional information.

Sincerely,

/RA/

Donna M. Skay, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/encl: See next page

ML023100166 OFFICE PDI-1/PM PDI-1/LA EMCB PDI-1/SC NAME DSkay SLittle WBateman TChan RLaufer DATE 10/30/02 10/30/02 10/31/02 10/31/02 Calvert Cliffs Nuclear Power Plant Unit Nos. 1 and 2 cc:

President Kristen A. Burger, Esquire Calvert County Board of Maryland Peoples Counsel Commissioners 6 St. Paul Centre 175 Main Street Suite 2102 Prince Frederick, MD 20678 Baltimore, MD 21202-1631 James Petro, Esquire Patricia T. Birnie, Esquire Counsel Co-Director Constellation Power Source Maryland Safe Energy Coalition 111 Market Street P.O. Box 33111 Baltimore, MD 21202 Baltimore, MD 21218 Jay E. Silberg, Esquire Mr. Loren F. Donatell Shaw, Pittman, Potts, and Trowbridge NRC Technical Training Center 2300 N Street, NW 5700 Brainerd Road Washington, DC 20037 Chattanooga, TN 37411-4017 Mark Geckle Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean, Manager Nuclear Programs Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406

REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 RELIEF REQUEST TO USE ALTERNATIVE TECHNIQUES FOR REACTOR VESSEL HEAD REPAIR

1. A Section III analysis should be performed to demonstrate the structural integrity of the weld repair. In addition, the experience from other licensees who have completed their control rod drive mechanism (CRDM) nozzle repairs of a similar nature indicates that a weld anomaly could exist at the root of the CRDM weld repair. As a result, they requested relief from NB-5330(b), which requires that indications characterized as cracks, lack of fusion, or incomplete penetration are unacceptable regardless of length; and proposed, alternatively, a flaw evaluation using a conservatively assumed flaw size to demonstrate the structural integrity of the weld repair with weld anomaly. The Nuclear Regulatory Commission requests that the licensee either demonstrate through ultrasonic testing that the repair would not have this weld anomaly or request relief from NB-5330(b) and perform a flaw evaluation to assess the impact of this anomaly on the structural integrity of the weld repair.
2. Identify the specific paragraphs and subparagraphs that you are taking exception to from the AME Boiler and Pressure Vessel Code for each of your exceptions, and the basis for the exceptions.
3. How do you intend to address crevice corrosion?
4. Triple point anomaly (TPA) is the joining of three different materials. Address any implications of TPA on the primary water stress corrosion cracking (PWSCC) and the non-PWSCC sides of the repair welds.
5. Verify the edition of the Code that is being referenced for the Section III repairs and non-destructive examination.

Enclosure