NRC 2002-0038, Supplement to Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles.

From kanterella
Revision as of 14:41, 26 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Supplement to Response to NRC Bulletin 2001-01, Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles.
ML021550428
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/09/2002
From: Warner M
Nuclear Management Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
BL-01-001, NRC 2002-0038
Download: ML021550428 (3)


Text

Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, WI 54241 920.755.2321 NMC Committed to NuclearECelfence Excell VKwue 920.388.2560 Kewaunee on Beach Point ec Nuclear ula Operated by Nuclear Management Company, LLC NRC 2002-0038 10 CFR 50.54(f)

May 09, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Ladies/Gentlemen:

Docket Numbers 50-266 and 50-301 Point Beach Nuclear Plant (PBNP), Units 1 and 2 Supplement To Response To NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles"

References:

1. NMC Letter dated September 4, 2001, "Response To NRC Bulletin 2001 01, 'Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles"'
2. NMC Letter dated January 3, 2002, "Revised Response To NRC Bulletin 2001-01, 'Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles"'

In Reference 1, Nuclear Management Company, LLC (NMC), licensee for Point Beach Nuclear Plant (PBNP), Units 1 and 2, provided the requested response to NRC Bulletin 2001-01, CircumferentialCracking of ReactorPressure Vessel Head PenetrationNozzles.

In Reference 2, NMC provided additional information in response to the NRC Bulletin, item 1 .e, describing the reactor vessel level indication system piping. Reference 2 also provided additional information in response to a request made during telephone conversations between NRC staff and NMC representatives on October 30, 2001 and on December 18, 2001. The NRC request focused on the proposed inspection techniques provided in response to item 4.a of the NRC Bulletin.

During telephone conversations between NRC staff and NMC representatives on March 15, 2002, and on April 23, 2002, NRC staff requested additional information in response to item 4.a, regarding proposed under head inspection techniques, in the event above head inspection results were indeterminate for any given reactor pressure vessel (RPV) nozzle.

NRC 2002-0038 May 09, 2002 Page 2 Therefore, NMC is providing the following information: The base metal RPV head inspection performed on PBNP Unit 2 in April 2002 resulted in an effective visual examination that revealed no evidence of boric acid deposition or wastage of the RPV head. The Unit 1 RPV head inspection is scheduled for the Fall 2002 outage. For those RPV head penetrations that the NMC cannot obtain an effective visual examination, an examination from underneath the RPV head will be performed using one of several available methods. These methods may include rotating or blade ultrasonic probes or eddy current as applicable. The RPV head nozzle penetration examination method used will be capable of ensuring no through-wall pressure boundary leakage.

To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respects, these statements are not based entirely on my personal knowledge, but on information furnished by cognizant NMC employees and consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on May 09, 2002.

Mark E. Warner Site Vice President RDS/kmd cc: NRC Regional Administrator NRC Project Manager - PBNP NRC Senior Resident Inspector - PBNP

NRC 2002-0038 May 09, 2002 Page 3 bcc: R. A. Anderson L. J. Armstrong A. J. Cayia K. M. Duescher (3) J. Gadzala R. R. Grigg (P460)

B. D. Kemp C. T. Prothero R. P. Pulec T. H. Taylor C. A. Tomes M. E. Warner D. A. Weaver (P129) T. J. Webb E. J. Weinkam III

Text

Kewaunee Nuclear Power Plant Point Beach Nuclear Plant N490 Highway 42 6610 Nuclear Road Kewaunee, WI 54216-9511 Two Rivers, WI 54241 920.755.2321 NMC Committed to NuclearECelfence Excell VKwue 920.388.2560 Kewaunee on Beach Point ec Nuclear ula Operated by Nuclear Management Company, LLC NRC 2002-0038 10 CFR 50.54(f)

May 09, 2002 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Ladies/Gentlemen:

Docket Numbers 50-266 and 50-301 Point Beach Nuclear Plant (PBNP), Units 1 and 2 Supplement To Response To NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles"

References:

1. NMC Letter dated September 4, 2001, "Response To NRC Bulletin 2001 01, 'Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles"'
2. NMC Letter dated January 3, 2002, "Revised Response To NRC Bulletin 2001-01, 'Circumferential Cracking of Reactor Pressure Vessel Head Penetration Nozzles"'

In Reference 1, Nuclear Management Company, LLC (NMC), licensee for Point Beach Nuclear Plant (PBNP), Units 1 and 2, provided the requested response to NRC Bulletin 2001-01, CircumferentialCracking of ReactorPressure Vessel Head PenetrationNozzles.

In Reference 2, NMC provided additional information in response to the NRC Bulletin, item 1 .e, describing the reactor vessel level indication system piping. Reference 2 also provided additional information in response to a request made during telephone conversations between NRC staff and NMC representatives on October 30, 2001 and on December 18, 2001. The NRC request focused on the proposed inspection techniques provided in response to item 4.a of the NRC Bulletin.

During telephone conversations between NRC staff and NMC representatives on March 15, 2002, and on April 23, 2002, NRC staff requested additional information in response to item 4.a, regarding proposed under head inspection techniques, in the event above head inspection results were indeterminate for any given reactor pressure vessel (RPV) nozzle.

NRC 2002-0038 May 09, 2002 Page 2 Therefore, NMC is providing the following information: The base metal RPV head inspection performed on PBNP Unit 2 in April 2002 resulted in an effective visual examination that revealed no evidence of boric acid deposition or wastage of the RPV head. The Unit 1 RPV head inspection is scheduled for the Fall 2002 outage. For those RPV head penetrations that the NMC cannot obtain an effective visual examination, an examination from underneath the RPV head will be performed using one of several available methods. These methods may include rotating or blade ultrasonic probes or eddy current as applicable. The RPV head nozzle penetration examination method used will be capable of ensuring no through-wall pressure boundary leakage.

To the best of my knowledge and belief, the statements contained in this document are true and correct. In some respects, these statements are not based entirely on my personal knowledge, but on information furnished by cognizant NMC employees and consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on May 09, 2002.

Mark E. Warner Site Vice President RDS/kmd cc: NRC Regional Administrator NRC Project Manager - PBNP NRC Senior Resident Inspector - PBNP

NRC 2002-0038 May 09, 2002 Page 3 bcc: R. A. Anderson L. J. Armstrong A. J. Cayia K. M. Duescher (3) J. Gadzala R. R. Grigg (P460)

B. D. Kemp C. T. Prothero R. P. Pulec T. H. Taylor C. A. Tomes M. E. Warner D. A. Weaver (P129) T. J. Webb E. J. Weinkam III