ML021560401
| ML021560401 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 06/03/2002 |
| From: | Feigenbaum T North Atlantic Energy Service Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-01-001, BL-02-001, NYN-02053 | |
| Download: ML021560401 (6) | |
Text
North North Atlantic Energy Service Corporation P.O. Box 300 Not Seabrook, NH 03874 Atlantic (603) 474-9521 The Northeast Utilities System June 3, 2002 Docket No. 50-443 NYN-02053 U.S. Nuclear Regulatory Commission Attn: Document Control Desk 11555 Rockville Pike Rockville, MD 20852 Seabrook Station Response to NRC Bulletin 2001-01 "Circumferential Cracking of Reactor Vessel Head Penetration Nozzles" and NRC Bulletin 2002-01 "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity" Pursuant to 10CFR50.54(f), NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Vessel Head Penetration Nozzles" dated August 3, 2001, requests that licensees provide information to permit the assessment of plant specific compliance with Nuclear Regulatory Commission (NRC) regulations concerning through-wall cracking of vessel head penetration nozzles. Also, NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity," dated March 18, 2002, requests that licensees provide information to permit the assessment of plant specific compliance with NRC regulations concerning reactor coolant pressure boundary integrity. The previous North Atlantic Energy Service Corporation (North Atlantic) responses to NRC Bulletins 2001-01 and 2002-01 were provided in references (1), (2) and (3). The North Atlantic responses to NRC Bulletin 2001-01, item 5 and NRC Bulletin 2002-01, Item 3 are provided in Enclosure 1.
Should you have any questions concerning this response, please contact Mr. James M. Peschel, Manager - Regulatory Programs, at (603) 773-7194.
Very truly yours, NORTH ATLANTIC ENERGY SERVICE CORP.
Executive Vice es1dent and Chief Nuclear Officer A* s A05~
U. S. Nuclear Regulatory Commission NYN-02053/Page 2
References:
(1)
North Atlantic Letter (NYN-01076),
Response
to NRC Bulletin 2001-01, "Circumferential Cracking of Reactor Vessel Head Penetration Nozzles," dated August 31, 2001.
(2)
North Atlantic Letter (NYN-02032), Response to NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity,"
dated April 2, 2002.
(3)
North Atlantic Letter (NYN-02047), Response to NRC Bulletin 2002-01, "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity,"
dated May 13, 2002.
cc:
H. J. Miller, NRC Region I Administrator R.D. Starkey, NRC Project Manager, Project Directorate 1-2 G.T. Dentel, NRC Senior Resident Inspector
STATE OF NEW HAMPSHIRE Rockingham, ss.
DATE Then personally appeared before me, the above-named Ted C. Feigenbaum, being duly sworn, did state that he is the Executive Vice President and Chief Nuclear Officer of the North Atlantic Energy Service Corporation that he is duly authorized to execute and file the foregoing information in the name and on the behalf of North Atlantic Energy Service Corporation and that the statements therein are true to the best of his knowledge and belief.
Marilyn y C ission Notary Public My Commission Expires: April 17, 2007
ENCLOSURE 1 TO NYN-02053
North Atlantic Response to NRC Bulletin 2001-01 "Circumferential Cracking of Reactor Vessel Head Penetration Nozzles"Bulletin 2001-01 ITEM 5:
- 5.
Addressees are requested to provide the following information within 30 days after plant restart following the next refueling outage:
- a.
A description of the extent of RHP nozzle leakage and cracking detected at your plant including the number, location, size, and nature of each crack detected;
- b.
If cracking is identified, a description of the inspections (type, scope, qualification requirements, and acceptance criteria) repairs, and other corrective actions you have taken to satisfy applicable regulatory requirements. This information is requested only if there are any changes from prior information submitted in accordance with this bulletin.
RESPONSE TO BULLETIN 2001-01 ITEM 5:
During our recent refueling outage, which commenced May 4, 2002, a VT-3 visual examination (in accordance with ASME Section XI, 1995 Edition, 1996 Addendum, Table IWB-2500-1, Examination Category B-N-1, item number B 13.10, Reactor Vessel Interior) was conducted to determine the general mechanical and structural condition of the underneath portion of the reactor vessel head.
The examination criteria of IWB-3520.2, Visual Examination VT-3 was used. No unsatisfactory conditions were noted.
1
North Atlantic Response to NRC Bulletin 2002-01 "Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity"Bulletin 2002-01 ITEM 2:
- 2.
Within 30 days after plant restart following the next inspection of the reactor pressure vessel head to identify any degradation, all PWR addressees are required to submit to the NRC the following information:
- a.
the inspection scope (if different than that provided in response to item 1.1D) and results, including the location, size, and nature of any degradation detected,
- b.
the corrective actions taken and the root cause of the degradation.
RESPONSE TO BULLETIN 2002-01 ITEM 2:
The Reactor Vessel Head visual inspection conducted during our recent refueling outage, which commenced May 4, 2002, achieved 100% coverage of the Reactor Pressure Vessel head penetrations and surfaces underneath the Reactor Vessel insulation. Evidence of leaking penetrations, boric acid, or head corrosion were not observed by the VT-2 inspectors. No corrective actions were required.
2