Letter Sequence Other |
|---|
|
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MONTHYEARML0208701212002-03-29029 March 2002
Conference Call (Meeting) with Rg&E Rg&E Response to NRC Bulletin 2002-01 Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity
Project stage: Meeting
ML0209405052002-04-0303 April 2002
Conference Call Regarding Rg&E Post-Inspection Results of the Reactor Pressure Vessel Head
Project stage: Other
ML0209500102002-04-0505 April 2002
R. E. Ginna Nuclear Power Plant - Summary of 03/29/2002 Conference Call Rg&E Post-Inspection Results of the Reactor Pressure Vessel Head
Project stage: Other
ML0214303112002-05-24024 May 2002
Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity, 15-Day Response (Tac No. MB4548)
Project stage: Other
ML0217006932002-06-12012 June 2002
R. E. Ginna Withdrawal of Request for Application for Amendment to Facility Operating License Regarding Proposed Change to Plant Staff Qualification
Project stage: Withdrawal
ML0232600672002-11-22022 November 2002
RAI, Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
Project stage: RAI
2002-04-03
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Text
April 3, 2002 LICENSEE: Rochester Gas and Electric Corporation (RG&E)
FACILITY: R. E. Ginna Nuclear Power Plant
SUBJECT:
SUMMARY
OF MARCH 29, 2002, CONFERENCE CALL REGARDING RG&E POST-INSPECTION RESULTS OF THE REACTOR PRESSURE VESSEL HEAD (TAC NO. MB4548)
On March 29, 2002, a conference call was held with members of the U.S. Nuclear Regulatory Commission (NRC) staff and representatives from Rochester Gas and Electric Corporation, the licensee for Ginna Nuclear Power Plant. The list of participants is enclosed. The purpose of this call was to discuss the licensees preliminary results of their inspection of the reactor pressure vessel head.
The reactor pressure vessel head inspection consisted of: 1) a 100% visual inspection of the block insulation located on top of the reactor pressure vessel head inside the shroud support ring; 2) ultrasonic testing to verify the thickness of the head around the center control rod drive mechanism (CRDM) penetration nozzle; and 3) ultrasonic testing of that portion of the head located outside the shroud support ring where four nearby instrument ports had previously experienced boric acid leakage. The licensee asserted that a potential through-wall crack in a penetration nozzle, J-groove weld or leakage from above the reactor pressure vessel head would lead to accumulation of boric acid and corrosion products at the head/insulation interface, in the annulus between insulation and nozzle, and above the insulation. The licensee also postulated that if the boric acid deposits and corrosion products were to accumulate at the head/insulation interface, the accumulation would eventually exert sufficient force on the insulation to cause displacement or cracking.
Based on the results of the visual inspection, the licensee stated that the block insulation within the shroud support ring was in very good condition with only minor cracks or gaps in the insulation. The licensee also stated that some minor staining (brown spots) was present on top of the insulation and that white shading was also observed on certain CRDM nozzles.
However, there was no evidence of boric acid deposits or corrosion products on the outside surface of the insulation and no visible indication of distortion (displacement or cracking) of the block insulation due to boric acid/corrosion product uplifting.
In areas where the insulation was damaged (stained, missing or cracked), the licensee removed small pieces of the insulation to expose the bare metal of the head. These areas showed no evidence of boric acid deposits nor any evidence of degradation. Upon careful examination of the discolored areas, the licensee determined that the brown coloring on top of the block insulation was due to previous conoseal leaks from instrument ports and was not the result of corrosion products. The white coloring observed on some of the nozzles (near the canopy seal weld) was due to white developer overspread while performing Section XI weld inspections and was not boric acid deposits. The licensee also analyzed block insulation samples (i.e., the ones removed to expose the bare metal of the head) and determined that no
significant radioactivity was present (providing some assurance that no significant leakage had occurred).
In addition to the above, bare metal inspections of several penetration nozzles were performed using a video camera to look into the annulus between the block insulation and nozzle. The licensee stated that the video inspection did not reveal any crystalline deposits around the penetration nozzles. The licensee also removed the block insulation from the head outside the shroud support ring to perform bare metal inspection of the head in this region. No boric acid deposits or corrosion products were observed coming out of the shroud support ring from under the insulation.
The ultrasonic testing (UT) examination on the center CRDM penetration nozzle from beneath the head indicated that head thickness was well within design limits and that there was no physical evidence of reactor vessel head corrosion (i.e., no material loss). The licensee also performed UT examination for wall thickness of the reactor pressure vessel head outside the shroud support ring on the downhill side of four instrument ports. The results indicated that the head thickness was well within design limits.
Following the licensees presentation, the NRC staff stated that it did not have any further questions. The licensee stated that a formal letter will be sent to the NRC documenting the results of the reactor vessel head inspection within 30 days after plant restart as required by NRC Bulletin 2002-01. Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
/RA/
Robert L. Clark, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: See next page
significant radioactivity was present (providing some assurance that no significant leakage had occurred).
In addition to the above, bare metal inspections of several penetration nozzles were performed using a video camera to look into the annulus between the block insulation and nozzle. The licensee stated that the video inspection did not reveal any crystalline deposits around the penetration nozzles. The licensee also removed the block insulation from the head outside the shroud support ring to perform bare metal inspection of the head in this region. No boric acid deposits or corrosion products were observed coming out of the shroud support ring from under the insulation.
The ultrasonic testing (UT) examination on the center CRDM penetration nozzle from beneath the head indicated that head thickness was well within design limits and that there was no physical evidence of reactor vessel head corrosion (i.e., no material loss). The licensee also performed UT examination for wall thickness of the reactor pressure vessel head outside the shroud support ring on the downhill side of four instrument ports. The results indicated that the head thickness was well within design limits.
Following the licensees presentation, the NRC staff stated that it did not have any further questions. The licensee stated that a formal letter will be sent to the NRC documenting the results of the reactor vessel head inspection within 30 days after plant restart as required by NRC Bulletin 2002-01. Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity.
/RA/
Robert L. Clark, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION PUBLIC PD1-1 Rdg File J. Zwolinski/T. Marsh W. Bateman R. Clark A. Hiser K. Karwoski J. Munday S. Little S. Bloom D. McCain I. Jung D. Lew, RGI M. Evans, RGI B. Platchek, RGI T. Bergman, RGI W. Lanning, RG1 C. Welch, RGI ACRS OGC J. Collins E. Gray, RGI L. Doerflein, RGI Accession No.: ML020940505 OFFICE PDI-1/PM PDI-1/LA EMCB/PM PD1-1/(A)SC NAME RClark SLittle SBloom JMunday DATE 4/3/02 4/3/02 4/3/02 4/3/02 OFFICIAL RECORD COPY
R.E. Ginna Nuclear Power Plant cc:
Christopher Welch, Sr. Resident Inspector Mr. Paul Eddy R.E. Ginna Plant New York State Department of U.S. Nuclear Regulatory Commission Public Service 1503 Lake Road 3 Empire State Plaza, 10th Floor Ontario, NY 14519 Albany, NY 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. William M. Flynn, President New York State Energy, Research, and Development Authority Corporate Plaza West 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 Daniel F. Stenger Ballard Spahr Andrews & Ingersoll, LLP 601 13th Street, N.W., Suite 1000 South Washington, DC 20005 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Falls Road, Room 11 Rochester, NY 14620
LIST OF MEETING PARTICIPANTS March 29, 2002 NRC Robert Clark NRR Larry Doerflein Region 1 Steven Bloom NRR Christopher Welch Region 1 Kenneth Karwoski NRR Michele Evans Region 1 Edwin Gray Region 1 RG&E Robert Mecredy Joe Widay Paul Lewis Al Butcavage John Smith Mark Flaherty Gerry Geiken Enclosure
