ML051470103
| ML051470103 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar |
| Issue date: | 05/24/2005 |
| From: | Pace P Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| BL-04-001, TAC MC3525 | |
| Download: ML051470103 (10) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 MAY 2 4 2005 10 CFR 50.54(f)
U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk 11555 Rockville Pike Rockville, Maryland 20852-2738 Gentlemen:
In the Matter of Tennessee Valley Authority
)
Docket No.50-390 WATTS BAR NUCLEAR PLANT (WBN)
UNIT 1 -
BULLETIN 2004-01, INSPECTION OF ALLOY 82/182/600 MATERIALS USED IN THE FABRICATION OF PRESSURIZER PENETRATIONS AND STEAM SPACE PIPING CONNECTIONS AT PRESSURIZED-WATER REACTORS -
INSPECTION COMPLETION (TAC NO.
Reference:
TVA letter to NRC dated July 27,
Sixty-day Response to NRC Bulletin 2004-01, Inspection Of Alloy 82/182/600 Materials Used In The Fabrication Of Pressurizer Penetrations And Steam Space Piping Connections At Pressurized-Water Reactors."
The purpose of this letter is to provide the results of the bare metal visual inspection of the upper pressurizer Alloy 600 locations (safety, spray, and relief safe-ends) performed during the WBN Unit 1 Cycle 6 refueling outage as committed in the referenced letter and in response to the subject Bulletin.
The results of the inspection are provided in the Enclosure.
There are no regulatory commitments associated with this submittal.
If you have any questions about this letter, please contact me at (423) 365-1824.
U.S. Nuclear Regulatory Commission Page 2 MAY 2 4 2005 I declare under penalty of perjury that the foregoing is true and correct.
Executed on this 24 day of May 2005.
Sincerely, P
LPace Manager, Site Licensing and Industry Affairs Enclosure Cc:
(Enclosure)
NRC Resident Inspector Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Mr. D. V. Pickett, Project Manager U.S. Nuclear Regulatory Commission MS 08G9a One White Flint North 11555 Rockville Pike Rockville, Maryland 20852-2738 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303
ENCLOSURE WATTS BAR NUCLEAR PLANT UNIT 1 BULLETIN 2004-01 UNIT 1 CYCLE 6 OUTAGE INSPECTION NRC requested plants to perform an inspection of the Alloy 82/182/600 pressurizer penetrations in Bulletin 2004-01.
TVA committed to perform this inspection in the Cycle 6 refueling outage for WBN in the 60-day response to the bulletin dated July 27, 2004.
Below is the response to NRC's request.
NRC REQUEST Within 60 days of plant restart following the next inspection of the Alloy 82/182/600 pressurizer penetrations and steam space piping connections, the subject PWR licensees should either:
(a) submit to the NRC a statement indicating that the inspections described in the licensee's response to item (1)(c) of this bulletin were completed and a description of the as-found condition of the pressurizer shell, any findings of relevant indications of through-wall leakage, followup NDE performed to characterize flaws in leaking penetrations or steam space piping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid, and any corrective actions taken and/or repairs made as a result of the indications found, or (b) if the licensee was unable to complete the inspections described in response to item (1)(c) of this bulletin, submit to the NRC a summary of the inspections performed, the extent of the inspections, the methods used, a description of the as-found condition of the pressurizer shell, any findings of relevant indications of through-wall leakage, followup NDE performed to characterize flaws in leaking penetrations or steam space piping connections, a summary of all relevant indications found by NDE, a summary of the disposition of any findings of boric acid, and any corrective actions taken and/or repairs made as a result of the indication found.
In addition, supplement the answer which you provided to item (1)(d) above to explain why the inspections that you completed were adequate for E-1
ENCLOSURE WATTS BAR NUCLEAR PLANT UNIT 1 BULLETIN 2004-01 UNIT 1 CYCLE 6 OUTAGE INSPECTION (c) the purpose of maintaining the integrity of your facility's RCPB and for meeting all applicable regulatory requirements which pertain to your facility.
RESPONSE
In TVA's response to Item (1)(c) of Bulletin 2004-01 dated July 27, 2004, TVA committed to perform a bare metal visual (BMV) inspection of the upper pressurizer Alloy 600 locations (safety, spray, and relief safe-ends) during the upcoming Unit 1 Cycle 6 Refueling Outage (RFO) in the Spring 2005.
TVA also submitted a supplemental response to the bulletin dated February 11, 2005 which provided a description of the WBN pressurizer and each pressurizer penetration.
That submittal confirmed the locations of any Alloy 82/182/600 penetrations and steam space piping connections.
TVA restarted from Cycle 6 RFO on April 1, 2005.
The BMV inspections were performed during the outage in accordance with TVA's procedure N-VT-19, "Visual Inspection of Alloy 600/82/182 Pressure Boundary Components."
The results of the inspection indicated no relevant indications of through-wall leakage at those locations.
The data sheets from those inspections are attached.
ISI drawing CHM-2570-C-01 is also attached and provides the locations of the component identifiers recorded on the data sheets.
An NRC Region II Inspector, who was on site performing the Inservice Inspection (ISI) inspection, witnessed the inspection of the Alloy 82/182/600 locations.
The inspector's review is documented in Inspection Report 50-390/2005-002.
E-2
ENCLOSURE WATTS BAR NUCLEAR PLANT UNIT 1 BULLETIN 2004-01 UNIT 1 CYCLE 6 OUTAGE INSPECTION TENNESSEE VALLEY AUTHORITY RECORD OF VISUAL EXAINNATION EXAM DAT&
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) DIMENSIONS TlTLE SEAM NO.
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REFERENCE DRAWINGS 47W465-2 VENmooR MANUAL wuN-VTf-WI20-055O FIGURES 5-1. 5-3. 5-6. 5-7S. 5-1. 5-71 MATERIAL SPECIFICATIONS NOZZLE SAFE ENDS SURGE 14 S-CH.
160 SA - 182 OR F-3 I 6L SPRAY SCH. 160 SA-182 OR F-316L SAFETY 6 SCH. 160 SA-182 OR F-316L RELIEF 6 SCH. 160 SA-182 OR F-316L NOZZLE & MANWAY FORGINGS SA-50B CLASS 2 SHELL BARRELS SA 533 GR. A CL. 2 UPPER & LOWER HEAD SA -533 GR. A CL. 2 ASME CC-I (EQUIVALENT)
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