ML060270303
| ML060270303 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 02/03/2006 |
| From: | Pickett D NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Singer K Tennessee Valley Authority |
| DOUGLAS PICKET, NRR/DORL, 41501364 | |
| References | |
| TAC MC8305 | |
| Download: ML060270303 (6) | |
Text
February 3, 2006 Mr. Karl W. Singer Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
SUBJECT:
WATTS BAR NUCLEAR PLANT, UNIT 1 REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST NO. ISPT-09 FOR THE FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL (TAC NO. MC8305)
Dear Mr. Singer:
By letter dated September 8, 2005 (ADAMS Accession Number: ML052560093), Tennessee Valley Authority (TVA), the licensee for the Watts Bar Nuclear Plant, Unit 1 (WBNP-1),
submitted Relief Request (RR) No. ISPT-09. In this request, TVA requested relief from the requirements of Paragraph (g)(4) to Section 50.55a of Title 10 of the Code of Federal Regulations and the system leak test requirements that are specified in Table IWB-2500-1, Examination Category B-P and Paragraph IWA-5222(a) of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1. RR No. ISPT-09 is applicable to the First Ten-Year Inservice Inspection Interval for WBNP-1 and pertains to the system leak test requirements for ASME Code Class 1 portions of the safety injection and residual heat removal systems.
In order for the staff of the Nuclear Regulatory Commission to complete its review of the subject relief request, we request that the licensee respond to the enclosed request for additional information (RAI). Based on discussions with your staff, we understand that you plan to respond to the enclosed RAI within 60 days of receipt of this letter.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-390
Enclosure:
Request for Additional Information cc w/enclosure: See next page
ML060270303 NRR-088 OFFICE LPL2-2/LA LPL2-2/PM DCI/CFEB LPL2-2/BC NAME RSola DPickett JTsao (A) MMarshall by memo dated DATE 02/03/ 06 02/03/ 06 12 / 12 / 05 2 / 03 / 06 Mr. Karl W. Singer Tennessee Valley Authority WATTS BAR NUCLEAR PLANT cc:
Mr. Ashok S. Bhatnagar, Senior Vice President Mr. Glenn W. Morris, Manager Nuclear Operations Corporate Nuclear Licensing Tennessee Valley Authority and Industry Affairs 6A Lookout Place Tennessee Valley Authority 1101 Market Street 4X Blue Ridge Chattanooga, TN 37402-2801 1101 Market Street Chattanooga, TN 37402-2801 Mr. Larry S. Bryant, Vice President Nuclear Engineering & Technical Services Mr. Paul L. Pace, Manager Tennessee Valley Authority Licensing and Industry Affairs 6A Lookout Place Watts Bar Nuclear Plant 1101 Market Street Tennessee Valley Authority Chattanooga, TN 37402-2801 P.O. Box 2000 Spring City, TN 37381 Mr. Robert J. Beecken, Vice President Nuclear Support Mr. Jay Laughlin, Plant Manager Tennessee Valley Authority Watts Bar Nuclear Plant 6A Lookout Place Tennessee Valley Authority 1101 Market Street P.O. Box 2000 Chattanooga, TN 37402-2801 Spring City, TN 37381 Mr. Michael D. Skaggs Senior Resident Inspector Site Vice President Watts Bar Nuclear Plant Watts Bar Nuclear Plant U.S. Nuclear Regulatory Commission Tennessee Valley Authority 1260 Nuclear Plant Road P.O. Box 2000 Spring City, TN 37381 Spring City, TN 37381 County Executive General Counsel 375 Church Street Tennessee Valley Authority Suite 215 ET 11A Dayton, TN 37321 400 West Summit Hill Drive Knoxville, TN 37902 County Mayor P. O. Box 156 Mr. John C. Fornicola, Manager Decatur, TN 37322 Nuclear Assurance and Licensing Tennessee Valley Authority Mr. Lawrence E. Nanney, Director 6A Lookout Place Division of Radiological Health 1101 Market Street Dept. of Environment & Conservation Chattanooga, TN 37402-2801 Third Floor, L and C Annex 401 Church Street Nashville, TN 37243-1532 Ms. Ann P. Harris 341 Swing Loop Road Rockwood, Tennessee 37854
REQUEST FOR ADDITIONAL INFORAMTION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FIRST 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM TENNESSEE VALLEY AUTHORITY REQUEST FOR RELIEF NO. ISPT-09 WATTS BAR NUCLEAR PLANT, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-90 DOCKET NO: 50-390
- 1. Relief Request (RR) No. ISPT-09 requests relief from the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Division 1 (henceforth Section XI), Table IWB-2500-1, Examination Category B-P, based on the hardship provisions that are specified in Paragraph (a)(3)(ii) of Title 10 of the Code of Federal Regulations. Specify which Edition of Section XI is the Code of record for Watts Bar Nuclear Plant, Unit 1 (WBN-1). In addition, specify which Inspection Items in Section XI Table IWB-2500-1, Examination Category B-P are applicable to the piping segments that are within the scope of the relief request, as identified in Table 1, Piping Segment Descriptions, of the Enclosure to the relief request.
- 2. Reference the basis (e.g., Academic Textbook, ASME Section XI paragraph, NUREG Report, etc.) for the following equation that is specified on Page E-4 of the RR No.
ISPT-09 submittal:
Lp = LXI x ( Pp / PXI )1/2
- 3. The relief request proposes to perform the required hydrostatic pressure tests of the ASME Code Class 1 piping segments at test pressures lower than those that are required in Section XI Table IWB-5220-1, which is called out by reference in Section XI Paragraph IWB-5222(a). Confirm that the alternative pressure tests proposed in RR No. ISPT-09 will be subject to the minimum hold times that are required by Section XI Paragraph IWA-5213 for hydrostatic pressure tests and the minimum test temperatures that are required by Section XI Article 5000 (e.g., the minimum temperature requirements in Paragraph IWB-5230 in Editions through the 1992 Edition or in Paragraph IWB-5240 in the 1995 Edition and more recent Editions).
ENCLOSURE
- 4. Table 1, Piping Segment Descriptions, of the Enclosure to RR No. ISPT-09 (i.e., the enclosure to the Tennessee Valley Authority letter of September 8, 2005) provides the descriptions of the piping segments that are within the scope of the relief request. The staff seeks the following clarifications for the piping segments descriptions that are provided in Table 1:
- a. Reactor Coolant Loop 1 on Page E-7: Low pressure safety injection from RHR system CKV-63-633 to the 10-inch Loop 1 cold leg injection line. Clarify which component in the 10-inch Loop 1 cold leg injection line bounds the end of the piping segment that requires pressure testing.
- b. Reactor Coolant Loop 1 on Page E-7: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 1 cold leg piping to CKV-63-586. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-586 in the Loop 1 cold leg piping.
- c. Reactor Coolant Loop 1 on Page E-7: Safety injection pump piping from CKV-63-543 to the 8-inch Loop 1 hot leg injection line. Clarify which component in the 8-inch Loop 1 hot leg injection line bounds the end of the piping segment.
- d. Reactor Coolant Loop 1 on Page E-7: Safety injection pump piping from CKV-63-551 to the 6-inch Loop 1 cold leg injection line. Clarify which component in the 6-inch Loop 1 cold leg injection line bounds the end of the piping segment.
- e. Reactor Coolant Loop 2 on Page E-8: Low pressure safety injection from RHR system CKV-63-632 to the 10-inch Loop 2 cold leg injection line. Clarify which component in the 10-inch Loop 2 cold leg injection line bounds the end of the piping segment.
- f. Reactor Coolant Loop 2 on Page E-8: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 2 cold leg piping to CKV-63-587. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-587 in the Loop 2 cold leg piping.
- g. Confirm that the Loop 2 piping segment descriptions on page E-8 should not include an entry from a check valve in the Safety Injection pump piping to a valve in an 8-inch or 6-inch Loop 2 hot leg injection line in the manner they have been included for Reactor Coolant System Loops 1, 3, and 4. If the Loop 2 entries should include such a piping segment description and the entry has not been included in Table 1, please amend Table 1 to add it. If the Loop 2 entries in Table 1 do include such a piping segment entry, please identify which entry contains the applicable component description.
- h. Reactor Coolant Loop 2 on Page E-8: Safety Injection pump piping from
CKV-63-553 to the 6-inch Loop 2 cold leg injection line. Clarify which component in the 6-inch Loop 2 cold leg injection line bounds the end of the piping segment.
I. Reactor Coolant Loop 3 on Page E-9: Low pressure safety injection from RHR system CKV-63-634 to the 10-inch Loop 3 cold leg injection line. Clarify which component in the 10-inch Loop 3 cold leg injection line bounds the end of the piping segment.
- j. Reactor Coolant Loop 3 on Page E-9: High pressure safety injection piping from CKV-63-581 to Loop 3 cold leg piping to CKV-63-588. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-588 in the Loop 3 cold leg piping.
- k. Reactor Coolant Loop 3 on Page E-9: Safety injection pump piping from CKV-63-545 to the 8-inch Loop 3 hot leg injection line. Clarify which component in the 8-inch Loop 3 hot leg injection line bounds the end of the piping segment.
- l. Reactor Coolant Loop 3 on Page E-9: Safety injection pump piping from CKV-63-555 to the 6-inch Loop 3 cold leg injection line. Clarify which component in the 6-inch Loop 3 cold leg injection line bounds the end of the piping segment.
- m. Reactor Coolant Loop 4 on Page E-10: Low pressure safety injection from RHR system CKV-63-635 to the 10-inch Loop 4 cold leg injection line. Clarify which component in the 10-inch Loop 4 cold leg injection line bounds the end of the piping segment.
- n. Reactor Coolant Loop 4 on Page E-10: High pressure safety injection piping from the 3-inch common header from CKV-63-581 to Loop 4 cold leg piping to CKV-63-589. Confirm that the component description should be High pressure safety injection piping from CKV-63-581 in the 3-inch common header to CKV-63-589 in the Loop 4 cold leg piping.
- o. Reactor Coolant Loop 4 on Page E-10: Safety injection pump piping from CKV-63-557 to the 6-inch Loop 4 cold leg injection line. Clarify which component in the 6-inch Loop 4 cold leg injection line bounds the end of the piping segment.
- p. Reactor Coolant Loop 4 on Page E-10: RHR piping between FCVs-74-1 and 8 and FCVs-74-2 and 9. The staff recommends that the pipe segment description be broken into two separate entries because it is confusing exactly which flow control valves are the valves that bound the length of the piping segments.