ML20153H304

Forwards SE Accepting Util Proposed Alternatives Contained in Requests for Relief 3-SPT-3 & 3-SPT-4 for Second Interval Per 10CFR50.55(a)(3)(i) & Code Case N-546.INEEL TER in Support of Relief Requests Also Encl

ML20153H304
Person / Time
Site:	Browns Ferry
Issue date:	09/28/1998
From:	Hebdon F NRC (Affiliation Not Assigned)
To:	Scalice J TENNESSEE VALLEY AUTHORITY
Shared Package
ML20153H308	List: ML20153H304 ML20153H314
References
TAC-M97805, NUDOCS 9810020004
Download: ML20153H304 (4)

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k UNITED STATES j j NUCLEAR REGULATORY COMMISSION

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o WASHINGTON, D.C. 20555-0001

'% September 28, 1998 [p;yg Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNIT 3 - RELIEF FROM ASME BOILER

. AND PRESSURE VESSEL CODE, SECTION XI REQUIREMENTS: RELIEF

, REQUEST 3-SPT-3 AND 3-SPT-4 (TAC NO. M97805)

Dear Mr. Scalice:

By letters dated January 22,1997, and June 12,1998, the Tennessee Valley Authority (TVA) submitted its second 10-year intervalinservice inspection plan for the Browns Ferry Nuclear Plant, Unit 3 (BFN-3) and associated requests for relief.

Relief Request 3-SPT-3 requests relief regarding the qualifications of personnel performing VT-2 visual examinations. The American Society of Mechanical Engineers Boiier and Pressure Code (ASME Code),Section XI, Paragraph IWA-2300, requires that personnel performing VT-2 visual examinations be qualified in accordance with comparable levels of competency as defined in American National Standards Institute N45.2.6. In accordance with 10 CFR 50.55a(a)(3)(i), TVA has proposed to use Code Case N-546 in lieu of the requirements of Paragra,ph IWA-2300 for VT-2 visual examination personnel.

The staff has reviewed the information submitted regarding TVA's proposed altemative to use Code Case N-546. This Code Case includes the following requirements:

1. At least 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of plant walkdown experience, such as that gained by licensed and nonlicensed operators, local leak rate personnel, system engineers, and inspection and nondestructive examination personnel.

2. At least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of training on Section XI requirements and plant specific procedures for VT-2 visual examination.

3. Vision test requirements of Paragraph IWA-2321,1995 Edition.

In addition to the Code Case requirements, TVA's attemative includes commitments to use procedural guidelines for consistent, quality VT-2 visual examinations, to verify and maintain records of the qualification of persons selected to perform VT-2 visual uxaminations, and to perform independent reviews and evaluations of leakage.

Based on the information provided in support of Relief Request 3-SPT-3, the staff concludes that TVA's proposed attemative to use Code Case N-546 as supplemented by additional TVA

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commitments provides an acceptable level of quality and safety. Therefore, TVA's proposed altemative is authorized pursuant to 10 CFR 50.55a(a)(3)(i). Use of Code Case N-546 is authorized for the second interval or untilit is published in Regulatory Guide 1.147. At that time, use of the Code Case shallinclude limitations, if any, issued in Regulatory Guide 1.147. ,g

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Mr. J. A. Scalice 2 September 28, 1998 lhlitf Rsqu2st 3-SPT-4 requssts rzlitf from ASME Cods, Stction XI, Paragrrph IWA-5250 (a)(2) regarding the visual examination of components and corrective measures if leakage occurs at bolted connections during system pressure tests. ASME Code,Section XI, Paragraph IWA-5250 (a)(2), states, "If leakage occurs at a bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with Paragrapn IWA-3100."

In accordance with 10 CFR 50.55a(a)(3)(i), TVA has proposed an alternative that involves an engineering evaluation of the bolted connection to determine the susceptibility of the bolting to corrosion and potential failure. This evaluation will consider, as a minimum, the location of the leakage, the leakage history of the connection, the fastener materials, evidence of corrosion, with the connection assembled, the corrosiveness of the process fluid, the history and studies of similar fastener material in a similer environment, and other components in the vicinity that may be degraded due to the leakage.

If the evaluation determines that the leaking condition has not degraded the fasteners, then no further action is required, other than reasonable attempts to stop the leakage. If the evaluation indicates the need for further evaluation, or if no evaluation is performed, then a bolt closest to the source of leakage shall be removed, VT-1 examined and evaluated for corrosion in accordance with Paragraph IWA-3100(a), and dispositioned in accordance with Paragraph IWB-3140. When the removed botting shows evidence of rejectable degradation, all remaining bolts in the connection shall be removed and receive a VT-1 examination and evaluation in accordance with Paragraph IWB-3140.

Based on the information provided for Relief Request 3-SPT-4, the staff concludes that TVA's proposed attemative examination and corrective measures provide an acceptable level of quality and safety. Therefore, TVA's proposed alternative is authorized for the second interval at BFN-3 pursuant to 10 CFR 50.55a(a)(3)(i).

The staff's safety evaluation and conclusions are contained in the Enclosure. Attached to the Enclosure is the INEEL Technical Letter Report.

Sincerely, Original signed by Frederick J. Hebdon, Director Project Directorate ll-3 Division of Reactor Projects - l/Il Office of Nuclear Reactor Regulation Docket No. 50-296 Serial No. BFN-98-021

Enclosure:

Safety Evaluation cc w/ enclosure: See next page DISTPJBUTION

• Doeket Mer BChyton THarris (e-mail SE, TLH3)

PUBLIC OGC GHill (2)

JZwolinski ACRS MTschiltz FHebdon LPlisco, Rll TMcLellan ADeAgazio BFN r/f DOCUMENT NAME: G:\BFN\97805.WPD

• see previous concurrence To receive a copy of this document, Indicete in the box: "C" = Copy without attachrnent/ enclosure "E" = Copy with attachrnent/ enclosure *N" = No copy A/

W OFFICE PDil-3/PM [/{F l PDil-3/LA ,j OGC' l PDil-3/D .)

NAME ADeAgazio:cn BCLwton /V FHebdon hf DATE o9/M/98 09/1) /98 09/ 0 /98 09/fff98 OFFICIAL RECORD COPY a

Mr. J. A. Scalice 1 l

Relief request 3-SPT-4 reque'sts relief from ASME Code,Section XI, Paragraph IWA-5250 (a)(2) regarding the visual examination of components and corrective measures if leakage occurs at l bolted connections during system pressure tests. ASME Code,Section XI, Paragraph IWA-5250

[ (a)(2), states, "If leakage occurs at o bolted connection, the bolting shall be removed, VT-3 visually examined for corrosion, and evaluated in accordance with Paragraph IWA-3100."

In accordance with 10 CFR 50.55a(a)(3)(i), TVA has proposed an attemative that involves an engineering evaluation of the bolted cc'inection to determine the susceptibility of the bolting to corrosion and potential failure. This evaluation will consider, as a minimum, the location of the leakage, the leakage history of the connection, the fastener materials, evidence of corrosion, with the connection assembled, the corrosiveness of the process fluid, the history and studies of similar fastener material in a similar environment, and other components in the vicinity that may be degraded due to the leakage.

If the evaluation determines that the leaking condition has not degraded the fasteners, then no further action is required, other than reasonable attempts to stop the leakage. If the evaluation indicates the need for further evaluation, or if no evaluation is performed, then a bolt closest to the source of laakage shall be removed, VT-1 examined and evaluated for corrosion in accordance wnh Paragraph IWA-3100(a), and dispositioned in accordance with Paragraph IWB-3140. When the removed bolting shows evidence of rejectable degradation, all remaining bolts in the connection shall be removed and receive a VT-1 examination and evaluation in accordance with Paragraph IWB-3140.

Based on the information provided for Relief Request 3-SPT-4, the staff concludes that TVA's proposed attemative examination and corrective measures provide an acceptable level of quality and safety. Therefore, TVA's preposed alternative is authorized fo the second interval at BFN-3 pursuant to 10 CFR 50.55a(a)(3)(i).

The staffs safety evaluation and conclusions are contained in the Enclosure. Attached to the Enclosure is the INEEL Technical Letter Report.

Sincerely, s f Frederick J. Hebdon, Director Project Directorate 11-3 Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation Docket No. 50-296 l

Serial No. BFN-98-021 l

l

Enclosure:

Safety Evaluation

, cc w/ enclosure: See next paga l

h'.

l Mr. J. A. Scalice BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority ,

l l

cc:

Senior Vice President Mr. Mark J. Burzynski, Managar l Nuclear Operations Nuclear Licensing l Tennessee Valley Authority Tennessee Valley Authority i 6A Lookout Place 4X Blue Ridge '

1101 Market Street 1101 Market Street l Chattanooga, TN 37402-2801 Chattanooga, TN 37402-2801 '

l Mr. Jack A. Bailey, Vice President Mr. Timothy E. Abney, Manager Engineering & Technical Services Licensing and Industry Affairs l Tennessee Valley Authority Browns Ferry Nuclear Plant l 6A Lookout Place Tennessee Valley Authority l 1101 Market Street P.O. Box 2000 i Chattanooga, TN 37402-2801 Decatur, AL 35609 l l

Mr. C. M. Crane, Site Vice President Regional Administrator, Region 11 Browns Ferry Nuclear Plant U.S. t.'uclear Regu'-tory Commission Tennessee Valley Authority 61 Forsyth Street, SW., Suite 23T85 P.O. Box 2000 Atlanta, GA 30303-3415 Decatur, AL 35609 Senior Resident inspector l General Counsel U.S. Nuclear Regulatory Commirsion l Tennessee Valley Authority Browns Ferry Nuclear Plant ET 10H 10833 Shaw Road '

400 West Summit Hill Drive Athens, AL 35611 Knoxville, TN 37902 State Health Officer Mr. Raul R. Raron, General Manager Alabama Dept. of Public Health Nuclear Assurance 434 Monroe Street Tennessee Valley Authority Montgomery, AL 36130-1701 5M Lookout Place 1101 Market Street Chairman Chattanooga, TN 37402 2801 Limestone County Commission 310 West Washington Street Mr. Karl W. Singer, Plant Manager Athens, AL 35611 Browns Ferry Nuclear Plant Tennessee \ alley Authority P.O. Box 2000 Decatur, A'. 35609