1CAN058409, Forwards Arkansas Nuclear One Unit 1 Reactor Containment Bldg 10-Yr Surveillance. No Abnormal Degradation of Containment Structure Indicated

Forwards Arkansas Nuclear One Unit 1 Reactor Containment Bldg 10-Yr Surveillance. No Abnormal Degradation of Containment Structure Indicated

ML20237C879
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/30/1984
From:	John Marshall ARKANSAS POWER & LIGHT CO.
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20237C867	List: 1CAN058409, Forwards Arkansas Nuclear One Unit 1 Reactor Containment Bldg 10-Yr Surveillance. No Abnormal Degradation of Containment Structure Indicated 1CAN128707, Forwards Info Re Elevated Reactor Bldg Temp & Schedule of Completion of All Committed Actions,Per NRC 871015 Request ML20237C886
References
1CAN058409, 1CAN58409, NUDOCS 8712220236
Download: ML20237C879 (1)

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Cu:; x . ::-1x3 1CAN058409 Mr. John T. Collins Regional Administrator '

O. S. Nuclear Regulatory Commission Region IV--

611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011

SUBJECT:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. OPR-51 ANO-1 Ten Year Tendon Surveillance Report

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Gentlemen:

The purpose of this letter is to transmit the ten year physical tendon surveillance report for the Arkansas Nuclear One - Unit One (ANO-1) primary reactor containment building.

Based on the results of the enclosed ten year tendon surveillance test report, the conclusion is reached that no abnormal degradation of the containment structure is indicated for ANO-1.

Very truly yours, (Y

ohn R. Marshall l

Manager, Licensing JRM: 0ET: sc cc: Mr. D. Powers U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 0

8712220236hO0313 PDR ADOCK PDR P

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[ December 28, 1984 Docket No. 50-313 Mr. John M. Griffin, Senior Vice President of Energy Supply Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203

Dear Mr. Griffin:

We have reviewed the ten year tendon surveillance report for the Arkansas i Nuclear One, Unit 1, reactor containment building as submitted by your letter dated August 1, 1983. We have concluded that the tendon surveillance was in accordance with regulatory requirements and the tendons met the require-ments imposed by the standards. Therefore, the ten year tendon surveillance for ANO-1 is acceptable. Our associated Safety Evaluation is enclosed.

Sincerely,

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Jot n F. Stolz, ' Chief 0 . rating Reactors Branch #4 ,

ivision of Licensing

Enclosure:

Safety Evaluation cc w/ enclosure:

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Arkansas Power & Light Company ' 50-313, Arkansas Huclear' One, Unit 1 -

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Mr. 'J. Ted Enos Manager, Licensing Arkansas Power & Light Company -

Mr. Frank Wilson P. O. Box 551 Director, Division of Environmental Little Rock, Arkansas ' 72203 - Health Protection Department of Health Mr. James M. Levine Arkansas Department of Health General Manager 4815 West Markham Street Arkansas Nuclear One Little Rock, Arkansas 72201 P. O. Box 608 Russe 11vil'e, Arkansas 72801 Mr. W. D. Johnson U.S. Nuclear Regulatory Commission P. O. Box 2090 Russellville, Arkansas 72801 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Nr. Nicholas S. fleynolds d.

iBishop, Liberman, Cook, Purcell & Reynolds 120017th Street, NW Washington, DC 20036 Honorable Ermil Grant Acting County Judge of Pope County Pope County Courthouse Russellville, Arkansas 72801 Regional Radiation Representative EPA Region VI 1201 Elm Street Dallas, Texas 75270 Mr. Robert Martin, Regional Administrator U. S. Nuclear Regulatory Commission, Region IV 611 Ryan Plaza Drive, Suite .1000 Arlington, Texas 76011 D

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[  ;, - NUCLEAR REGULATORY COMMISSION yn I WASHINGTON, D. C. 20S55 N \*****p SAFETY' EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION CONCERNING THE TEN YEAR SURVEILLANCE OF REACTOR BUILDING CONTAINMENT TENDONS FOR ARKANSAS NUCLEAR ONE, UNIT N0. 1 ARKANSAS POWER AND LIGHT COMPANY DOCKET NO. 50-313 INTRODUCTION The prestressed concrete containment for the Arkansas Nuclear One, Unit 1

-(AN0-1) uses a system of tendons to provide.the required compression forces to prevent. leakage in the event of an accident inside the containment. These.

. tendons require periodic inspection to ensure the capability is available if needed. . This inspection is required at the end of one year, three years, five

, years and every five years thereafter. This evaluation concerns the ten year (the fourth) report of the surveillance of the tendons of the ANO-1 reactor

' 0A containment building. The previous three inspections have been reviewed and accepted by the NRC staff.

BACKGROUND i

L The Arkansas containment is a prestressed concrete shallow dome shell which 1 uses 186 - 1/4 inch diameter wire tendons inserted in metal sheaths cast in I the concrete walls and dome. The horizontal tendons encircle 240 degrees of the cylindrical part of the containment and are anchored on each end at two of the three buttresses. The dome tendons are anchored to a large concrete ring cast at the' top of the cylindrical shell. The vertical tendons in the cylindrical section are anchored at the aforementioned ring and the bottom of the containment base mat. The tendons are tensioned to provide a prestressing force of approximately 1400 kips per tendon.

DISCUSSION.

The information pertinent to the ten years tendon surveillance is contained in a report " TEN YEAR PHYSICAL SURVEILLANCE OF THE ARKANSAS NUCLEAR ONE - UNIT 1 PRIMARY REACTOR CONTAINMENT BUILDING", dated August 1, 1983. This report, filed by the licensee, contains copies of the surveillance data and the procedures used in the surveillance. j O

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f h Tendon surveillance is required by the licensee's Technical Specification for plant operation. Inspections are prescribed at periodic, intervals after the

'e initial tendon installation and tensioning. These intervals are at the end of one year, three years, five years, and each five years thereafter. After the third surveillance (five years) inspection, the number of tendons inspected can be reduced, provided the previous inspections were satisfactory and showed nc abnormal tendon deterioration. The licensee has implemented this provision g and.at the recent inspection a total of 13 tendons were inspected: 3 vertical, l' 7 horizontal, and 3 tendons in the dome.

'During the surveillance inspection, the lift-off forces were measured and recorded.in accordance with NRC requirements. As> required, individual wires were removed from three tendons, one from each of the 3 types (horizontal, l .

vertical, and dome). These wires were inspected for deterioration and cut into lengths for strength' testing. Also, samples of the sheath filler L material- (grease) were removed and analyzed as required. The anchorage components were examined for corrosion, cracks, and buttonhead size and condition.

The lift-off forces for the surveillance tendons exceed the projected prestress forces and were less than the upper bound prestress forces. The maximum force measured was tendon ID303 at 1416 kips and the minimum force was tendon 32H44 at 1165 kips. There was no evidence of abnormal degradation of the tendon prestressing forces. The tendons were retensioned to 80% of the tendon ultimate force. Lift-off forces after retensioning were essentially I Q'Q '

the same as the lift off forces at detensioning.

During the inspection of the anchorages it was noted that tendon 32H14 had one wire buttonhead missing from the field end but was present at the shop end.

The shop end button head had a piece of wire wrapped around it. Tendon 32H15 had one wire not buttonheaded at the field end. When tendon 3D102 was lifted off, two of the individual wires broke. This breakage was attributed to the shims between the stressing washer and the containment hearing plate being initially. cocked which led to the wire shearing.

One wire from each tendon 32H44 (horizontal), V73 (vertical) and the two broken wires from tendon 30102 (dome) were removed for inspection and testing.

The removal of one wire from each tendnn type is required. The visual inspection revealed no corrosion on the wires. The wires were cut into individual samples and tested for tensile strength. All wires exceeded the minimum required tensile values of 192 ksi for yield and 240 ksi for the ultimate tensile strength. The minimum yield strength recorded was 222 ksi and the minimum ultimate strength was 258 ksi.

Using standards ASTM 0512 and ASTM D992, the samples of the sheath filter (grease) were analyzed to check for water content, water-soluble chlorides, nitrates and sulfides. The filler material was found acceptable for water content, water soluble chlorides, nitrates and sulfides. One tendon sheath, ,

V73 at the field end, showed a water content of 9.9% which is still within the j acceptable value of 10% while the other tendons and the shop end of sheath V73 lL - showed values of 2% water content or less. Hence, these tests met the acceptance criteria.

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The neutralization test on the grease was performed to the required standard, ASTM, D664. = Additionally, the neutralization test was performed to standards ASTM D974 and ASTM D974 modified. (The ASME Section III, Division 2 code

. (Appendix F) is being revised to require the ASTM D974 modified testing standard. The three ASTM tests were performed to develop a historical base for future reference.) The sheath filler material was acceptable, based upon the results from the three ASTM testing standards.

EVALUATION The ten year tendon surveillance for ANO-1 was performed in accordance with the technical specifications 'and the requirements of Regulatory Guide 1.35, Rev. 2, January 1976. The tendon selection was in accordance with Regulatory Guide 1.35, Section 2.2.1, " Typical containments": three tendons from each of the groups (dome, vertical, and hoop) were selected. The tendon anchorage assembly hardware was visually inspected for abnormal conditions. The surveillance tendons were lifted off to determine the available prestressing forces which then were compared to the required prestress forces. A sample of the tendon wires was removed from each of the tendon groups and tested for material properties. Samples of the sheath filler material were removed and tested for deleterious components.

CONCLUSION The tendon surveillance was in accordance with regulatory requirements and the tendons met the requirements imposed by the standards. Therefore, the ten year tenden surveillance for ANU-1 is acceptable to the staff.

Dated: December 28, 1984 Primary contributor: Harold Polk i

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