ML19257A359
| ML19257A359 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 11/30/1979 |
| From: | Case E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19257A240 | List: |
| References | |
| NUDOCS 8001030815 | |
| Download: ML19257A359 (5) | |
Text
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7509-01
- 11TED STATES OF AMERICA NL' CLEAR REGULATORY COMMISSION In the Matter of
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WISCONSIN ELECTRIC POWER COMPANY
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Docket No. 50-266 (Point Beach Nuclear Plant,
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Unit 1)
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';r::v: ::V C :E: ::: M::: 7::r: CN 0: L::ENSE I
Wisconsin Electric Power Company (the licensee) is the holder of Facility Ooerating License No. DPR-24 which authorizes the licensee to operate the Point Beach Nuclear Plant, Unit 1, located in Two Creeks, Wisconsin, under certain specified concitions. License No. OPR-24 was issued by the Atomic Energy Corrission on October 5,1970 and is due to expire en July 25, 2008.
II Inservice inspections of the Point Beach Unit 1 steam generators per-fomed during the August 1979 and October 1979 outages indicated extensive general intergranular attack and caustic stress corrosion cracking on certain of the external surfaces of the steam generator tubes. As a result of infoma-tion provided in discussions with the licensee and its representatives, which 1s documented in a letter dated November 23, 1979 from S. Burstein to H.D.
Denton, and the Staff's Safety Evaluation Report, dated November 30, 1979, on Point Beach Unit 1, Steam Generator Tube Degradation Due to Deep Crevice Corrosion, it was detemined that additional operating conditions would be required to assure safe operation prior to resumption of operation of Unit 1 from the current refueling outage.
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'2-7509-01 III The licensee in letters dated November 29 '979 and November 30,1979 has agreed to additional conditions which are necessary to provide reasonable assurance for safe operation of Unit 1 for a period of 60 effective full power days.
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After review of the Licensee's comitment, it has been dete mined.that this comi=ent should be femalized by order. Accordingly, pursuant to the Atomic Energy Act of 1951., as amended, and the Comission's Rules and Regula-tions in 10 CFR Parts 2 and 50 IT IS HERE3Y ORDERED THAT the above license be ame".dec, in tre manner hereinafter provideo,to include the following concitions:
1.
a)
'.'itnin 30 effective full power days, a 2,000 psid primary to seconcary hydrostatic test and a 800 psid secondary to primary hydrostatic test will be perfomed. Should any significant leakage develop as a result of either test, the leaking tubes will be identified and plugged.
b) Witnin 60 e#fective full power days, the same primary to secondary and secondary to primary hydrostatic tests will be repeated, and an eddy current examination of the steam generator tubes will be perfomed.
This eddy current program will be submitted to the NRC for Staff review.
l 2.
Primary coolant activity for Point Beach Nuclear Plant Unit.1 will be limited in accordance with the provisions of sections 3.4.8 and 4.4.3 of the Standard Technical Specifications for Westinghouse Pressurized Water Reactors, Revision 2 July 1979, rather than Technical Specification
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7509-01 3.
Close surveillance of primary to secondary leakage will be continued and the reactor will be shut down for tube plugging on detection and confirma-
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tion of any of the following conditions:
a) Sudden primary to secondary leakage of 150 gpd (0.1 gpm) in either stear generator; b) Any primary to seconcary leakage in excess of 250 gpd (0.17 gpm) in either steam generator; or c) An upward trend in primary to secondary leakage in excess of 15 gpd (0.01 g;m) per day, when reasured primary to seconcary leakage is above 150 goc.
4 The reactor will be shut down, any leaking steam generator tubes plugged, and an eady current examination performec if any of the following conditions are present:
a) Confirmation of primary to secondary leakage in either steam generator in excess of 500 gpd (0.35 gpm); or, b) Any two identified leaking tubes in any 20 calendar day period.
This eddy current program will be submitted to the NRC for Staff review.
5.
The NRC Staff will be provided with a sumary of the results of the eddy current examination perfonned under items 1 and 4 above, including a descrip-tion of the quality assurance program covering tube examination and plugging.
This sunnary will :nclude a photograph of the tubesheet of each steam generator which will verify, the location of tubes which have been plugged.
6.
The licensee will not resume operation after the eddy current examinations
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required to be perfonned in accordance with condition 1(b) or 4 until the Director, Office of Nuclear Reactor Regulation determine in i iag h the results of such tests are acceptable.
7.509-01.
7.
The licensee will complete a review of Emergency Operating Procedure 3A, Revision 9, dated March 29, 1978, confirm that this procedure is appro-priate for use in the case of a steam generator tube rupture, and have com-oleted a retraining program for all licensed reactor operators and senior reactor coerators in this procedure before return to power.
8.
Unit I will not be operated with more than ISP. of tubes plugged in either steam generator.
V Copies of the above referenced dc;uments are availacle for inspection at the Comr.ission's Public Document Room at 1717 H Street, N.W., Washington, D.C.
20555, and are being placed in the Commission's local public document room at Document Department, University of Wisconsin.Stevens Point Library, Stevens Point, Wisconsin 54451.
VI Any person whose interest may be affected by this Order may within twenty days of the date of this Order request a hearing with respect to this Order.
Any such request shall not stay the effectiveness of this Order. Any request for a hearing shall be addressed to the Director of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555.
In the event a bearing is requested, the issues to be considered at such hearing shall be:
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7509-01 1) Whether the facts stated in Section II and III of this Order are correct; and.
- 2) Whether this Order should be sustained.
FOR THE NUCLEAR REGULATORY COMMISSION
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P l"
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3 tascn u. Case, Actin 9 'irec:cr Cffice of Nuclear Rea::or Replation
Attachment:
Staff Safety Evaluation Report, dated November 30, 1979 Effective date: Novetcer 30, 1979.
Be:nesca, Marylanc.
185l 139
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,o 5,,,4 SAFETY EVALUATION REPORT RELATED TO POINT BEACH UNIT 1 STEAM GENERATOR TUSE DEGRADATION DUE TO DEEP CREVICE CORROSICN INTRODUCTICN Inservice inspections of the ?oint Beach 'Jnit 1 steam generators per#crmed during the August 1979 and October 1979 outages indicate extensive general intergranular attack (!GA) and caustic stress corrosion cracking on the external surfaces of the stean generator tubes within the tnickness of the tube sheet.
This condition appears to have developed rapidly during the last twelve (12) nonths as evidenced by small primarf to secondarf generator tube leaks occurring on September 20, 1978 and March 1, August 5, and August 29, 1979. Ninety-seven (97) tubes were plugged as a result of the August 1979 inscection, and 145 tubes were plugged as a result of the October 1979 inspection. Of the 145 tubes plugged in the October inspection,134 tubes were deemed defective due to the crevice corrosion phenomenon.
Following the October 1979 inspection, the NRC staff met with representatives of Wisconsin Electric Power Company (the licensee) and their Westinghouse con-sultants on November 5, and again on November 20, 1979 to discuss the opera-tional experience at Point Beach Unit I and the present condition of the steam generators. This included a discussion of the Point Beach Unit 1 operating history, results of the August and Oc results of laboratory examinations of Entire document previously outage, laboratory tests and calculat entered into system under.
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