ML20041G547

Summary of 820127 Meeting in Bethesda,Md W/Util Re Steam Generator Eddy Current Insp Interval

ML20041G547
Person / Time
Site:	Point Beach
Issue date:	03/05/1982
From:	Colburn T Office of Nuclear Reactor Regulation
To:	Clark R Office of Nuclear Reactor Regulation
References
TAC-48122, NUDOCS 8203220506
Download: ML20041G547 (11)

Text

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.L 0 MAR 5 1982 Q(4 /M - C /b

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Division of Licensing

. [ /f/;g2 71934 q WCEtyED plMORANDUM FOR: Robert A. Clark, Chief Operating Reactors Branch #3

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Timothy G. Colburn, Project Manager Operating Reactors Branch #3 8

Division of Licensing 4

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SUBJECT:

Summary of January 27 Meeting with Wisconsin Electric Power Company to Discuss Point Beach Unit 1 Steam Generator Eddy Current Inspection Interval In response to the NRC staff's December 30, 1981 letter, T. M. Novak to Sol Burstein, Wisconsin Electric Power Company (WEPCO) requested a meeting with NRC staff to discuss WEPCO's proposed eddy current inspection interval for Point Beach Unit 1 Steam generators. This meeting was held on January 27, 1981 in Dothesda, Maryland. The meeting agenda and list of attendees are attached.

T53 NP? staff's December 30, 1981 letter took exception to WEPCO's proposed

" full cycle" eddy current inspection interval for Point Beach Nuclear Plant Unit 1 steam generators. The staff strongly recommended that a mid-cycle eddy current inspection be conducted on Point Beach Unit 1 steam generators.

At the meeting with the MRC staff, WEPCO presented additional data concerHgg the rate of corrosion they feel exists in the Unit 1 steam generators. A copy df this data is attached.

The meeting began with a comparison, by WEPCO, of the recent steam generator tube rupture at the R. E. Ginna Nuclear Plant to the steam generator rupture that occurred in the Point Beach Nuclear Plant Unit 1 steam generators in 1975.

Next, the NRC staff reviewed the history of the licensing actions taken it Point Beach 1 to help correct steam generator corrosion problems. These included Confirmatory Orders for Modification of License dated November 1979, January 1980, and April 1980 which placed more restrictive leakage limit on the Unit 1 steam generators, reduded reactorscoolant system radioactivity level limits, reduced primary system operating pressure and increased the frequency of stean generator eddy current inspections. Xt'the time these Orders were issued, WEPC0 also voluntari}y reduced hot leg temperature and conducted crevice flushing and sludge removal operations in an effort to reduce the corrosion rate. These efforts proved to be effective rJ1.though the relative effect of each in reducing the corrosion rate cannot be deter-mined.

8203220506 920303 PDR ADOCK 05000266 0

PDR omcap SURNAME) omy NHC FOHM 318 00M NHCM 0ao OFFICIAL RECORD COPY usc.

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. 1 In July 1981, WEPC0 raised the hot leg temperature to 575' F, which is approximately half-way between the original hot leg temperature and the reduced hot leg temperature they chose in 1979. Prior to this action, eddy current inspection results since November 1979 had showed a continuing decrease in the corrosion rate for the Unit 1 steam generators which provided adequate basis for reducing the frequency of eddy current inspections to once per 150 effective full power days (EFPD).

The staff's review of the October 1981 Unit 1 eddy current inspection results indicated that the rate of corrosion was no longer decreasing and may even n

be increasing as a result of raising the hot leg temperature. This was a chief concern in the staff's December 30, 1981 letter, WEPC0 stated that the NRC staff may have misinterpreted the data contained in the LERs describing the results of eddy current inspections of the Point Beach Unit 1 steam generators. WEPC0 stated that their interpretation of the data indicated that the rate of corrosion in Unit 1 had leveled off and was neither increasing nor decreasing.

Further evidence, UEPC0 maintained, lay in the fact that relatively small amounts of sludge being removed fromtthe Unit 1 steam generators by flushing and lancing indicates that few corrosion particles are present as compared to pre-1979 levels.

WEPC0 also stated that although primary to secondary leakage in the Unit 1 steam generators has increased slightly since raising their hot leg temperature it has leveled off well below the leakage limits imposed by the November 1979 Confirmatory Orders. Were it to continue to increase, they would plan to shut down and investigate the cause, presumably in mid-cycle, even if the leakage were still well below the allowable limits. However, WEPCO would like to maintain the operating flexibility of a full cycle inspection interval so long as conditions within the steam generators do not indicate the need for a nore frequent inspection interval.

WEPC0 next stated its plans to conduct a full scale sleefing of the Unit 2 steam generator tubes during the Spring 1983 refueling outage.

The NRC staff made no decision on the eddy current inspection' interval for the Unit 1 steam generators but promised to review the data presented by WEPC0 and promulgate its decision at a later date.

Origiruil adpad by:

Timothy G. Colburn, Project Parager Operating Reactors Branch #3 Division of Licensing

Enclosures:

As stated ORB,#3, ORB #3 ORB #3 Mrnh a

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OFFICIAL RECORD COPY usam

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4 MEETING SUtdARY DISTRIBUTION i

Licensee:

'a'isconsin Electric Power Company

• Copies also sent to those people on service (cc) list for subject plant (s).

1, Docket File 3

NRC' PDR L POR NSIC TERA j

ORBe3 Rdg JHeltemes j

BGrires RAClark Project f: tanager 4

PMKreutzer OELD ILE ACRS-10 ORE #3 Summary File NRC Participants i

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Wisconsin Electric Power Company cc:

Mr. Bruce Churchill, Esquire Mr. William Guldemond Shaw, Pittman, Potts and Trowbridge USNRC Resident Inspectors Office 1800 M Street, N. W.

6612 Nuclear Road.

Washington, D. C.

20036 Two Rivers, Wisconsin 54241 Joseph Mann Library Peter B. Block, Chairman 1516 Sixteenth Street Administrative Judge Two Rivers, Wisconsin 54241 Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission Mr. Glenn A. Reed, Manager Washington, D. C.

20555 Nuclear Operations Wisconsin Electric Power Company Dr. Hugh C. Paxton Point B~each Nuclear Plant Administrative Judge 6610 Huclear Road 1229-41st Street Two Rivers, '.lisconsin 54241 Los Alamos, New Mexico 875d4 Mr. Gordon Blaha Dr. Jery R. Kline Town Chairman Admi1nistrative Judge Town of Two Creeks Atomic Safety and Licensing Board Route 3 U.St-Nuclear Regulatory Commission Two Rivers, Wisconsin 54241 Washington, D. C.

20555 Ms. Kathleen M. Falk Francis X. Davis General Counsel P. O. Box 355 Wisconsin's Environmental Decade Pittsburgh, PA 15230 114 N. Carroll Street Madison, Wisconsin 53703 Mr. C. W. Fay Assistant Vice President U* S. Environmental Protection Agency Wisconsin Electric Power Company Federal Activities,eranch 231 West Michigan Street Milwaukee, Wisconsin 53201 Region V Office ATTN: Regional Dadiation Representative

- 230 S. Dearborn Street Chicago, Illinois 60604 1

j Chairman j

Public Service Comnission of Wisconsin j

Hills Farms State Office Building

,i Madison, Wisconsin 53702 hj Regional Administrator H

Nuclear Regulatory Commissicn, Region III

,i Office of Executive Director for Operations

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799 Roosevelt Road Glen Ellyn, Illinois 60137 i

M AGENDA POINT BEACH NUCLEAR PLANT, UNIT 1 STEAM GENERATOR INSPECTION INTERVAL JANUARY 27, 1982 l

1.0 Introduction and Purpose

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Progression of Crevice Corrosion

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2.0 2.1 Experience prior to July 1981 I

2.2 Experience since July 1981 h

l Bases for Proposing Full Cycle Opefa' tion i

3.0 I

i 3.1 Leakage History 3.2 Comparison of LER data 3.3 Apparent rate of corrosion 3.4 Crevice cleaning experience 4.0 Future Plans for Unit 1 Near-term temperature limitations 4.1 Calorimetrics of various power levels 4.2 Steam generator inspection in fall 1982

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LIST OF ATTENDEES NRC WEPC0 WESTINGHOUSE T. Novak S. Burstein J. Esposito G. Lainas D. Porter C. Hirst W. Johnston G. Frieling R. A. Clark B. Churchill S.'Pawlicki G. Holahan C. Cheng f.

E. Murphy T. Colburn C. McCracken R. Bachman

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_...s UtJIT 1 POINT DEACIIt1UCLEAR PLANT,

SUMMARY

OF CREVICE ItJDICATIO!1S

• AFTElt ADJUSTMEllT FOR TIME OF FIRST DETECTIOt{

STEAM GEt1ERATOR A Cumulative Total fiable 100%_

90-99%

80-89%

70-79%

60-69%

50-59%

<50 Total Unidenti-Outage Prior to and

• August 1979 4

8 20 28 6

2 1

69 69 including 2

1 38 30 13 4

2 10 100 169 December 1979 7

1 7

2 2

8 27 196 October 1979 March 1980 3

4 6

4 4

4 6

31 227 3

8 5

3 9

5 33 260 2

16 276 July 1980 December 1980 13 1

1 1

9

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2 4

4 289 July 1981 1

1 2

October 1981

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n STEAM GENERATOR B Prior to and 51 51 August 1979 1

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4 including October 1519 4

2 27 19 16 6

3 14 91 142 19 161 December 1979 2

1 4

8 3

1 4

3 1

5 4

20 181 March 1980 2

1 2

1 2

10 8

10 2

1 36 217 219' 2

July 1980 December 1980 1

1 1

F 224 July 1981 3

227 October 1981 1

1 1

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d STEA!4 GEllEHATOR I.EAKAGE IIISTORY P iil t1T lili A C l! 11 U C I.E A R P I.A N T, Ut31T 1 STEAM GENERATOR B Prior STEAM GEtJERATOR A_

Date of I.eak I.ea ki ng Leaking Wet Leaking Leaking Wet Shutdown Rate Tubes Plugs Plugs Tubes __

Plugs Plugs (9P'l) 12/79 (1) 0 0

0 1

2 0

3/80 20-34 0

0 0

1 0

1 7/80 10-20 0

2 2

1 0

1 2

0 0

2 11/80 4-10 0

0 7/8'l 4-6 0

3 3

0 1

2 10/81 s-lo 0

0 0

0 1

2 Present 10-20

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( 1) Forced outage due to tube leak.

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COMPARISON OF EDDY CURRENT SIGNAL CHANGES FOR TUBES WITH HOT LEG INDICATIONS IN OCTOBER 1981tAJ

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October 1981 Compared To July 1981(2)

At Or Above Tubesheet Crevice l

Change No Change Change No Change

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Steam Generator A 2

4 10 14 I

Steam Generator B 0

3 3

5 4

l TOTAL 2

7 13 19 4

July 1981 Compared to December 1980(2, 3) i j

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15 6

l Steam Generator A 1

Steam Generator B 1

2 3

2 TOTAL 2

6 18 8

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(1) Based upon data provided in LER 81-017/OlT-0

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(2) One tube not tested in July 1981, steam generator A.

(3) Four tubes in steam generator A and three tubes in steam generator B showed no defects, A g;y4,r fy.,jfec4 w,

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