IR 05000395/1987022

Insp Rept 50-395/87-22 on 870723-24.No Violations or Deviations Noted.Major Areas Inspected:Plant Chemistry

ML20237J117
Person / Time
Site:	Summer
Issue date:	08/07/1987
From:	Kahle J, Ross W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20237J114	List: IR 05000395/1987022 ML20237J111
References
50-395-87-22, IEIN-86-106, NUDOCS 8708170491
Download: ML20237J117 (4)

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maatou UNITED STATES jo NUCLEAR REGtlLATORY COMitilSSION y -

( REG lONtl y j 101 MARIETTA STREET, N.W.

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• • • • • AllR 4 f MR7 Report No.: 50-395/87-22 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.: 50-395 License No.: NPF-12 Facility Name: Summer Inspection Conducted: July 23-24, 1987 Inspector-p .

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Accompanying Personnel: C. A. Hughey J. B. Kahle Approved by: WAkdd J. B. Kphle, Section Chief k/7/r 7 Date / Signed Divis(en of Radiation Safety and Safeguards SUMMARY Scope: This routine, unannounced inspection was conducted in the area of plant chemistr Results: No violations or deviations were identifie !

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REPORT DETAILS t

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s Persons Contacted '

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3 4 0. Bradham, D'trector, Nuclear Plant Operatidos j >

• J. Skolds, Group Mai1ager, Operations , 1 ,

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> *M. Browne, Group Manager,' Technical Suppot'; Servico)

• A. Koons, Manager, Technical Support s ig

• F. Bacon, , Associate Manager, Chemistry I

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R. Burch,- Chemistry Supervisor i L. CMHer, Welding Supervisor .' ,

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• A. Ct% b, Plant Chemist ,\

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iT. Effinger, Engineer, fo% orate TechnicaS Services ,

t 14 Frick, Supervisor, Performance Engineering .

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P. Troy, Steam Generator 1.yject Manager Nucl' ear Regulatory Commission y

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Prevatte, Senior Res'&ar:.a.Inspe jdor '( $;'/\

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• P. HopRins, Resident InspEctort

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'The inspection scopt nd finoings were summarized on July 24, 1987, with those persons indich.ed id Paragraph 1 above. %e inspector described the i areas inspected an:/ 'diiscussed the inspection findings. No dissenting comments were i rectRed from the licensee. The licensee did not identify as proprietyf.fr.ny K the :naterial t9ftided to^ or reviewed by the inspector dsr,ing this inspection, r

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, LicenseeActiononPreviousEnforcemd$ Matters' a <

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Thissubject.wasnotaddressedintheinsp4ctinh' '

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~ Plant Chemistry (79 01) ,

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lM This abbreviated inspection was performed for the'following purposes: to

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[d . review the degree to which the licensee had maintained the integrity of ,

j i the l tubesp)rimary since coolant pressure bockfary the last inspection ,in this area (especitlly in January the 1985steamand generatorto i reitiew actions bei g taken by the iicensee in response to IE Notice 86-106 related to pipe wall thinnin ,

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At the91pe of th1s inspbction, the Summer unit was operating at 100%

power lbi thi ,second month of its fourth \ fqel cycle. Through an audit of

) _/ operationailand chemistr3 dcta, the inspet. tor concluded that the third

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fuel cycle had been ralatively stable and the level of chemistry control continued to significantly exceed tha criteria recommended by the Steam Generator Owners Group (SGOG). However, chemistry control during several months had been complicated by the continual leakage of a total of 50 to 150 gallons of oil into the secondary water system. The source of the oil leak was eventually identified as a crack in the boot seal in "A" feedwat.er pump condense Although the presence of oil throughout the secondary water system affected measurements of conductivity and total organic carbon, the licensee did not identify any corrosive environments caused by the oil itself or by cleansing agents (e.g., sodium phosphate)

that were used to remove oil contaminatio Integrity of Steam Generators The principal problem related to the integrity of the steam generators continued to be primary side stress corrosion cracking of the steam generator tubes (see Inspection Report No. 50-395/86-01 dated February 11, 1986). Additional degradation of tubes within the tube sheet region resulted in further plugging of 269 tubes during the March-April 1987 refueling outage. However, reanalysis of earlier eddy current test data allowed the licen ee to remove the plugs from 24 tube Because of the large number of indications of primary side stress corrosion the licensee had continued to try to reduce stress levels within the tube sheet and in the "U" bend region by shot peening and annealing procedures. In addition, the Technical Specifications relating to steam generator tube inspections had been amended to recognize' the differences in integrity of a tube based on the depth of a crack below the face of the tube sheet or below the top of the lowest hardroll of tube to tube sheet. A distance of 1.6 inches had been established as the minimum depth for this F* distance; i.e., a crack below this depth was to be considered less a hazard to safety than a crack within the F* distance. The inspector was informed that based on ttle F* analysis, the licensee had been forced to plug approximately 5% of the 4674 tubes in "B" steam generator and about half as many in each of the other steam generator During the recent refueling outage "C" steam generator was sludge lanced for the first time in three year A relatively small amount of iron oxide (approximately 24 pounds) was removed, thus indicating chemistry control was continuing to prevent oxidation and wastage of carbon steel pipe in the low and high pressure regions of the power l and steam conversion system These exemplary conditions resulted, in part, from the effectiveness of the secondary coolant system in preventing ingress of corrosive i impurities. The inspector also observed that the licensee had l upgraded its inservice inspection program to minimize '

erosion / corrosion by macro- and micro-biological species in the raw service water and condenser cooling water. The inspector considered

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that chemistry was being controlled well' because of increased experience of the chemistry staff, especially in the implementation of the Steam Generator Owners Group (SG0G) guideline The inspector considered the return of the Plant Chemist to active participation on the chemistry staff to be a positive action take during the past year. On the negative side, the inspectors were informed that, in addition to bypassing the condensate polishers when power level was greater than 50%, during the past year difficulties had been encountered in the use of these polishers during unit startup, primarily due to design difficulties that affected precoating schedule b. IE Notice 86-106 The inspector reviewed the actions being taken by the licensee in .

response to IEN 86-106 and supplements relative to the .feedwater pipe rupture at the Surry Nuclear Station in December 1986. Upon receipt of this Notice the licensee had identified 115 fittings that were considered to be vulnerable to erosion / corrosio However, after ultrasonically testing the thickness of these fittings all.were found to be within mill tolerance. Two heater drain lines were replaced 1 because of evidence of wea !

Plans were underway to revise the ISI program to include pipes in j single phase-(water) systems, so that during the ten year program i approximately 800 additional fittings, with multiple inspection areas and points, would be examine I

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