IR 05000245/1987016

Insp Rept 50-245/87-16 on 870706-10.No Violations Noted. Major Areas Inspected:Licensee Action on Previous Insp Findings,Licensee Surveillance of Vendor Inservice Insp (ISI) Activities,Review of ISI Data & IGSCC

ML20237H851
Person / Time
Site:	Millstone
Issue date:	08/18/1987
From:	Gray E, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20237H833	List: IR 05000245/1987016 ML20237H830
References
RTR-NUREG-0313, RTR-NUREG-313 50-245-87-16, IEB-82-03, IEB-82-3, NUDOCS 8708250173
Download: ML20237H851 (6)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-245/87-16 Docket N License N DPR-21 Licensee: Northeast Nuclear Energy Company P.O. Box 270 Hartford, Connecticut 06141-0270 Facility Name: Millstone Nuclear Power Station, Unit 1 Inspection At: Waterford, Connecticut Inspection Conducted: July 6-10, 1987 Inspectors: [ h A' [/ / 7, /@ 7 date '

R.A.McBrearty,ReactorEgneer Approved by: V 9 /6 I E 7 E. H. Gray, Acting CMef, Materials date

& Processes Section, EB, DRS

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Inspection Summary: Inspection on July 6 10, 1987 (Inspection Report j No. 50-245/87-16 l

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Areas Ing ected: A routine, unannounced inspection was conducted by one regional based inspector of licensee action on previous inspection findings, licensee surveillance of vendor ISI activities, review of ISI data, augmented i examination program for intergranular stress corrosion cracking, balance of plant erosion / corrosion program, and the ultrasonic measurement of pump boltin Results: No violations were identified.

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8708250173 G70820 PDR ADOCK 05000245 G PDR

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DETAILS Persons Contacted Northeast Utilities E. Abolafia, Engineer

• M. Bigiarelli, Assistant Engineering Supervisor - Unit 1

• C. Clemont, Superintendent - Unit 3 P. Finck, Engineering Specialist R. Fuller, NDE Level III L. Georgian, Engineer

• H. Haynes, Station Servicas Superintendent

• J. Leason, ISI Coordinator - Unit 1

• C. Libby, Supervisor, Assessment Services  !

S. Sikorski, NDE Level III  ;

• R. West, Unit 1 ISI Coordinator - NUSCO

Denotes those present at the exit meeting on July 10, 1987. Licensee Actions On Previous Inspection Findings (Closed) Unresolved Item (245/84-12-02) Correlating automatic and manual ultrasonic data: Ultrasonic indications recorded with the automated UDRPS system appeared to be referenced to a different zero reference than were data collected from the same weld during a manual examinatio Manual and automated data were reviewed and compared by the inspecto The licensee representatives mapped the indications which were recorded by each metnod, and demonstrated that they were referenced to the weld zero reference at the top dead center of the weld. The inspector found that the data were capable of being correlated and this item is considered close . Augmented Examination Program for Intergranular Stress Corrosion Cracking Because of occurrences throughout the industry of intergranular stress corrosion cracking (IGSCC) of BWR recirculation system and associated piping, and in response to NRC IE Bulletins, the licensee has established an inspection program for early detention of IGSCC at Millstone Unit In response to IE Bulletin 82-03 the licensee, in October 1982, sent an inspection team to the Battelle Memorial Institute at Columbus, Ohio, to demonstrate its capability to detect IGSCC in cracked samples taken from the Nine Mile Point Unit 1 facilit Subsequently the requirements have been revised regarding performance demonstrations and personnel qualifi-cation and certification. The inspector found that examination personnel at Millstone have been qualified to requirements which were in effect at the time of the various examinations since 198 ___ __

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. 3 During a March 4, 1987 meeting in Bethesda, Maryland with the NRC Staff, the licensee presented the 1987 IGSCC inspection plan. The 1987 augmented inspection plan was developed in accordance with the guidelines of draf t NUREG-0313, Revision 2. Since the 1985 refueling outage, the licensee has reviewed all the IGSCC inspection data for Millstone Unit Based on this review the welds at the facility were categorized in accordance with the guidelines of draft NUREG-0313, Revision 2. The inspection plan does not take credit for IGSCC inspections performed prior to 1985, and discounts examinations which were performed prior to the implementation of the upgraded 1985 EPRI NDE Center Qualification Progra There are presently 9 welds in the plant which have been repaired with the weld overlay technique, including the 22" diameter recirculation system ring manifold end cep weld which was found to be cracked and was repaired during the current refueling outag The overlay repaired welds are as follows:

Isolation Conderser Weld #ICAC-F-13, 12" diameter Weld #ICAC-F-3, 16" diameter Recirculation System Weld #RRAJ-4, 12" diameter Weld #RR8J-1, 12" diameter Weld #RRBJ-2, 12" diameter Weld #RRCJ-3, 12" diameter Weld #RREJ-3, 12" diameter Weld #RRFJ-1,12" diameter Weld #RMBJ-1, 22" diameter end cap - repaired during current outag The inspector reviewed the licensee's program and found that it meets the guidelines of draft NUREG-0313, Revision 2, and fulfills the licensee's commitment to the NR No violations were identifie . Review of Inservice Inspection ISI Data The inspector reviewed selected da'a to ascertain compliance with ASME l Code and regulatory requirements. Data associated with the following welds were included in the inspector's review:

Reactor Water Cleanup System Weld #CUBJ-12, 8" diameter stainless steel elbow to pipe weld (ultrasonic examination).

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Core Spray System Weld #CSAJ-3-EL, 10" diameter stainless steel elbow longitudinal weld (ultrasonic examination and liquid penetrant examination)

Core Spray System Weld #CSAJ-3, 10" diameter stainless steel pipe to elbow weld (liquid penetrant examination)

Recirculation System weld #RMBJ-1, 22" diameter stainless steel loop

"B" manifold pipe to end cap weld (ultrasonic examination)

Recirculation system weld RMBJ-1 was evaluated by the licensee Level III and found to contain 3 cracks, 1", 4", and 5.1/2" in length respectively, with a maximua thru wall penetration equal to 27% of wail thicknes The individual who measured the thru wall penetration was trained and qualified for this function at the EPRI NDE Center at Charlotte, North Carolina, and is listed on the latest registry published by the NDE Center. The inspector agreed with the licensee's assessment of the wol The licensee intends to repair the cracked weld with the weld overlay technique. The insp9ctor informed NRR of the licensee's proposed repair and was advised that it was acceptabl The data were found to be complete, indications were accurately recorded, and were evaluated by qualified Level III personnel. The inspector found that ASME Code and regulatory requirements were me No violations were identifie . Balance of Plant (BOP) Erosion / Corrosion Program The inspector reviewed the licensee's actions with regard to the detection of erosion / corrosion in plant components. Concern regarding erosion / corrosion in balance of plant piping systems has been heightened

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as a result of the December 9,1986 feedwater line rupture that occurred at Surry Unit This event was the subject of NRC Information Notice 86-106 issued on December 16, 1986, and its supplement issued on February 13, 1987. The inspection was conducted to ascertain the scope of the licensee's program, and the results to dat Af ter system conditions were identified by the licensee, potential problem areas were predicted using Generation Engineering wear models (MIT or EPRI). Based upon plant records INPO reports, NRC information, NUSCO input and plant drawings, inspection plans were developed. The

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l licensee selected 15 locations for its initial sampl Each location is composed of a piping run, and includes a number of specific inspection areas.

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Inspections include remote visual from the pipe I.0. (total length cf piping run when possible), random ultrasonic thickness measurements from the pipe I.D. using transducers which are attached to the crawler, and, additionally, ultrasonic thickness measurements are made from the piping 0.0. on selected area At the time of this inspection the piping inspections were not completed. Results of completed inspections were reviewed at the site and then forwarded to engineering at Corporate Headquarters for final evaluation and dispositio The inspector was advised that, at the time of this inspection, no problem areas were note . Licensee Surveillance of Vendor ISI Activities The inspector reviewed the licensee's actions regarding surveillance of ISI activities performed by its ISI vendo The inspection was conducted to ascertain the adequacy of the licensee's overview of vendor activities, and further, to ascertain that licensee and regulatory requirements were me Reports of 4 surveillance which were done during the ongoing refueling outage were reviewed. The surveillance were done by NUSCO reliability engineering, and covered various aspects of ultrasonic and visual examination activitie Nuclear Engineering and Operations Procedure No. NE0 2.07, Revision 2, entitled " Management of Inservice Inspection Programs" governs ISI surveillance activities, and requires that the NUSCO ISI Coordinator provide personnel to perform surveillance of the technical activities of the examination contractor to ensure adherence to applicable examination procedure The inspector found that the contractor activities were covered by a qualified licensee Level III, and that the scope of the surveillance was broad enough to assess the vendor's performance. Additionally, the inspector found that licensee and regulatory requirements were me No violations were identifie . Ultrasonic Measurement of Pump Hold Down Bolts During the course of this inspection it was brought to the inspector's attention that ultrasonic measurement of LPCI and core spray pump hold-down bolts indicated that 3 of the 4 LPCI pumps and both core spray pumps were installed with improper length bolts. Ultrasonic measurements which were made of the bolts in 1984 indicated that the bolts were shorter than required by design drawings. At that time the licensee considered the ultrasonic data to be inconclusive and took no further action.

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. , 6 Measurements made during the current outage confirmed the 1984 dat This was further confirmed by visual inspection after concrete removal to expose selected bolt At the time the inspector left the site the licensee's investigation was  :

still in progress. The item will be followed by the resident inspector with assistance from the regional office if it is require . Exit Meeting The inspector met with licensee representatives, denoted in paragrarh 1,  ;

at the conclusion of the inspection on July 10, 1987. The inspector summarized the purpose and scope of the inspection and the findings. At no time during this inspection was written material provided by the inspector to the license j

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