IR 05000289/1977010
| ML19256D340 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/29/1977 |
| From: | Haynes R, Mcbrearty R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D327 | List: |
| References | |
| 50-289-77-10, NUDOCS 7910170844 | |
| Download: ML19256D340 (12) | |
Text
{{#Wiki_filter:..__ .. _ _.. _._ .- . . Reg I Form 12 (Rev Feb 77) U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
IE Inspection Report No: 50-289/77-10 Docket No: 50-289 2 Licensee: Metrocolitan Edison comoany License No: DPR-50 p_ n Any 54? Priority: -- Reading, Pennsylvania 19603 Category: C ,
' Sa feguards -- Location: Middletown. Pennsylvanis (Three Mile Island 1) Type of Licensee: pWR. 2535 MWt Type of Inspection: Routine. Announced i ' Dates of Inspection: March ?? 24.1977. March 29-29.1977. and i April 5-8, 1977 ! Dates of Previous Inspection: 14 arch 21-24,1977 h 6 Reporting Inspector: d f/ ZP/77 R. A. McBrearty, Reactfr Inspector DATE Accompanying Inspectors: NONE , DATE ' i i ' OATE
DATE DATE Other Accompanying Personnel: NONE DATE [[h /77 Reviewed Sy: / - u R.C.Haynes,C64f,EngineeringSupportSection /DATE , Reactor Construction and Engineering Support Branch ry 910179, ' ._ . .
.. - -. -.. -. . - -. . . . e-i, , ' SUMMARY OF FINDINGS I Enforcement Action None.
I Licensee Action on Previously Identified Enforcement Items ! Not inspected.
. Design Changes , None identified.
Unusual Occurrences None reported.
Other Significant Findinas l A.
Current Findings () 1.
Acceptable Areas a.
Let-Down Cooler Welds l The licensee's plans to install and inspect new let-down ' cooler welds were reviewed and found to be acceptable.
(Details, Paragraph 10) b.
Inservice Inspection Inspection of the implementation of the licensee's in-service inspection program by his contractor (Conam), including data review and witnessing of in-process non-destructive examinations, showed this work was acceptable.
(Details, Paragraphs 3, 4, 5, 6, 7, 8, and 10) 2.
Unresolved Items 77-10-01 - Auemented Inservice Insoection Ultrasonic examinations of pipe welds in the Reactor Building Spray System were done using a technique which did not identify the test frequency.
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' i B.
Status of Previously Reported Unresolved Items Not inspected.
C.
Deviations
None. identi fied.
Management Interview . At the conclusion of the inspection, the inspector held a meeting at the site to discuss the results of the inspection. Attendees at this meeting included those personnel whose names are highlighted (i.e. *) in paragraph 1 of the Details section of this report.
The inspector summarized the purpose and scope of the inspection and the results of the inspection as listed in Details paragraphs 2 through 10.
The licensee acknowledged the inspector's findings.
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t j, . ! j DETAILS
l.
Persons Contacted ' ! Metropolitan Edison Company i R. Barley, Lead Mechanical Engineer, Unit 1 l J. Colitz, Unit 1 Superintendent
W. Cotter, Supervisor - Quality Control ! J. Hall, Inservice Inspection Coordinator
J. Principe, Quality Control Assistant i Conam Inspection R. Marlow, Manager N. Munoz, NDE Level II , M. Zeise, NDE Level II i l Hartford Steam Boiler Inspection and Insurance Comoany N. Lynch, Authorized Inspector C - 2.
General A preinspection meeting was held at the site on March 22, 1977, ' with Mr. J. Colitz to discuss the scope of the inspection and work in progress which may bear upon the inspection. The inspec-tion was held to review the licensee's inservice inspection activities.
3.
Inservice Insoection (ISI) Program i l The inspector audited the licensee's ISI Program which was eveloped for the March 19,1977 - April 1977 refueling outage.
'inis is the first inspection interval of the ISI Program.
i The inspector reviewed the following documents to ascertain the adequacy of the program and its compliance with the require-ments of the ASME Boiler and Pressure Vessel Code, Section XI, 1970 Edition through Winter 1970 Addenda.
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. m, t Conam Inspection Division Quality Assurance Program 99 QAP-001, Revision 2, dated April 29, 1975.
Three Mile Island Unit 1 Inservice Inspection Program dated July 1,1975.
Three Mile Island Unit 1 Procedure 1300-1, Revision 2, dated August 30, 1976, entitled " Inservice Inspection Program."
l Three Mile Island Unit 1 Technical Specification 4.2 - Reactor Coolant System Inservice Inspection.
' The above listed documents contain provisions and requirements , ' for the administration, control, And execution of the examina-tions which will be performed during the ongoing outage.
! l No discrepancies in documented program requirements were identi- ! fled by the inspector.
4.
Nondestructive Examination Personnel Certification , Tiis inspector reviewed qualification records for those Conam insper. tion personnel scheduled to perform nondestructive examina-(] tions cering the ongoing outage.
! The records Indicated the nondestructive examination technique for which the individual was certified, the level of certifica-tion, the date of certification and/or recertification, and any restrictions. imposed on the individual in the use of particular techniques. The eye examination test reports identified the mechod used for the examination.
No discrepancies with the requirements of the SNT-TC-1A recommended practices were identified.
5.
Equipment Certification The inspector reviewed the calibration records associated with the equipment used to perform eddy current, ultrasonic, magnetic particle 3 and liquid pentrant examinations during the angoing outage.
Current certificates were available for each piece of equipment.
. No discrepancies with the ISI program requiraments were identified.
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I 6.
Inservice Inspection Procedures i The inspector reviewed the following procedures: Three Mile Island Unit 1 Surveillance Procedure 1300-IE, Revision 1, dated December 23, 1976, entitled " Manual Ultrasonic Examina-tion of Reactor Coolant and Associated Piping Welds."
Three Mile Island Unit 1 Surveillance Procedure 1300-lV8, Revision 0, dated February 9,1976, entitled " Inservice Inspection of ! Reactor Vessel Closure Head Cladding."
! Three Mile Island Unit 1 Surveillance Procedure 1300-lX, Revision l 1, dated February 20, 1976, entitled " Liquid Pentrant Examination l Procedure."
, l Three Mile Island Unit 1 Surveillance Procedure 1300-1AD, Revision 0, dated February 25, 1976, entitled " Continuous Wet Fluorescent >
Magnetic Particle Procedure for Pressure Retaining Bolting 2 Inch l Diameter and Greater."
Three Mile Island Unit 1 Surveillance Procedure 1300-1V25, (l Revision 0, dated February 11, 1976, entitled " Inservice Inspection ' of Piping Supports and Hangers Not Welded to a Pressure Boundary."
! The above procedures were reviewed for technical adequacy and ' compliance with the requirements of the ASME Boiler and Pressure Vessel Code, Section X1. This included, but was not limited to, the parameters described below for the magnetic particle and ultrasonic examination techniques: a.
Magnetic Particle Examination i (1) Examination by the continuous method is specified.
(2) The type of magnetic particles is specified.
(3) Current and technique are consistent with applicable Code requirements.
(4) Viewing conditions for fluorescent particles are consistent with Code requirements.
(5) Acceptance criteria are specified and consistent with applicable Code requirements.
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Ultrasonic Examination (1) The type of apparatus, including frequency range, is specified.
(2) The extent of coverage, beam angles, and size of trans-ducers are specified.
(3) Calibration is accomplished on appropriate side drilled holes and scanning sensitivity is defined and is in accordance with the ASME Code.
j (4) Evaluation, recording, and acceptance standards for flaw indications are specified and consistent with the applic-able ASME Code.
The inspector's review of Procedure 1300-IE, Revision 1, revealed that paragraph 10, entitled " Evaluation Criteria," did not comply with the 1970 Edition of the ASME B&DV Code, Section XI through Wint'.r 1970 Addenda, which requires that all indications which produce a response greater than 20 percent of the reference level shall be investigated to the , j extent that the operator can determine the shape, identity, and location of all such reflectors.
Part. graph 10.1.1 of ' Cq Procedure 1300-IE, Revision 1, requires that all indications which produce a response equal to or greater than 50 percent of the reference level shall be recorded.
In response to the inspector's question, the licensee stated that the procedure would be revised to comply with the ASME Code, Section XI.
Prior to completion of the inspection, the inspector reviewed Temporary Change Notice (TCN) Number 77-67, dated March 29, 1977, which provided the necessary revision to Procedure 1300-IE.
The inspector stated that the revision was acceptable and the inspector had no further questions at this time.
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., ) 7.
Observation of Work In Progress i a.
Ultrasonic Examination of Pice Welds
l The inspector witnessed the ultrasonic examination of welds . number MS-20, MS-50A, and MS-SOC on the 24" diameter main ! steam line.
No recordable indications were detected.
The examinations were conducted in accordance with procedural l requirments and were consistent with the items detailed in i paragraph 6 above.
! b.
Eddy Current Examination of Steam Generator Tubing The inspector witnessed the eddy current examination of tube #29 row 8, tube 36 row 12, and tube 38 row 14 in the
"A" steam generator.
The examination was conducted in i accordance with Procedure 41-EC-Oll, Revision 0, dated
December 15, 1975, entitled " Eddy Current Procedure - Steam Generator Tubing Examination."
The instrumentation included the following:
! ( Eddy Current Instrument - Automation Industries Model EM 3300,~ serial number 120.
' ' ~ ~ Probe Pusher - Zetec Model SM-3 ' Strip Chart Recorder - Brush MK 220, serial number 01104 i l FM Tape Recorder - Teac Model A-2300S, serial number 92 The inspections were done using a test frequency of 685 KHz by personnel certified to NDE Level I and NDE Level II in accordance with SNT-TC-1 A,197 5 edition.
No discrepancies in implementing the procedural require-ments were identified by the inspector.
c.
Magnetic Particle Examination of RCP Lower Seal Housina Bolting The inspector witnessed the magnetic particle examination of the following bolts: 1454 281 .
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(/ RCP a-1 LSH, serial #208 RCP a-2 LSH, serial #212 RCP a-3 LSH, serial #225 RCP a-4 LSH, serial #230 RCP a-5 LSH, serial #206 RCP a-6 LSH, serial #209 RCP a-7 LSH, serial #203 The examinaticn was conducted in accordance with procedural requirements and were consistent with the items detailed , in paragraph 6 above.
d.
Visual Examination The inspector witnessed the visual examination of the following studs and nuts: RH-08-M RH-09-M RH-10-M RH-ll-M RH-12-M ' ', RH-13-M
RH-14-M - ' RH-15-M RH-16-M The examinations were conducted by Metropolitan Edison Company personnel in accordance with Procedure 1300-lV6, Revision 0, dated February 14, 1976.
No discrepancies in implementing the procedural requirements were identified by the inspector.
The inspector also witnessed the visual inspection of pipe supports in the Reactor Water Makeup and Purification and Decay Heat Lines. Hangers and supports identified as OH-23 through 30 and MUE-14 through 19, 38, and 39 were inspected.
The inspections were conducted by the licensee's contractor personnel.
No discrepancies in implementing visual inspection procedure 1300-lV25 were identified by the inspector.
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ISI Data Review and Evaluation The inspector reviewed available results documented for completed examinations.
These included the eddy current examination of steam generator tubing and the liquid penetrant examination of closure head cladding.
The results were as follows: a.
Steam Generator Eddy Current Ex A.ation (1) "A" Steam Generator No tube thinning was detected.
No tubes required plugging.
(2) "B" Steam 5enerator Tubes numbered 4 through 9 in raw 77 displayed wall thinning ranging from 53 percent to 55 percent of full wall thickness. The thinning was detected in the area (} 46" below the top tube sheet at the bottom of the first ^ - support plate.
The licensee stated that the identified tubes would be pl ugged.
No other tubes displayed any detectable wall thinning.
b.
Reactor Vessel Closure Head Claddirig Examination Locations RH-001-CL and RH-004-CL were examined by use of the visible dye liquid pentrant technique in accordance with Procedure 1300-lX, Revision 0.
The data identified the penetrant material, penetrant dwell time, and developing time.
The two areas were judged acceptable by the NDE Level II individual who conducted the examinations.
No discrepancies were identified by the inspector.
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(3 \\ / 9.
Augmented Inservice Inspection References: (1) IE Circular No. 76-06, entitled " Stress Corrosion Cracks in Stagnant, Low Pressure Stainless Piping Containing Boric Acid Solu-tion at PWRs.
l (2) Metropolitan Edison Letter of December 29, ! 1976 in response to IE Circular No. 76-06.
The inspector reviewed the available data associated with the ultrasonic examination of pipe welds in the Reactor Building Spray System.
The data revealed that the ultrasonic examinations were conducted l using a 5.0 MH transducer with the ultrasonic instrument frequency z j selector switch set at 2.25 MH. z l During a discussion with the licensee the inspector stated that the technique was not acceptable because the test frequency could not be identified.
The licensee stated that the examinations would be redone using a-U technique in which the frequency selector switch is matched to the nominal frequency of the transducer.
This corrective action was acceptable to the inspector.
This item is considered unresolved pending a review of the data generated by the re-examination.
l 10.
Let-Down Cooler Welds i The ihspector reviewed the licensee's plans to install and inspect new Let-Down Cooler Welds.
Woric hequest number 16392 identified the welding procedures which would govern the welding as WDS 81 and WPS llN.
Inlet Nozzle weld MU-1A and Outlet Nozzle weld MU-2A in the Primary side will be stainless steel welds and will be fabricated in accord-ance with WPS 81.
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7) v Inlet Nozzle weld IC83Q and Outlet Nozzle weld IC 88 in the Intermediate Cooling side will be carbon steel welds and fabricated in accordance with WPS llN.
. The licensee stated that the root pass will be examined radio- < l graphically and the final weld will be examined by ultrasonic i and radiographic techniques.
The work was not sufficiently advanced to permit a complete j inspection. However, the inspector's review of the procedure provided for the welding, nondestructive examination and ' administrative control showed that these procedures were i l acceptable in meeting the applicable code requirements.
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