IR 05000250/1985009

Insp Repts 50-250/85-09 & 50-251/85-09 on 850423-26. Violations Noted:Failure to Provide Acceptance Criteria for Thread Engagement & to Include Accumulator Pressure Relief Valves in ASME Section XI Pump & Valve Program

ML17346B103
Person / Time
Site:	Turkey Point
Issue date:	05/07/1985
From:	Blake J, Kleinsorge W, Newsome R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML17346B101	List: IR 05000250/1985009 ML17346B102
References
50-250-85-09, 50-250-85-9, 50-251-85-09, 50-251-85-9, IEIN-82-29, NUDOCS 8506270813
Preceding documents:	ML20213G326 (10 November 1986)
Download: ML17346B103 (18)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION II

101 MARIETTASTREET, N.W.

ATLANTA,GEORGIA 30323 Report'os.:

50-250/85-09 and 50-251/85-09 Licensee:

Florida Power and Light Company 9250.West Flagler Street Miami, FL 33101 Docket Nos.:

50-250 and 50-251 License Nos.:

DPR-31 and DPR-41 Facility Name:

Turkey Point 3 and

Inspection 'Cond 'ct Inspectors:

il 3 - 26, 1985 nsorge e

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e Approved by:

J.

J a e, Section C ief E g'ering Branch iv sion of Reactor Safety a

e igne SUMMARY Scope:

This routine, unannounced inspection entailed 58 inspector-hours on site in the areas of licensee action on previous enforcement matters (Units 3 and 4),

inservice inspection ( ISI)(Unit 3), inspector followup items (IFI) (Units 3 and 4), and'E information notice (Unit 3).

Results:

Two violations were identified - "Failure to provide acceptance criteria for thread engagement

- paragraph 3.a.

and "Failure to include the accumulator pressure relief valves in the ASME Section XI Pump and Yalve Program"

- paragraph 3.b.

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REPORT DETAILS Persons Contacted Licensee Employees

• C. Wethy, Vice President

• C. Baker, Plant Manager

• J. Arias, Jr., Regulation and Compliance Supervisor

• R. Teuteberg, Regulation and Compliance Engineer

• J. Ferrare, guality Assurance Engineer

• B. Abrishami, System Performance Supervisor

• F. Carr, Inservice Inspection

• H. Hartman, Inservice Inspection

• E. Anderson, Inservice Inspection

• V. Chilson, Inservice Testing Other licensee employees contacted included construction craftsmen, engineers, technicians, operators, mechanics, security force members, and office personnel.

Other Organization

• D. E. Bogen, ANII Factory Mutual NRC Resident Inspectors

• T. Peebles, Senior Resident Inspector

• D. Brewer, Resident Inspector

• Attended exit interview Exit Interview (30703)

The inspection scope and findings were summarized on April 26, 1985, with those persons indicated in paragraph 1.

above.

The inspector described the areas inspected and discussed in detail the inspection findings listed below.

No dissenting comments were received from the licensee.

The licensee committed to provide a Title 10 Code of Federal Regulations, Part 50.59 report for the throttling and subsequent unthrottling of the residual heat removal system stop valves by June 20, 1985, and to confirm the above in writing by May 10, 1985.

(Open) Violation 250, 251/85-09-01:

"Failure to Provide Acceptance Criteria for Thread Engagement"

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(Open) Violation 250, 251/85-09-02:

"Failure to include the Accumulator Pressure Relief Values in the ASME Section XI Pump and Valve Program "-

paragraph 3.b.

(Open)

Inspector Followup Item 250/85-09-03:

"Visual Examiner Certifica-tion" - paragraph 6.a.

The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.

3.

Licensee Action on Previous Enforcement Matters (92701B)(92702B)

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Unresolved Item 250/84-37-01 and 251/84-38-01:

"Thread Engagement" This item concerns the identification of a nut with one full thread less than full engagement on the 4C intake cooling water pump.

The inspectors discussed the above with the licensee who was unable to provide the inspectors with documented acceptance criterion for thread engagement for bolted connections on safety-related components.

Subsequently, as a result of this item, the licensee generated Training Brief 851, which listed the following requirements applicable to project Turkey Point:

"Standard criteria for thread engagement should be at least one full thread ast the nut (not including bevels, chamfers, or points

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~'NSI B31.1 (1977),

Paragraph 108.5.1.A,

"Bolts and bolt studs shall extend complete through the nuts."

ASME Section III, Division 1, Subsections NF (component supports),

Paragraph NF-4711, "All bolts or studs shall be engaged for the full length of thread in the nut."

ASME Section III, Division 1, Subsections NB, NC, and ND (classes 1, 2, and 3), Paragraph 4711,

"The threads of all bolts or studs shall be engaged in accordance with the design."

ANSI B16.5 (1977),

Flange Standard specifies lengths of stud bolts for standard flanges.

During this inspection period the inspectors identified approximately 20 more examples of nuts on safety-related components, with at least one full thread less than full engagement.

This indicates that the requirement for full thread engagement plus was not widely known among the plant maintenance personnel as evidenced by the wide spread compliance failure in this area.

Therefore, the licensee's failure to provide documented acceptance criteria for thread engagement resulted

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in numerous examples of less than full thread engagement.

Failure to provide documented procedures with applicable acceptance criteria for activities affecting quality is a violation of Title 10 Code of Federal Regulations, Part 50, Appendix B, Criter ion V.

This matter will be closed as an unresolved item and opened as Violation 250, 251/85-09-01:

"Failure to Provide Acceptance Criteria for Thread Engagement."

b.

(Closed)

Unresolved Item 250/84-37-04 and 251/84-38-04:

"ISI for Safety Injection PRV" This item concerns the fact that the safety injection accumulator pressure relief valves 3-858 A, B and C and 4-858 A, B, and C are not included in the inservice valve test program.

The American Society of Mechanical Engineers Boiler and Pressure Vessel (ASME BLPV) Code, 1980 Edition with Addenda through the Winter of. 1981 (80W81),

paragraph IWV 1100 requires,

"inservice testing to verify operational readiness of certain Class 1, 2, and 3 valves (and their actuating and position indicating systems)

in light-water cooled nuclear power plants, which are required to perform a specific function in shutting down a reactor to the cold shutdown condition or in mitigating the consequences of an accident."

Title 10 Code of Federal Regulations Part 50, 50.55a(g)

requires that inservice testing, to verify operational readiness, of pumps and valves whose function is required for safety, be accomplished in accordance with Section XI of the ASME BSPV Code.

Clearly, the omission of the safety injection accumulation pressure relief valves is contrary to the requirements of ASME BSPV -Code,Section XI, paragraph IWV-1100 and therefore is in violation with Title 10 Code of Federal Regulations Part 50.55a(g).

This matter will be closed as an unresolved item and opened as Violation 250, 251/85-09-02:

"Failure to Include the Accumulator Pressure Relief Valves in the ASME Section XI Pump and Valve Program."

4.

Unresolved Items Unresolved items were not identified during this inspection.

5.

Independent Inspection Effort (92706B)

Maintenance Progress The inspectors conducted a general inspection of Unit 3 containment, turbine buildings, auxiliary buildings, and the protected area to observe mainte-nance progress and activities such as welding, material handling and control, housekeeping and storage.

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Inservice Inspection (ISI) (Unit 3)

The inspectors examined documents, activities, and records as indicated below to determine whether ISI was being conducted in accordance with applicable procedures, regulatory requirements and licensee commitments.

The applicable code for ISI is the ASNE B&PV Code, 80W81 and 70W70 as discussed in IE Report 250, 251/85-07.

Observation of Work and Work Activities (73753)

Examiner gualification The inspectors reviewed the qualification documentation for the below listed Florida Power and Light, Nuclear Energy Services (NES),

and Paul-Nunroe (P-M) examiners in the following areas:

employer's name; person certified; activity qualified to perform; effective period of certification; signature of employer's designated representatives; basis used for certification; and annual visual acuity, color vision examination and periodic recertification.

Examiner (P-M)

DFE TMB GF MLN Examiner (FP&L)

FC EA Examiner (NES)

Method - Level VT3-II) VT4-II VT3-I, VT4-I VT1-II, VT2-II ) VT3-II, VT4-II L-III Visual Examiner (Mechanical)

Method - Level PT-III, NT-III, UT-'II UT-III, NT-III, VT1-III, VT2-III VT3-III, VT4-III Method - Level GF PH OS SD JN DM CA UT-II UT-I UT-I UT-II UT-II UT-II UT-I VT-II VT-II VT-II VT-II VT-II MT-II NT-II NT-II MT-I PT-II PT-II PT-II PT-I I PT-I I PT-II RT-II With regard to the examination above, the inspectors noted that the qualification certification for NLN indicated Level III Visual Examiner (Mechanical) without specifying visual method (i.e., VT-1, VT-2, VT-3 or VT-4).

The licensee indicated that they would get clarification from P-M in this area.

The inspectors indicated pending NRC review of the clarification this matter would be identified as Inspector Followup Item 250/85-09-03:

"Visual Examiner Certification."

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Liquid Penetrant (PT) Examination The inspectors observed the liquid penetrant examinations indicated below.

The observations were compared with the applicable procedures and the Code in the following area:

specified method, penetrant materials identified; penetrant materials analyzed for halogens and sulfur; acceptable pre-examination surface; drying time; method of penetrant application; penetration time; surface temperature; solvent removal; dry surface prior to developing; type of developer; examina-tion technique; evaluation technique; reporting of examination results; and procedure requalification.

Weld Identification 14-RHR-2301-1 14-RHR-2301-6 14-RHR-2301-7 14-RHR-2301-8 Code Item Valve (3-751)-to-elbow C5.21 Elbow-To-Pipe C5.21 Pipe-to-Elbow C5.21 Elbow-to-Penetration C5.21 The inspectors reviewed the below listed liquid penetrant materials certification records to ascertain if the sulfur and halogen content of the material was within acceptable content limits.

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Materials Liquid Penetrant Cleaner/Remover Developer Magnetic Particle (MT) Examination Batch Number 82F082, 84G008 84D044, 81M033

83C020 The inspectors observed the magnetic particle examinations indicated below.

The observations were compared with the applicable procedures and the Code in the following areas:

examination methods; contrast of dry powder particle color with background; and surface temperature; suspension medium and surface temperature for wet particles, if applicable; viewing conditions; examination overlap and directions; pole or prod spacing; current or lifting power (yoke);

and acceptance criteria.

Weld Identification 6-8DB-2301-19 6-BDB-2301-20 6-BOB-2301-21 Descri tion Pipe-to-Elbow Elbow-to-Pipe Pipe-to-Elbow Code Item C5.21 C5.21 C5.21

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Batch Number J

83J053 83D048 The above listed welds were MT examined using an alternating current (AC) yoke serial No. 4428.

An additional AC, direct current (DC) yoke, serial No. 4459 was available for use by MT Examiners for the perform-ance of ISI MT examinations.

The inspectors reviewed documentation indicating that a ten pound lift test had been performed on yoke No. 4428.

However, AC/DC yoke No. 4459 had not yet been used for MT Examinations and no lift tests had been performed.

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4459 in order to confirm its adequacy for performing MT examinations.

Lift tests were performed using a ten pound steel plate, serial No.

1004, with the yoke being operated in the AC mode and with a 40 pound steel plate, serial No.

1005, with the yoke being operated in the DC mode.

Certification records for lifttest plates 1004 and 1005 were reviewed to confirm the plate weight.

The lifttests were performed satisfactorily.

Visual Examination The inspectors observed the visual examinations indicated below.

The observations were compared with the applicable procedures and the Code in the following areas:

type of examination; lighting levels; cleanli-ness; measurements; and results.

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Ultrasonic (UT) Examination The inspectors observed the ultrasonic examinations indicated below; The observations were compared with the applicable procedures and the Code in the following areas:

availability of and compliance with approved Nondestructive Examination (NDE) procedure; use of knowledge-able NDE personnel; use of NDE personnel qualified to the proper level; type of apparatus used; extent of coverage of weldment; calibration requirements; search units; beam angles; DAC curves; reference level for monitoring discontinuities; method of demonstrating penetration; limits of evaluating and recording-indications; recording significant indications and; acceptance limits.

Weld Identification 6-BDB-2301-18 6-BDB-2301-19 6-BDB-2301-20 6-8 DB-2301-21 Elbow-to-Pipe Pipe-to-Elbow Elbow-to-Pipe Pipe-to-Elbow Code Item C5.21 C5.21 C5.21 C5.21 The following listed ultrasonic equipment and materials certification records were reviewed:

Ultrasonic Instruments Krautkramer/

Branson Sonic MKI Sonic MKI Sonic MKI Sonic MKIV USL-31 Serial No. 781306 Serial No. 784519 Serial No. 06421 Serial No. 790911 Serial No. 210064 Size 1/2" x

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Sf<<'" ' '") I f * ") )>>g 'V )'<<l' c l ) cl ) lI,I I ~ ) fO ) 'II) " I II) Il~, << ~ II 0) ~ > << II, r'<< "<< ~ ) ~,, ),,",;,,f,', f I) ', f <<f "<<.')) ),f "f<<,)) f I"V)) luff "I 'I' f, "ll ) )<< 'lf) a<<II" <<g" ) " f) l f ' f)t <<0 )'.. ~ << , II 'I ')... f ) <<1").<< K a << ~ I) I ii 'I )).-.') ) Iy W ) ~ I)l, ~ 'P l) '<<I'~ ) << )e I >>ll ))g ) 1 ~ ) ~ "" ') il ~ C;f)f, <<i ~ I, f \\ ~ I ~' ~ << ~ I, ~ II ~ ~ <<<<'l k. I Iil << Ultrasonic Rom as Blocks 792234 792230 790937 (Steel) (Steel) (Stainless Steel) Ultrasonic Cou lant Batch No. 8330 Within the areas inspected, no violations or deviations were identified. 7. Inspector Followup Items a. (Closed) Inspector Fol 1 owup Item 250/84-24-01 and 251/84-25-01: "IST Procedure Discrepancies" OP-0209.1, HP-1507.1, OP-13104.1 and OP-13404.1 have been revised. OP-209.4 was deleted and the material incorporated in OP-13404.1. The inspectors have no further questions in this area. b. (Closed) Inspector Followup Item 250/85-07-03: "Level III Procedure Approval" OP-209.9 and MP-0707.33 were revised such that Level III approval is no longer required. This matter is considered closed. c. (Closed) Inspector Followup Item 250/85-07-04: "Snubber Examiner gualification and Certification" HP-0707.33 was revised such that examiner qualification and certifica-tion statement is no longer required. It was determined that the qualification statement in AD-0190.85 is adequate. This matter is considered closed. 8. IE Information Notices IE Information Notice No. 82-29, dated July 23, 1983, "Control Rod Drive (CRD) Guide Tube Support Pin Failures at Westinghouse PWRs" reported several failures in both domestic and foreign reactors. The inspectors observed a portion of the automated remote replacement of the "control rod drive guide tube support pins" presently being accomplished in the Unit 3 reactor vessel. The replacement process was still in progress at the conclusion of this inspection. Within the area examined no violations or deviations were note I ~ il i hl I lt t W IIV I I ) C' I W $ h ) h ~ g ' t 'I )lt ) t ) g Wt f )) thP'h Iti.~ I~) fhh "' " I 'i I,, Wt'v t pith ~ 'W) )I ) ) ht . t 'h ~\\' tWl 'll )I I i W) I >> 'I' 'I g li )) I ) K ~ t WI. ) >>)) ilfg' ~ I h Wll lgt