IR 05000302/1986008

Insp Rept 50-302/86-08 on 860129-31.No Violation or Deviation Noted.Major Areas Inspected:Reactor Coolant Pump 1A Shaft Failure & Ultrasonic Exam & Pressurizer Code Safety Relief Valve Discharge Flange Misalignment

ML20154L106
Person / Time
Site:	Crystal River
Issue date:	02/25/1986
From:	Blake J, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20154L097	List: IR 05000302/1986008 ML20154L092
References
50-302-86-08, 50-302-86-8, NUDOCS 8603110392
Download: ML20154L106 (5)

Text

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pa na0 UNITE 3 5TATES

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4 0g),, NUCLEAR REGULATORY COMMISSION

! g r;EGION ll 3' t 101 M ARIETT A STREET, *

! o, ATLANTA. GEORGI A 30303 i

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I i Report No.: 50-302/86-08 -

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_ Licensee: Florida Power Corporation

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i 3201 34th Street, South

St. Petersburg, FL 33733 ,

Docket No.: 50-302 License No.: OPR-72 Facility Name: Crystal River 3

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Inspection Conducted: January 29-31, 1986 Inspector:

N v A ,c .wf +: sJ Pf /Date 5fqned Approved by: . (., i

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J. '. B)tke,'Section Chief Date Signed E inedring Branch

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D vi(ion of Reactor Safety l

SUMMARY l

Scope: This routine, announced inspection entailed 17 inspector-hours on site in

! the areas of reactor coolant pump (RCP) "1A" shaft failure and ultrasonic examina- '

tion; pressurizer code safety relief valve RCV-8 discharge flange misalignment.

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Result: No violations or deviations were identifie I

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i 8603110392 960303 PDR ADOCM 05000302 G PDR

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REPORT DETAILS Persons Contacted Licensee Employees P. F. McKee, Plant Manager

• V. R. Roppel, Manager, Plant Engineering and Technical Services K. R. Wilson, Supervisor, Site Nuclear Licensing F. V. Fusick, Supervisor, Nuclear Engineering G. Halnon, RCP "1A", Task Force Leader

• K. F. Lancaster, Manager, Site Nuclear, QA

• L. Rosefeld, Manager Site Nuclear Compliance

• J. Alberdi, Manager Site Nuclear Operations Technical Services W. G. Neuman, III, Nuclear ISI Specialist Other Organization Courter & Company, In Joe Arrain. QC Inspector i NRC Resident Inspectors

• T. Stetka, Senior Resident Inspector

• J. Tedrow, Resident Inspector

• Attended exit interview 1 Exit Interview

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The inspection scope and findings were summarized on January 31, 1986, with 1 those persons indicated in paragraph 1 above. The licensee was informed of the inspection finding below which was discussed in detail. No dissenting comments were received from the license (0 pen) Unresolved Item 302/86-08-01 "RCV-8 Discharge Flange Misalign '

ment," paragraph The licensee did not identify as. proprietary any of the materials provided to or reviewed by the inspector during this. inspectio . Licensee Action on Previous Enforcement Matters (92702)

This subject was not addressed in the inspectio __ _ _______ _

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s 3 The following applicable procedures were reviewed for technical content:

l SP-200 Rev. 4 Hydraulic Snubber Functional Testing PT-130 Rev. O, Hydraulic Pipe Snubber Test Procedure l

MP-175 Rev. 5, Power Pipe Snubber Removal and Installation

~MP-196 Rev. O, ITT Grinnell Pipe Snubber Renoval and Replacement l The functional testing of the below listed hydraulic snubber was observed to ascertain whether it conformed to acceptance criteria contained in the aforementioned procedure PT-130. These snubbers were identified as follows:

FWH-126 S/N 720083 2}" bore di MUH-40 S/N 73022C 1}" bore di The testing was performed on a ITT Grinnell Shock and Sway Suppressor

! Tester, Model #5434-3. In addition to the functional tests, the inspector

! verified by observation equipment calibration check and reviewed equipment and personnel qualifications for compliance with specifications, industry

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standards and regulatory requirements as applicabl Within the areas inspected, no violations or deviations were identifie . Independent Inspection Effort Discharge Flange Misalignment, Valve RCV-8 Welding (55700)

Following a discussion with the senior resident inspector concerning repair work on pressurizer code safety relief valve CCV-8, the inspector reviewed work package #76268 entitled " Correct Discharge Flange Misalignment on Discharge Pipe". Discussions with cognizant personnel disclosed that the work package was generated when it was determined that the flange on the discharge side of the valve piping exceeded minimum acceptable misalignment criteri The work package showed that in order to correct the problem, the site welding engineer prescribed the following corrective action:

"Using weld procedure 8/8-TT-019, Rev. 5, start weld operation with TIG torch using. weld procedure but do not add weld filler materia Monitor flange alignment. Move TIG unit along the circumference...

allow weld area to cool and check alignment".

This corrective action had been approved by management on January 24, 198 The applicable procedure qualification record (PQR)72-002 showed the TIG process was used in conjunction with 308/308L type filler metal to qualify the procedure for a thickness range of 0.062 to 9/16 inches. The procedure was qualified in accordance with ASME Code Section IX requirement The inspector discussed the use of the aforementioned weld procedure

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2 Unresolved Items (92701)

Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph . Reactor Coolant Pump "1A", Shaft Failure (62700)

This inspection was a followup to that documented in Report 50-302/86-0 Upon arrival at the site, the inspector ascertained that the licensee had fabricated a calibration standard and' developed an ultrasonic examination ,

procedure to be used for the examination of the other three pump shaft l The calibration' block was fabricated from material that was similar to the pump shafts with similar dimensions, configuration and acoustical proper- )

. ties. In addition to the grooves predicated by design, three notches were machined in the areas of interest and located 120* apart at distances of

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approximately 38", 49", and 59" from the top of the shaft. Each notch was

! approximately-1.5 inches long and 0.250" wide and varied in depth from 0.226 to 0.376~ inches. These notch depths were selected with the intent of showing minimum flaw size that could be reasonably detected. The inspector l witnessed the demonstration of the U/T procedure and verified that the reflectors emanating from the machined notches were readily detectabl Discussion with the licensee disclosed that examination of the shafts including the replacement for RCP "1A" would probably occur sometime during i the coming weekend or possibly early during the week of February 3,198 Following the closing of this inspection on February 3, 1986, the licensee's representative, via telephone, informed the inspector that indications with depths greater than minimum notch depth (0.226") were detected in the RC pump "1B" shaft. The indications were located approximately 49" from the top of the shaft and over one half of the circumference. These indications appeared to be in the proximity of the "1A" RC pump shaf t failure. No indications were detected in the shafts of RC pumps C and D. In addition, the licensee indicated that B&W would conduct further U/T examinations in an attempt to characterize and quantify the indications' in "1B" RC pump shaf On February 5, 1986, the licensee decided to arrange for the procurement of a replacement shaft for RC pump "18".

t Discussions with cognizant licensee personnel disclosed that the investiga-tion into the cause of the "1A" RC pump shaft failure was continuing, however, the cause for the initiation and subsequent catastrophic shaft failure has yet to be determine . Inservice Inspection - Snubber Functional Testing, Work Observation (73753)

At the time of this inspection, the licensee was conducting functional tests on designated hydraulic snubbers as required by Technical Specification (TS) 4.7.9.1.(c).

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- 4 without filler metal and stated that this practice violated Code requirement QW-404.14 - Deletion or Addition of Filler Metal, in response, the licensee representative stated that QC had identified this problem and had issued a qual'ty program discrepancy report (QPDR), #86-NQC-002, dated January 34, 1986. .The inspector discussed this matter with onsite management. and stated that an unresolved item would be identified until a review and evaluation of the corrective action ~ to. the QPDR can be done on' a 'later date. The unresolved item was identified as 302/86-08-01, "RCV-8 Discharge Flange Misalignment".

Within the areas inspected, no violations or deviations were identified.

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