IR 05000413/1993033

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Insp Repts 50-413/93-33 & 50-414/93-33 on 931129-1203.No Violations Noted.Major Areas Inspected:Isi of Pipe Supports & Snubbers & TS Surveillance of Snubbers
ML20059C150
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 12/23/1993
From: Blake J, Clou R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20059C148 List:
References
50-413-93-33, 50-414-93-33, NUDOCS 9401040409
Download: ML20059C150 (9)


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/g ate \ UNITED STATES NUCLEAR REGULATORY COMMISSION

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[* yak REGION 11

$- g 101 MAR!ETTA STREET, N.W., SUITE HJO

'4 't j ATLANTA. GEORGIA 303230199 I

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Report Nos.: 50-413/93-33 and 50-414/93-33 Licensee: Duke Power Company  ;

422 South Church Street  :

Charlotte, NC 28242 i

Docket Nos.: 50-413 and 50-414 License Nos.: NPF-35 and NPF-52 ,

Facility Name: Catawba 1 and 2 l

Inspection Conducted: November 29 to December 3, 1993

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Inspec or: //- 3 .3

. . ihou Date Signed Approved by: .- / 3f*

J f( Blake, Chiaf Date Signed +

9 erials and Processes Section t -

Engineering Branch Division of Reactor Safety  :

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SUMMARY  ;

Scope:

This routine, announced inspection was conducted in the areas of Inservice *

Inspection (ISI) of pipe supports and snubbers and Technical Specification  ?

Surveillance of Snubber ,

Results:

In the areas inspected, violations or deviations were not identifie .

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Two unresolved items were identified in the area of inspection of pipe  ;

supports for not removing insulation during ISI inspections (Paragraph 2.2) .i and in the area of concerns about procedures and inspections of snubbers (Paragraph 3).  :

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9401040409 DR 931229 ADOCK 05000413' ,

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REPORT DETAILS _;

, Persons Contacted j Licensee Employees  !

  • A. Bhatnagar, Component Engineer Manager-  ;
  • D. Caldwell, Civil Engineer Supervisor f
  • C Cauthen, Component Engineer 1:

J. Coleman, Quality Control (QC) Supervisor .

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  • J. S. Forbes, Engineering Manager  !
  • R. Giles, Quality Assurance (QA) ISI Coordinator
  • D. Kimball, Catawba Safety Review Group Manager
  • McCollum,-Station Manager

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  • K. Nicholson, Compliance Specialist

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  • G. Robinson, Mechanical Maintenance QA Supervisor
  • J. Stackly, Component Engineer Supervisor e M. Wiles, QC Inspector  ;

i Other licensee employees contacted during this '.nspection included  ;

craftsmen, engineers, mechanics, technicians, and administrative i

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personne '

NRC Resident Inspectors  :

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  • R. Freudenberger, Senior Resident Inspector J. Zeiler, Resident Inspector
  • Attended exit interview

' Visual Examination of Pipe Support for Inservice Inspection - Unit 1 1 Procedure Review '

The inspector reviewed the procedures listed below to determine whether:  :

they were consistent with regulatory requirements and licensee commitments. The' procedures were also reviewed in the areas of  ;

procedure approval, requirements for qualification of examiners, and

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compilation of required record ;

i Procedures N Rev. N Title 'i QAF-9 9 Pipe Support Installation Inspection- l t

QAF-14 13 ISI Visual Examination, VT-3 and l-VT-4 l

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Procedure No. QAF-9 was only partially reviewed because the inspectio standards or acceptance criteria for the correct settings of snubbers

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and spring cans referred to QAF-14. Procedure No. QAF-14 is to provide  !

the examination requirements and records in accordance with American  ;

Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV)

Code Section XI, 1980 Edition with Addenda through Winter 1981, for Catawb ,

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' Observations of Examination The' licensee provided updated status of pipe support inspections to the inspector as follows:

Class 1 Class 2 Class 3 Total 69 119 243 Completed 44 78 242 Remaining 25 41 1 There were no discrepancies found on class 1 supports. -Th_e discrepancies found for classes 2 and 3 were listed below:

Support No, Rev. N ISI Item N Pipe Class Discrepancies e

1-R-SA-0029 6 Fl.02.793 2 Spring can out of toleranc R-KC-0515 3 Fl.03.590 3 Bushing out of positio R-KC-0555 4 F1.03.606 3 Bushing out of positio _l-R-KC-0875 -0 Fl.03.624A 3 - A loose bolt on pipe clam ?

- Anchor bolts and base plate _

pulled out from ,

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The licensee issued Work Requests (WR) to fix the problems for the first three items; - Problem Investigation Process (PIP) No. 1-093-0875 wa s written for root cause analysis and resolution of the fourth ite .)

il To verify the licensee examination process, the inspector observed i inspections conducted by the licensee examiner and then independently 1 inspected eight pipe supports 'after the examiner completed the ~

examination to see if-any discrepancies were not found or recorded by -

the examiner. The eight pipe supports were in the Auxiliary Feed Water j System and Steam Vent System. The examination procedures and acceptance !

criteria were Procedure Nos. QAF-9 and 14. The visual inspection: -!

included a check for defects including: distortion, cracks, bent members, and weld failures induced by plant operations; condition of connections to supporting structures; and component settings. The inspector's observations generally agreed with the information recorded and reported by the licensee's ISI examine '

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Table 1 Support N Rev. N Insulation Condition and Findinas 1-R-CA-1596 6 Hard insulation covered pipe clamp bolts and nuts and welds between pipe clamp and short bars welded to the clamp R-CA-1597 5 Hard insulation covered the U-bol ,

1-R-CA-1598 5 Hard insulation covered two bolts and nuts next to the pip R-SV-1514 5 Soft insulation covered two bolts and nuts next to the pip The middle bolt and nuts (one of the two bolts next to the pipe) were found to be loose by the licensee's examiner when he lifted up slightly on the opening of the insulatio R-SV-1515 4 Soft insulation covered two bolts and nuts next to the pip The middle bolt and nuts (one of the two bolts next to the pipe) were found to be loose by the licensee's examiner when he lifted up slightly on the opening of the insulatio R-SV-1516 5 The jam nut for the extension pipe '

for the snubber was found to be loose. A 4 inch gap was found at the rear bracket between the spherical bearing and washer Hard insulation covered two bolts and nuts next to the pip Hard insulation avered two bolts

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l - R- SV- 1517 4 and nuts next to the pip R-SV-1519 4 Non ;

Most of the above supports the pipe clamps were covered by installed hard or soft insulation. There are typically three bolts with nuts in the pipe clamps; these are the load bolt, middle bolt, and end bol The middle bolt and the end bolt are next to the pipe. During the first three support inspections, the NRC inspector noted that the examiner did I not attempt to remove insulation for inspection, he only inspected up to the insulation. When the inspector questioned him as to why he did not )

remove insulation for the inspection, he said that it was not required i

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i to remove insulation for ISI. Later, he opened slightly the insulation for two supports. He found both supports to have loose bolts and nuts in the middle bolt .

j Per the licensee's QC inspector's and supervisor's. interpretations of j their procedure and code requirements, there is no need to remove insulation during the ISI except where an integral weld exists between the support members and the pipe such as lugs. The integral welds are required to be inspected to the requirements of the pipe classes with !

the removal of insulation. The licensee's bases for not removing ,

insulation are-as follows:

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ASME Code,Section XI, IWF-1300(e)

ASME Reply to Inquiry Item IN90-027 about IWF-1300(c)

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ASME Reply to Inquiry Item IN92-010 about IWF-1300(e)

The inspector believes that if you don't remove insulation during the -

ISI, you may miss defects either on the members or connections inside ;

insulation. The-licensee agreed to-evaluate the problem of not removing insulation during ISI. This item is identified as Unresolved Item 50-413,414/93 33-01, Pipe Insulation Removal During ISI Support ,

inspection. The licensee currently only intends to issue the Work Requests to fix the loose bolts and nuts already identifie :

i 2.3 Data Review *

Records of completed ISI examinations for the pipe supports listed in Table I were reviewed. These records were reviewed to determine whether- -

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the methods, techniques, and extent of the examination complied with the -

ISI plan and applicable procedure and findings were properly recorded and evaluated by qualified personne ;

2.4 Personnel Qualification Review l

The inspector reviewed personnel qualification documentation for the ISI :'

examiners, as listed below in Table These qualifications were reviewed in the following areas: employer's name; person certified; activity qualified to perform; current period of certification; signature of employer's designated representative; basis used for certification; and annual visual acuity; color vision examination, and periodic recertificatio ,

In the areas inspected, no violations or deviations were identifie ,

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ISI Examiner Qualification (VT-1 to 41 )

Initials Qualified Level Certified Period Eye Exam Expires

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TAB II 03/09/92 to 03/09/95 07/29/94 KMW Il 10/14/93 to 10/14/96 09/14/94- !

AL II 07/21/91 to 07/21/94 02/11/94 i KBG II 09/24/91 to 09/24/94 03/08/94 !

JAF II 09/24/91 to 09/24/94 05/25/94 JDB II 07/22/91 to 07/22/94 03/30/94 :

JHM II 09/24/91 to 09/24/94 03/03/94 !

DTM II 03/09/92 to 03/09/95 04/15/94 BMW II 09/24/91 to 09/24/94 02/10/94 MDM II 07/22/91 to 07/22/94 03/15/94 i

HCM II 10/14/93 to 10/14/96 09/20/94 TSM II 09/24/91 to 09/24/94 03/15/94'

PDS II 07/22/91 to 07/22/94 06/17/94 TJW II 07/22/91 to 07/22/94 '11/11/94: ;

'i Technical Specification Snubber Inspection - Unit 1

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In accordance with Section 3.7.8 of the Technical Specification, all the snubbers shall be operable. Per Section 4.7.8'of the same specification, each snubber shall be demonstrated operable by'the . 1 performance of visual inspection for all the snubbers plus stroking the mechanical snubbers through its full range of travel for six systems ,

before or during the each refueling outage. The six systems are the  :

systems with the potential dynamic events including the Main Steam System (upstream of the main . steam isolation valves), the Main Steam safety and power-operated relief valves and piping, Auxiliary Feedwater .i System, Main Steam Supply to the Auxiliary Feedwater Pump Turbine,' and the letdown and charging portion of the Chemical Volume Control (CVC) 3 System. .All safety-related snubbers shall be visually examined to

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verify snubber operability. At least every 18 months, during shutdown, '

a representative sample of 10 percent, or 37 snubbers, of the total of >

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6 -l each type (hydraulic, mechanical, or manufacturers) of safety-related 1 snubbers in use in the plant shall be functionally tested either in ,

place or bench teste !

i Catawba Unit I has 969 snubbers in safety-related piping systems of !

which 20 are hydraulic snubbers and 949 are mechanical snubbers. 294 snubbers are to be stroked in the six high temperature o.r high energy

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system The current status of the snubber inspection, functional test, ~l and stroke testing in field is shown belo ,

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Two Anchor / Darling Type snubbers were tested and were I acceptabl )

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37 Pacific snubbers were tested with one failur An additional sample of 18 snubbers had been tested and were acceptable. The failed snubber was from Support 1-RKC-081 ;

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Stroke testing of 280 of 294 snubbers. from the six systems, ,

had been completed, with three snubber failures. The failed

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snubbers were from Support Nns. 1-R-ND-0226, 1-R-ND-0596, l and 1-R-CF-1728. Evaluation of those three failed snubbers !

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determined that they had been. damaged by water.' hamme i

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Visual examination of 900 of 969 snubbers had been  !

completed. Three snubbers failed the visual examinatio Snubbers from Support Nos. 1-A-RN-9403 and 1-1 XC-8652 failed by binding near rear brackets. The snubber on

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Support 1-R-NC-1767 had paint on the snubber tube about-1 .

inch lon j

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The licensee used the following procedures to perform visual i examination, functional testing, field stroking, reinstallation after - !

stroking, and maintenance of snubber l-

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Procedure No. MP/0/A/7650/59, Controlling Procedure for Support / Restraint Maintenance

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Procedure No. MP/0/A/7650/85, Visual Inspection of . Snubbers -i and Corrective Maintenance j

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Procedure No. MP/0/A/7650/87, Controlling Procedure for Steam Generator Snubber Maintenance / Testing Activities

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Procedures No. MP/0/A/9650/95, Post Transient. Piping and Hanger Inspection

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Procedurc No. MP/0/A/7650/131, Functional Testing of Snubbers

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.The inspector observed inspection of six snubbers by the licensee's  !

snubber inspector. The NRC inspector independently inspected each I snubber, after the licensee's inspector, and generally agreed with' the )

. findings. The six snubbers observed and inspected are listed below in Table 3. Field stroke testing of the snubber in Support 1-A-NV-4211 was :

also observe ;

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Table 3

Snubbers Observed and Inspected .

Support N Rev. N Comments  !

l-A-NV-4211 I 2 Snubbers No. S/N 13680 i

1-R-NC-ll29 D2 1-R-NC-1603 D2 ,

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l-R-NC-1604 1 1-R-NC-1767 D3 1-R-NI-4385 0 During the review of procedure No. MP/0/A/7650/85, Visual Inspection of l Snubber and Corrective Maintenance, and observation of the snubber field- ;

inspection performed by the licensee's snubber inspector, the NRC  ;

inspector noticed the following: l

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Overall support Inspection The current snubber visual inspection procedure does not !

require the overall inspection for the supporting- 1 structures, or foundation, to support the snubber functio 'j The supporting structures should include the gang support !

The procedure only requires visual-examiners to inspect.the l snubber, pin to pin, which might extend to end attachment :

Currently, the licensee relies on the individual to perform the overall support inspections because this is not a requirement. The concern with not inspecting the overall supporting structure, or foundation, is that damage to the

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overall structure members or connections may impact the operability of the snubber.

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Gap Between the Spherical Bearing (Bushing) and Washers l The current inspection procedure and' practice do not inspect -l the gap between the spherical bearing and clevis or washers at the rod end, near the rear bracket, or the piston rod eye :

near the pipe clamps Conceivably, with an excessive gap, I snubber movement or impact due to pipe movement or vibration !

could cause damage to the rods, pins or washer Cold or Hot Setting Inspection and Record Comparison

There are v requirements in the procedure and to practice' !

in the fi:lu M pection to record the snubber cold or hot settings or,7j ompare them to the design documents to see if ,

the snubber nas experienced unusual activities or j transient Tool to Inspect 4 degrees Alignment Between Center Lines of i Clamp and SnLbber  ;

Per Section 11.4.4 of Procedure MP/0/A/7650/85, there is a !

requirement to inspect and make sure that the alignment of I pipe clamps and snubber center lines are within 4 degrees in :

each direction. Snubber in Support 1-R-NC-1604 appears to ;

be out of alignment between the pipe clamp and snubber. The '

NRC inspector did not see the licensee inspector carry any' ,

tool to measure and to make sure that the alignment is ;

within 4 degree The licensee agreed to evaluate the above concerns and find an appropriate resolution. The concerns shown above are identified as Unresolved item 50-413,414/93-33-02, Concerns with Snubber ,

Procedure and Inspectio .0 Exit Interview The inspection scope and results were summarized on December 3, 1993, with those persons indicated in paragraph'I. The inspector described '

the areas inspected and discussed in detail the inspection results listed below. Proprietary information is not contained in this repor Dissenting comments were not received from the license ,

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(0 pen) Unresolved item 50-413,414/93-33-01, Pipe Insulation Removal During ISI Support Inspectio ,

(0 pen) Unresolved Item 50-413,414/93-33-02, Concerns with Inadequate Snubber Procedure and Inspectio !

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