IR 05000271/1990005

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Insp Rept 50-271/90-05 on 900529-0601.One Violation & Four Unresolved Items Closed.Major Areas Inspected:Status of Previously Identified Items & Adequacy of Licensee Actions to Resolve Items
ML20044B160
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 06/26/1990
From: Anderson C, Cheung L, Rangaroa G
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20044B159 List:
References
50-271-90-05, 50-271-90-5, NUDOCS 9007170451
Download: ML20044B160 (7)


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U. S. NUCLEAR. REGULATORY COMMISSION

REGION I

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Report No.

50-271/90-05

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. Docket No.-50-271 License-No. DRP-28 f

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Licensee:

Vermont Yankee Nuclear Power Station-

7j Brattleboro, Vermont 05301

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Facility Name:

Vermont Yankee Nuclear Power Station

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Inspection At:

Vernon -Vermont

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Inspection Conducted:

May 29 - June 1,1990

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Inspectors: _ Leonard Cheung,- Senior Rea r Engineer date'

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Approved by:

4/46 9o C. J.// Anderson, Chief, Plant System

'date Section, E8/ ORS-

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Inspection Summaryi Inspection on May 29 - June 1, 1990

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F (Inspection Report No. 50-271/90-05)

. Areas' Inspected: Announced inspection by regional personnel to review the

status of previously identified items and to determine the adequacy of the

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licensee's actions to resolve them.

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Results: One violation (50-271/89-80-04) and four unresolved' items (50-271/89-80-03; 50-271/84-11-08; 50-271/87-19-07; 50-271/89-14-01) were closed.

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DETAILS

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1.0 Persons Contacted See Attachment 1 2.0 Purpose

- The purpose of this inspection was to review the licensee's corrective actions for the deficient items identified in previous inspections o

50-271/89-80, 50-271/89-14, 50-271/87-19, and 50-271/84-11.

The results of these_ reviews are discussed in Section 3.0 and 4.0 of this report.

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3.0 Followup of Deficient Items Identified During the Maintenance Team Inspection 3.1 (Closed) Violation 50-271/89-80-04 This item consists of three parts: a) outdated torque wrench calibration data sheets were being-used; b) torque wrench labels did not identify calibration direction as required by station procedure; and c) three torque wrenches sent

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out for calibration were not properly documented, a)

During the February 1989 maintenance team inspection, the NRC inspector -identified that two outdated torque wrench calibration data sheets (VYAPF 0201.03) had been used to record data obtained during a calibration of two torque wrenches.

Following that inspection, the licensee conducted a search of additional outdated documents -in their controlled document files of the maintenance department. All copies of outdated procedures and forms (data sheets) were removed and destroyed, and the maintenance c)erks were instructed to ensure that all forms and procedures in the department files are current.

The licensee notified all maintenance personnel of the need to ensure that current revisions of procedures and data sheets are.

in use. The licensee expanded these-preventive steps to other departments to ensure that only current procedures and procedure forms are to be used. -In addition, the licensee revised Vermont

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Yankee Plant Procedure (procedure #AP 0831) to require each department to maintain the procedures and procedure forms

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up-to-date. The inspector concluded that the licensee's correc-tive actions for this issue were adequate. This issue is closed.

b)

During the February,1989, maintenance team inspection, the NRC inspector identified that torque wrenches were not clearly labelled, as required by Vermont Yankee Procedure AP-0201, with "CW" or

"CCW" to indicate which direction the wrenches were calibrated.

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Following that inspection, the licer.see retrieved, checkec, and re-labelled all torque wrenches.

The licensee also revised

procedure AP-0201, Appendix A, on June 30, 1989, to more clearly

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define the labelling requirements of torque wrenches regarding the calibrated direction as follows:

Torque wrenches typically will be calibrated in the clockwise direction only.

Torque wrenches may be calibrated in a counter-clockwise direction on an as needed basis, but shall be clearly labeled as such when that occurs."

During this inspection, the inspector toured the. tool room and checked the -labels of three torque wrenches (VY-1610, VY-5012

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and VY-5522).

All of them were labelled in accordance with procedure AP-0201. This issue-is closed, c)

During the February, 1989, maintenance' team inspection the NRC

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inspector identified three "Hytorc" wrenches that were indicated

.i on the list as being out of service for calibration but did not

"j have supporting documentation on the M&TE sign out sheets maintained in the tool room.

Following the inspection, the licensee determined that the three affected torque wrenches, because of their. size, were-

stored remotely. from thu ^ ml room.

The equipment consists of a-hydraulic pump, cont

,on hoses and a special wrench head j

which must be used tc.cher in order to calibrate the unit.

.When these items wer. sent out for calibration before the maintenance team inspection, the maintenance personnel forgot to log those items on the M&TE sign out sheets.

To prevent a recurrence of?this deficiency, the licensee placed the special-wrench head in the tool room to insure that the tool room y

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attendant is aware of when the equipment is sent out.for g

calibration. This is then logged in accordance with the require-

ments of procedure AP-0201, " Control of Maintenance Department J

Measuring and Test Equipment " In addition, procedure AP-0201 j

was revised to include a clear statement of the importance of

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the M&TE sign out sheets, and the importance of recording the status of all equipment in the M&TE program, j

l This item is closed.

3.2 (Closed) Unresolved Item 50-271/89-80-03 pertaining to the

administrative control of tag-outs as it applies to an additional

-work party.

During the February 1989 maintenance team inspection, the NRC inspector identified that there were deficiencies in procedure AP-0140, " Vermont Yankee-Local Control Switching Rules" for addressing r-I how to add an additional party to an existing tag-out, I

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Following.the maintenance team inspection, the licensee organized a j

task force to stftagthen controls in this area. As a result, procedure AP-0140 was revised to address more clearly the administrative i

control of " Work Under Another Person's Tags". The revised procedure

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requires the authorized individual to personally go to.the control room to sign his name in the existing " Switching and Tagging Order."-

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Previously, this was allowed to be approved per telephone conversation.

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In addition, the licensee developed a detailed training plan for the y

procedure change..All personnel on the " Tagging Control List" are

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required ',o receive annuel training on procedure AP-0140.

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licensee's training records indicated that the training was completed on May 1, 1990.-

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This item is closed.

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4.0 Followup of Deficient Items Identified in Previous Equipment QualificationInspection 4.1 (Closed) Unresolved Item 50-271/84-11-08 pertaining to the environmental

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qualification (E0) of Containment High Range Radiation Monitor j

(CHRRM) (NUREG-0737 Item II.F.1-3)

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During the May-1984 ' inspection, the NRC inspector identified the

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following three unri.;.olved issues:

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The licensee was unable to provide documentation to substantiate

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the environmental qualification of the radiation detectors, cables, j

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and heat-shrink cable to connection sealer.

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The licensee was unable to provide documentation to substantiate

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the environmental qualifications of the. sealant (RTV-162) used

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to seal the cable connectors from the environment.

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The licensee was unable to provide documentation to substantiate

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the environmental qualification.of the cables (pigtails)~ supplied with General Electric Cable Penetrations which are used for the

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CHRRti.

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In response to the first concern, the licensee has developed EQ files with the necessary evaluation and test data for the qualification of the radiation detectors (Victoreen Model C77), the cable (Rockbestos RS-6-104) and the cable connectors (Amphenol with Raychem splices at

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the GE penetration and the Victoreen connectors at the detectors).

The licensee demonstrated the qualification of these items by type testing for the drywell harsh environment.

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For the second concern, the licensee explained that the Victoreen connectors were filled with an insulating compound when the cable connections were made.

The sealant (RTV-162) was then applied to tie surface of the connecting joints for additional protection.

The Q file contains test data showing that the Victoreen connector witinout the RTV sealant was qualified for the drywell harsh environment.

Also, the licensee has generated a work order to ' add Raychem r,plice fitting to those Victoreen connectors in the September 1990 outage to-provide additional protection.

For the third concern, the licensee stated that no pigtails were used-

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at the GE penetrations for the CHRRM Victoreen connectors.

The pigtails found in these penetrations are used for instruments other than the CHRRM.

Those pigtails were identified by the licensee as Kynar insulated cable.

The licensee qualified the pigtails by type testing in Acton Test facility (National Testing Systems) for the drywell harsh 2nvironment.

The inspector concluded that the evaluations and the documentation provided by the licensee are acceptable. This item is closed.

4.2 (Closed) Unresolved Item 50-271/87-19-07 regarding the qualification of wire connectors in three Limitorque actuators.

During the October 1987 inspection, while conducting the physical inspection of Limitorque actuators, the inspectors found that three motor terminations contained unidentified wire connectors and that the Limitorque qualification test reports did not contain adequate data to support the eny ronmental d

qualification of.these connectors.

The licensee identified these valve actuators as RHR-398, V10-34A and V14-11A which are clual voltage type motors.

This item was reviewed by the NRC during the August 1969 inspection.

At that. time, the licensee attempted to demonstrate the quclification of these wire connectors using the test results conduc uo by Illinois Power Company.

However, the test report was not available then for

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the inspector's review.

In addition, the inspector also noted that the activation energey used by the licensee to calculate the. thermal aging was not a conservative value.

Following the August 1989 inspection, the licensee decided to change-the existing condition by plant modifications. The licensee replaced the existing wire connectors with qualified Raychem cable splices for-valve actuators RHR-39B and V10-34A.

For valve V14-11A, the licensee replaced the dual voltage valve motor with a single voltage Limitorque valve motor which does not contain this type of wirt connector.

The inspector concluded that the licensee's corrective actions are acceptable. This item is closed.

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L 4.3 { Closed)~UnresolvedItem 50-271/89-14-01 regarding the qualification of GE EB-25 terminal blocks.

During the August 1989 inspection,-the inspector revieved QDR 17.4A i.

and a Wyle Laboratories test report and found the fol'owing:

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address the instrument loop accuracy, the licensee did not use the t

lowest insulation resistance value measured by Wyles' test and-L improperly calculated the loop error by comparing the measured

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leakage current to the mean value (50%) of the instrument loop.

In response to the NRC's concerns,.the licensee revised QDR 17.4A, page A-5 to reflect the lowest insulation resistance value and added the justification of the non-applicability of the insulation resistance measurements observed with the terminal blocks used with low voltage relay, power supply and temperature switch circuits.

The test sonducted by Wyle laboratories indicated that GE EB-25 terminal blocks are qualified for outside containment use in a high energy line break (HELB) environment. Under the HELB condition, the maximum peak temperature is 193'F for first 30 seconds, 175'F for next 200 seconds and then drops to 150'F and below.

In an isolated case, the test data showed 0.38 mA leakage current for the sample at 212'F for a 12 mA signal.

The licensee is aware of this 0.38 mA leakage current, which occurred at a test temperature above the 210'F range. Under the results summation, Wyle Laboratories clearly indicated that these deviations are not specimen induced. Hence, the licensee has chosen conservatively the value of 0.05 mA.as the maximum leakage

. current for the instrumentation for the instrumentation error calculation under a maximum HELB operating temperature up to 210'F.

The analysis provided by the licensee and the Wyle Laboratories test data adequately addresses the qualification of GE EB-25 terminal blocks for outside containment use.

This item is closed.

5.0.' Exit Meeting At the conclusion of the inspection on June 1, 1990, the inspector met with the licensee representatives denoted in Attachment 1.

The inspector summarized the scope and results of the inspection at that time.

At no time during this inspection was written material given to the license hI I

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Attachment 'l V

Persons Contacted

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1.0 Vermon: Yankee Nuclear Power Corporation G. Cappuccio, Senior Mechanical Engineer-R. Grippardi, QA Supervisor F. Helin, Project Engineer S.' Jefferson, Assistant to the Plant Manager J. Kinsey, Project Engineer

  • R. Lopriore Maintenance Supervisor

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  • J. Osmond, Senior Electrical Engineer R. Pagodin, Technical Services Supt.

D. Reid, Pir.nt Manager R. Wanczyk, Operations Superintendent 2.0 Yankee Atomic Electric Company

  • M. Saniuk EQ Cognizant Engineer 3.0 United _ States Nuclear Regulatory Commission H. Eichenholtz, Senior Resider.t Inspector T. Hiltz, Resident Inspector
  • Denotes those not present at the exit meeting at the Vermont Yankee site on June 1,1990, i

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