ML20209A369

Insp Rept 50-333/88-25 on 881011-14.Violation Noted.Major Areas Inspected:Status of Previously Identified Open Items & Adequacy of Licensee Response in Resolving Issues

ML20209A369
Person / Time
Site:	FitzPatrick
Issue date:	11/01/1988
From:	Anderson C, Julio Lara, Paolino R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20206K801	List: ML20206K797 ML20206K805 ML20209A369
References
50-333-88-25, NUDOCS 8811290553
Download: ML20209A369 (9)

See also: IR 05000333/1988025

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-333/88-25 ,

Docket No. 50-333

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License No. DPR-59 Priority -- Category C

Licensee: Power Authority of State of New York

P.O. Box 41

Scriba, New York

Facility Name: James A. Fitzpatrick Nuclear Power Plant (JAFNPP)

Inspection At: Scriba, New York  ;

Inspection Conducted: October 11-14, 1988

Inspectors: (f. / o f/ If

R. J/ Pao ino, Senior Reactor Engineer, PPS/EB ' date

Ok0 $( T bater

JF Lara, Reat or Engineer, PPS/i[B

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date

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Approved by: b h ff

C.J.Nnderson, Chief.PlantSystemsSection, date .

EB/ ORS

Inspection Summayr : Inspection on October 11-14, 1988 (Inspection Report

No. 50-33T/aF25)  ;

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Areas Inspected: Announced inspection by regional personnel to review status '

oT previously identtfled open items and determine adequacy of licensee

response in resolving each issue.

Results: The inspector determined that the licensee has satisfactorily I

responded to the open items. Eighteen previously identified open items have

been closed.

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During the inspection, one violation was identified involving unqualified  ;

Okonite splices in Limitorque 12MOV-15 located in the drywell.

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DETAILS

1. Persons Contacted

1.1 New York Power Authority (NYPA)

R. Baker, Maintenance Superintendent

• R. Converse, Resident Manger

• W. Fernandez, Superintendent of Power

H. N. Keith, I&C Superintendent

• J. M. Lazarus, Associate Plant Engineer

• K D. Moody, Plant Engineer II

• R. L. Patch, Quality Assurance Superintendent

• 0. Ruddy, Senior Plant Engineer

G. Tasick, Quality Assurance Supervisor

• V. M. Walz, Technical Service Supervisor

1.2 Nuclear __ Regulatory Commission

• A. J. Luptak, Senior Resident Inspector

• R. A. Plasse Resident Inspector

• Denotes personnel present at exit meeting of October 14, 1938,

2. Purpose

The purpose of this inspection was to review the status of previously

identified items and to determine the adequacy of the licensee's corrective

action in resolving each issue.

3. Status of previously Identified Items

(Closed) Unresolved Item 85-16-02 pertaining to cable pull tension for

cables installed per plant modifTeation F1-82-053. The NRC concern was

that the cable pull tension does not exceed the maximum allowed for the

smallest cable being pulled.

The NRC inspector reviewed licensee cable 5, I tension calculations No. 005

for Modification F1-82-053. The NRC inspector determined the licensee had

not exceeded the maximum pulling tension for any of the installed cables.

This item is closed.

(Closed) Unresolved Item 85-_16-01 pertaining to engineering justification

on use of 1 inch spfice seal length for Raychem splices. The NRC inspector

reviewed licensee splice installation drawings (F1-82-53-119) in effect at

the time which specified the 1 inch overlap. Data to support the 1 inch

splice seal length was developed by licensee contract personnel in Report

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Nos. PEI-TR-82-4-2A dated May 24, 1985 and PEI-TR-860300-01 dated May 9,

1986. Current test data (Wyle Report No. 17859-02P dated March 1987)

indicates Raychem splice seal overlap of less than 1 inch to be acceptable.

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This item is closed.  !

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(Closed)_ Unresolved Item 86-14-03 pertaining to installation procedure {

requirements for installing Okonite electrical splices. Licensee l'

procedure No. IS-E-OS Revision 1 dated February 4, 1987 was revised to

clarify application of insulating tape to conform to the qualifted  !

configuration. The requirements for four layers of tape has been  !

clarified to read two half-lapped layers of tape for the T-95 (red) and -

T-35 (black) tape. One half-lapped layer is defined as two layers total.

This item is closed.  !

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(Closed) Unresolved Item 87-14-01 pertaining to EQ Maintenance and  ;

Surveiflance Procedures.

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At the time of the EQ inspection, licensee EQ Maintenance and

Surveillance Procedures were in draft form awaiting review and approval. i

The licensee's review has been completed and the procedures have been  !

approved for use by the Plant Operating Review Committee (PORC). i

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The NRC inspector reviewed several procedures verifying cuistence of  !

EQ Maintenance / Surveillance procedures. '

This item is closed.

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(Closed) Violation 87-14-03 pertaining to generic EQ file deficiencies l

involving missing documents / data necessary in determining qualification l

of electrical equipment subject to 10 CFR 50.49 requirements.

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The Itcensee has developed and issued a new procedure (EDP-28) entitled f

"Review of Plant Specific Qualification Report." The procedure requires i

written documentation of the review, qualification and acceptance of EQ l

files in accordance with a checklist which documents the detatis of the l

file review and verification. The checklist includes acceptance criteria, I

similarity analysis as well as other pertinent qualification attributes. i

Fifty percent of the licensee files have been revised in accordance with i

procedure E0P-28. The remaining EQ files are scheduled for completion by j

mid-1939. l

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This item is closed. I

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(Closed) Violation 87-14-04 pertaining to the qualification of Brand-Rex

Cable (Model T;7600).

The licensee has revised the Brand-Rex EQ file 231 to include the

environmental qualification report No. QDR-6.18 Revision 1, dated 1987

which addresses qualification of the Brand-Rex cable (Model T-7600) in

the environmental conditions of the steam tunnel. The report also

compares the qualified T-7506 insulating materials with the T-7600 cable.

This item is closed.

(Closed)_ Violation 87-14-05 pertaining to the use of Cerro KXL-760 cable

l for generic instrument cable application.

The licensee has revised the Cerro KXL-760 EQ file to ine:.de the

"Qualification and Review Package" 00R 6.2 Volumes I, II, and III dattd

1987 on Rockbestos (Cerro) Firewall III and Pyro-Trol III cable.

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The NRC inspector also reviewed licensee analysis of cable circuitry

performance (ETR 2062-1 Revision 1) dated July 17, 1987 which evaluated

l total combined inaccuracy affects for the entire instrument loop for each

I instrument in the EQ program. The analysis included the accuracy effects

of all applicable cables and determined that the cables were capable of

maintaining acceptable instrument accuracy performance during applicable

postulated design basis accidents.

This item is closed.

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Closed) Unresolved Item 87-14-06 pertaining to generic use of BIW XLPE

{ibTe (modell Tb78-l 066) in H KB/LOCA instrument applications with peak

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accident temperatures of 285'F and peak pressure of 23.5 psia. The

licensee's BIW XLPE EQ Cable file No. 212 5as been revised to reflect the

licensees review and evaluation (ITS-87-0434) of October 21, 1987 which

determined that the BIW XLPE cable (model 14538-H-006) is only used in

non-EQ applications except for six instrueents which have been

reclassified as Category !! and III. The licensee has deleted this cable

from the EQ program and all applicable procedures, instructions have been

revised accordingly.

T'.is item is closed.

LCl_osed) Unresolved Item 87-14-07 pertaining to the seneric use of Eaton

cables inside the primary containment. The EQ file SCEV sheet indicates

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the Ecton cables are qualified for generic application inside primary

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containment. Note 2 of the SCEW sheet indicates cables are in a mild

emvironment. Licensee review and evaluation confirm cable is used in a

m 11d environment only. The cable has been removed from the EQ program

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and all applicable doc.uments have been revised by the licensee to reflect

the limited use of the Eaton cable.

This item is closed.

(Closed) Unresolved item 87-14-08 pertaining to Ro.emount Model 1153

Series B transmitters (fQ file NO. 276) used to detect and initiate an

isolation signal in the event of a Main Steam Line Break (MSLB).

The EQ file review contained several deficiencies which the licensee

committed to address in the next file revision. The revisions to the EQ

file include:

• The results of the tssts performed on type "P" transmitters be added

or summarized in the Patel Reporc PEI-TR-82-4-25 since the type "R"

transmitter (installed at JAFNPP) test performed was not a full

sequential type test as defined in IEEE std.323-1974.

• File did not have sufficient justification to support qualification

of Rosemont model 1153 Series B transmitter at 350*F. However, the

Rosemont Model 11538 is qualified to 265'F which envelops the

highest specified temperature for locations where these types are

installed.

• Inconsistency on qualified life corrected to show a qualified life

of 40 years provided that the 0-rings are replaced each time the

cover is removed. The inspector verified licensee revisions to the

EQ files.

This item is closed.

[ Closed)Unresolveditem 87-14-09 pertaining to the qualification of

Magnetrols Level $ witches supplied with internal wiring manufactured by

Rockbestos.

To establish qualification of the Rockbestos internal wiring, the

Rockbestos Report No. 1806 is referenced. However, the NRC determined

the concerns of Information Notice 84-44 were not addressed. The

licensee committed to revise the EQ file No. 267 to reflect the new

Rockbeston Reports. The inspector verified that the new Rockbestos

Report JAF EQ Reference 205b, Revision 1 "Plant Specific Qualification

Report for Rockbestos Firewall III and Pyro-Tral III" was included in

Patel's Evaluation Report (PEI-TR-82-4-25) of the Magnetrol Level Switch.

This item is closed.

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(Closed) Unresolved Item 87-14-10 pertaining to the missing functional l

tests which were not performed during LOCA Testtag of the Thomas and l

Betts Terminal lugs. The licensee does not take credit for insulating .

j capabilities provided by the Tefiel sections of these connectors in any l

of the installations. Instead, the required dielectric strength is '

] provided by properly installed and qualified terminal boards and l

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insulated splices. This resolution to tne Franklin TER concern was  !

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determined to be acceptable but was not ircluded in the Thomas & Betts EQ [

. file No. 261. The NRC inspector reviewed the revised EQ file verifying >

j the addition of the above information.

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This item is closed. l

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l (Closed)UnresolvedItem 87-14-13 pertaining to MCC's ;usceptible to water  !

l impingement resulting from steam condensations on equipment located above  !

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the MCC's. '

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The licensee reported two LER's (LER 86-12 and 86-21) involving water  !

which was either sprayed or drained onto Motor Controi Centers (MCC) and l

j caused shorting of safety-related circuits.  ;

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The long term corrective action by the licensee was a design change to j

l increase the MCC's water tight integrity.  :

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{ The inspector verified that the licensee has modified (no F1-86-061) the t

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MCC's by installing drfp shields and door gaskets for protection against  !

water spray. Licensee evaluation determined that the direct water spray l

l 15 not part of the postulated DBA. The worst case documented in the EQ i

file is 100*4 relative humidity.

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This item is closed.

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I (Closed) Unresolved ll em 87-14-14 pertaining to the thermal aging

evaluation based on different materials of construction for the General

Atomic Radiation Monitor cable / connector.

The material used in the Conax electrical penetration assembly was I

1 identified as tetrachloroethylene (TFE), whereas the material in tne I

] amph2nol connector was cross-linked polystyrene,

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] The licensee provided additional thermai aging data to demonstrate the  !

suitability of the Amphenol connector at Fitzpatrick. The NRC inspector

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reviewed the General Atomic Radiation Monitor EQ file No. 262 verifying I

addition of thermal aging data on Amphenol connectors. l

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(Closed) Violation 87-14-16 pertaining to the thermal aping analysis used

in qualifications of AAA-Solenoid valves besed on the assumption that the

solenoid coil was similar in construction to the Limitorque Motor.

New thermal aging data was developed to qualify the solenoid coil

configuration.

All applicable documentation (QDR 35.4) has been revised to reflect new

data which demonstrates qualification for the JAF site.

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This item is closed.

(Closedj_V,folation 87-14-18 pertaining to generic use of Cerro KXL-510

cable in the primary containment and missing insulation refistance

measurements. In p eparing a justification for continued operation, the

, licensee determined that all plant cables associated with the instruments

i identified in the EQ Master List WCAP10-1-11 using the Cerro KXL-510

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compound are used only as thermocouple extension wires. The licensee

committed to establish qualifiability of the Cerro KXL-510 cable for

specific applicacion in the plant and ensure controls are in place to

limit use of this cable.

The NRC inspector reviewed the revised EQ file QDR 6.8 which demonstrates

the qualification of these cables. The QDR also indicates that there is

no equipment serviced by these cables in the containment which require

environmental qualification.

The cable usage review confirms that only the thernocouple extension wire

used ina Cerro KXL-510.

This item is closed.

(ClosedlUnresolvedItem 87-21-05 pertaining to potential effects of two

missing 0-ring seals on the acceptability status of level switches

23LS-91A&B, located in the crescent area to nitigate an in-containment

sr.all break LOCA.

The licensee determined the seals do not provide a safety function and

have been removed from the EQ pregram (ref. JTS-87-0418 Revision 1). The

switches are in an area where the only potential environmental change

wculd be a small change in air temperature but a significant increase in

radiation. The switches are not required for any HELB accident in the

Reactor Building. The licensee concludes that the omission of 0-ring

seals in the level switches does not impair the function of any component

important to safety during an postulated Reactor Bailding HELB.

This item is closed.

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(Closed) Violation 86-04-02 pertaining to the licensee identification and j

replacement of unqualified torque svlitches and limit switches in the

recirculation systems discharge and discharge by pass valves. The

licensee determined the torque switc5 and the limit switch contained

insulation which did not meet primary containment environmental  !

requirements. Test reports reference in the EQ files did not provide an i

adequate basis for qualification to 00R Guidelines.  !

The licensee replaced the unqualified components in Limitorque valve  !

Nos, 02 MOV-53 A, B, C, and D with components qualified to NUREG-0588 and  !

filed a Licensee Event Report (LER) No.87-007.  :

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This items is closed.

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4 Physical Inspection '

The inspectors examined three Limitorque installations in the drywell. i

Items examined include Limitorque Valve Nos. 02 MOV-53A & B and 12 MOV-15  !

located at elevation 300'-0". The valve operator 12 MOV-15 is one of  !

three new units installed during this outage. [

The inspectors examined internal wiring, T-drain installation, splices  !

and general installed configuration and orientation.

In one of the valves, No. 12 MOV-15 the inspector noted that the splice

configuration did not corroly with installation requirements for a

qualified splice. Procedure IS-E-03 Revision 1, paragraph H i.11 requires

two half-lapped layers of the T-95 (red) tape and two half-lapped layers  ;

of the T-35 (black) tape over the T-95 (red) tape.  ;

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The T-95 (red) tape was visible at the end of the splice configuration. I

Visual observatien of the half-lapped layers indicate much less overlay  !

(1/8-1/4 inch) than the required 3/8-1/2 inch half-lapped layers (as f

determined by width of tape).  !

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Licensee personnel present during this inspection acknowladge the [

finding. Further discussions with the licensee indicate contract personnel [

installing the Limitorque may have made the splice. Records indicate the i

splice was inspected and accepted by quality control inspection, j

The NRC inspector expressed concern over the control of work performed by  !

contract personnel, The licenste comitted to examine other similar  !

installaticns made during this outage. The plant is presently shut down i

and does not present a sa'ety hazard. i

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This ite'n is a violation of 10 CFR 50.49 requirement for maintaining the  :

qualified status of EQ equipment (50-333/83-25-01).  !

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5. Exit Meetino

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The inspector met with licensee personnel (denoted in Oetills, paragraph l

1) at the conclusion of the inspection on October 14, 1988, The  !

inspector summarized the scope of the inspection and the inspection

findings. At no time during the inspection was written rnaterial given to

the licensee.

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