ML20137M835

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Insp Rept 50-530/85-20 on 850729-0802 & 12-16.No Violation or Deviation Noted.Major Areas Inspected:Activities Re Instrument Components & Sys
ML20137M835
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 08/28/1985
From: Miller L, Wagner W, Thomas Young
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20137M833 List:
References
50-530-85-20, NUDOCS 8509130384
Download: ML20137M835 (6)


See also: IR 05000729/2008002

Text

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U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report No. 50-530/85-20

Docket No. 50-530

Construction Permit No. CPPR-143

Licensee: Arizona Nuclear Power Project

P. 0. Box 52034

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Phoenix, Arizona 85072-2034

Facility Name: Pal"o' Verde Nuclear Generating Station - Unit 3

Inspection at: . Pal'o' Verde' Site, Wintersburg, Arizona

Inspection conducted: July 29.- August 2 and August 12-16, 1985

Inspectori .

.

Qagner,' Reptor Ins fee r

/ Date Signed

Approved By: ~^

t

. M

T. Young, Jr.', Chyf Date Signed

Engineering Section

.

$

. F. iller, 'Jr. // Chief . '

Date Signed

Reactor Projects Fection 2 '

Summary:

Inspection on July 29 - August 2 and August 12-16, 1985

(Report No. 50-530/85-20)

Areas Inspected: Routine unannounced inspection by a regional based inspector

of activities associated with instrument components and systems. The

inspection involved 75 inspector-hours by one NRC inspector. During this

inspection, Inspection Procedure 52053 was covered.

Results: No violations of NRC. requirements or deviations were identified.

8509130384 850820

PDR ADOCK 0 % y0

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L_________-_____ _ _ _ _ - - _ _ __ . __ - - -

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DETAILS

1. Persons Contacted

a. Arizona Nuclear Power Project (ANPP)

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  • D. B.' Karner, Assistant Vice President, Nuclear Production
  • W. E. Ide, Director,' Corporate QA/QC'
  • C. N. Russo, Manager, Quality Audits and Monitoring
  • S. G. Penick, Quality Monitoring Supervisor
  • R. M. Butlar, Director, Technical Services
  • J. R. Bynum, Plant Manager

J. D. Bayless, Quality Assurance Engineer

W. Montefour, Quality Assurance Engineer

b. Bechtel Power Corporation (Bechtel). ,

  • G. A. Hierzer, Field Construction Manager
  • T. L. Horst, Project Field Engineer
  • H. A. Hear, Assistant Project QC Engineer-
  • R. E. Vote, Assistant Project QA Manager

K. N. Bethell, Instrument Area Field Engineer

R. L. Treaster, Shipping and Receiving Supervisor

L. R. Eton,. Calibration Lab Engineer- .

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J. Yoshida, Mechanical Engineer

R. Kumbla, Lead F,ield. Engineer

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iT.. Weber, Lead-Mechanical'Engi,neer

  • Denotes those attendin'gethe exit interview on August 15, 1985.

2. Ins'trument Component t

and Systems Work Observation

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a. ' Receiving Inspection _

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No safety-related iastrument components were received during this

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inspection'. . The. inspector conducted a' detailed inspectica of

receiving and storage activities during March 1981; this is

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-documented in NRC Report Nos. 50-529/85-13 and 50-530/85-06.~ To

assure that~the administrative controls were currently being

affectively implemente'd the; inspector observed receiving inspection

activities. . Components were'being properly identified,

nonconforming components ccutrolled, and an adequate number of

qualified personnel were available- to perform the receiving

inspection functicn. The inspector-reviewed the quality records for.

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evidence that receiving inspection was performed for the installed

instrument components identified in.Section 2.c of this report. The '

folle.ing Material' Receiving Reports (MRRs) were reviewed.

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MRR No. Instrument Component

'183566 LT-1124B

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.161785 PT-352C

166567 Instrument Racks SBA-A01 and SBB-A01

168416 Instrument Racks SBC-A01 and SBD-A01

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Receiving inspections was performed for damage, storage

classification, identification and marking, and documents received.

A nonconformance report was written on MRRs 116567 and 168416 (NCR

No. 1203) for documentation not received. This NCR was subsequently

closed upon receipt of the documentation.

b. Storage

None of the type of instrumentation selected for this inspe tion

were located in storage. However, observation and evaluation of

storage activities for. Other safety-related instrument components

revealed the-following:

(1) Instruments are stored in proper storage level designations.

(2) Components are properly identified.

(3) Storage conditions (temperature, humidity, cleanliness, etc.)

are controlled and monitored.

(4) Nonconforming items are identified and segregated.

(5) An adequate number of qualified personnel are available to

perform.the; required storage function.

c. Completed Work

The following installed instruments were selected for inspection:

Instrument Transmitter

System ^

Number Description Channel

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,

n '

i Reactor Trip ;

J-RCN-PT-101A Pressurizer A

,, (SCRAM)~ ,J-RCB-PT-101B Pressure B

Initiai.iori . i"

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J-RCA-PT-102A A

c! J-RCD-PT-102D

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'

D

,,

J-RCD-PT-101D D

, Engineered J-HCA-PT-352A Containment A

. Safety-Featurese J-HCB-PT-352B Pressure B

. Actuation _ ~

J-HCC-PT-352C C

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. J-HCD-PT,-352D D

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Display J-SGB-LT-1124B Steam Generator B

Instrumentation No.2 Level

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Th$-location, configuration.'and installation of these instruments

were in accordance with the following approved design drawings

utilized during this inspection:

Combustion

Engineering Revision

Drawing No. No. Title

E-14272-510-006 3 Transmitter Configuration

for Mounting Bracket

E-14273-510-011 5 Instrument Rack Assembly

and Details

Bechtel

Drawing No.

13-J-ZZS-167 6 Instrument Mounting Assembly

Rosemount TransmittLr

13-J-01D-105 5 Auxiliary Building Isometric

13-J-01D-106 4 Sensing Lines

13-J-03D-117 5 Containment Building

13-J-01D-133 4 Isometric Sensing

13-J-01D-138 4 Lines

13-J-01D-140 4

13-J-01D-116 4

13-J-01D-103 3 Auxiliary Building

13-J-01D-104 3 Isometric Sensing Lines

13-J-ZAF-013 6 Auxiliary Building

13-J-ZAF-013 5= Instrument Location Plan

13-J-ZCF-004 8 Containment Building

13-J-ZCF-007 6 Instrument Location Plan

13-J-ZCF-008 7

Inspection of the installed instruments' revealed the following:

(1) A11' instruments were as specified on the design drawings.

s

(2) Instruments were correctly and permanently identified.

(3) Instruments were not exposed to potential hazards such as high-

pressure piping or flammable material.

(4)= Physical and electrical independence between redundant parts

were properly maintained.

Two of the instruments selected for this inspection were recently

removed. Pressure transmitter number RCA-PT-101A was removed for

rework in accordance with NCR No. JC-1065. Review of this NCR

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revealed that the instrument was returned to the vendor for

recertification in response to a 10 CFR Part 21 report. Pressure

transmitter RCD-PT-101D was removed as a result of a Material Change

Notice (MCN) No. 60196-J. The MCN is the controlling mechanism

utilized to transfer material and equipment from one unit to

another. In this instance MCN-60196-J was issued to obtain a

replacement pressure transmitter from Unit 3 for use in Unit 2.

d. Construction Testing and Calibration

This activity is no longer being performed by construction. All

testing and calibration activities are done by the startup group.

e. Instrument Air System

The instrument air system is not safety-related; however, it is

important to safety because instrument air is used for

safety-related control components. The major component of the

instrument air system selected for inspection was an air compressor

identified as IAN-COIC, R2T. The inspector utilized the following

design / installation drawings to verify proper location and

'

installation of the air compressor:

(1) Drawing No. 13-M-IAP-001 Revision 13, "P&ID Diagram Instrument

and Service Air System"

(2) Drawing No. 13-P-ZTL-401 Revision 5, " Equipment Locations

Turbine Building Plan"

,

(3) Drawing No. 13-C-ZTS-101 Revision 22, " Turbine Building

Foundation Mat Plan Area TIA, B&C"

The inspector observed that the air compressor was correctly and

permanently identified. In addition, the inspector was able to

verify correct location and configuration of the air compressor,

including anchor bolt locations, by performing physical measurements

within the Turbine Building. The air compressor was correctly and

permanently identified.

'

The inspector reviewed the inspection reports, called CIPs

(Construction Inspection Planning) associated with installation of

the air compressor. The CIP of May 21, 1981, was for inspection of

equipment installation which covered installation of anchor bolts,

and equipment location and orientation. Angular alignment and

i offset (parallel) alignment was performed and documented on CIP of

August 25, 1981. An additional CIP was initiated on May 17, 1984,

for equipment inspection as a result of internal corrosion being

discovered in the Unit.2 air compressors. CIP No. 156.0-301 was

written for. inspection of Unit 3 air compressors for evidence of

corrosion; no' corrosion was. discovered.

In addition ~to the above equipment inspection, the inspector  !

performed a lwalkdown inspection of approximately 45 feet of .

instrument air; tubing. This activity was conducted from header '

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(Root) valve V-872 to safety-related valves UY648 (Solenoid) and

UV648 (Control) located in the safety injection system. The

following drawings and specifications were utilized for verification

of the valves and associated air lines:

(4) Drawing No. 13-M-SIP-002 Revision 11, " Safety Injection and

Shutdown Cooling System"

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(5) Drawing No. 13-P-SIF-103 Revision 17, " Containment Building

Isometric-Safety Injection System"

(6) Drawing No. 13-P-IAF-177 Revision 2, " Containment Building

. Isometric-Service Air System Instrument Air"

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(7) Drawing No. 13-J-100.099 Revision 7, " Instrument Installation

Notes - Pneumatic"

'(8)-DrawingNo.13'-J-ZZS-092 Revision 10,"Instrumentsand

Controls,' General Installation Notes"

(9) Specification'No. 13-JM-702 Revision 7, " Installation

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Specification for~ Instrumentation and Controls"

. Instrument air tubing is' field routed which means that the tubing is

installed from' support to-support at the discretion of the field

engineer as long as the' installation is in accordance with the

requirements contained in the above drawings and specifications.

Attributes verified were minimum length of the unistrut supports,

embedment. length, minimum weld length, and where applicable, the

anchor bolt spacing distance. The safety-related valves were

correctly identified and located in accordance with the construction

drawings.

No violations of NRC requirements or deviations were identified.

3. Exit Meeting

The inspector met with licensee management representatives denoted in

paragraph 1 on August 15, 1985. The scope of the inspection and the

inspector's findings as noted in this report. were discussed.

,