IR 05000530/1985020

From kanterella
(Redirected from ML20137M835)
Jump to navigation Jump to search
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)


Text

7

.

.

U. S. NUCLEAR REGULATORY COMMISSION

REGION V

Report N /85-20 Docket N Construction Permit N CPPR-143 Licensee: Arizona Nuclear Power Project P. 0. Box 52034

'

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

.

$

. 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 covere Results: No violations of NRC. requirements or deviations were identifie PDR ADOCK 0 % y0 O

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

l

..

%

DETAILS Persons Contacted Arizona Nuclear Power Project (ANPP)

s

  • B.' Karner, Assistant Vice President, Nuclear Production
  • 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 Bechtel Power Corporation (Bechtel). ,
  • G. A. Hierzer, Field Construction Manager
  • 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- .

,

J. Yoshida, Mechanical Engineer R. Kumbla, Lead F,ield. Engineer

'

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

  • Denotes those attendin'gethe exit interview on August 15, 198 . Ins'trument Component t and Systems Work Observation

' ' Receiving Inspection _

'

No safety-related iastrument components were received during this

-

inspection'. . The. inspector conducted a' detailed inspectica of receiving and storage activities during March 1981; this is

~

-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 fo 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 reviewe MRR N Instrument Component

'183566 LT-1124B

'

.161785 PT-352C 166567 Instrument Racks SBA-A01 and SBB-A01 168416 Instrument Racks SBC-A01 and SBD-A01

.

w

2

.

.

Receiving inspections was performed for damage, storage classification, identification and marking, and documents receive 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 documentatio 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 designation (2) Components are properly identifie (3) Storage conditions (temperature, humidity, cleanliness, etc.)

are controlled and monitore (4) Nonconforming items are identified and segregate (5) An adequate number of qualified personnel are available to perform.the; required storage functio Completed Work The following installed instruments were selected for inspection:

Instrument Transmitter System ^

Number Description Channel

-

,

n '

i Reactor Trip ;

J-RCN-PT-101A Pressurizer A

,, (SCRAM)~ ,J-RCB-PT-101B Pressure B Initiai.iori . i"

'

J-RCA-PT-102A A c! J-RCD-PT-102D

' '

,

'

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

-

. J-HCD-PT,-352D D

^

"

Display J-SGB-LT-1124B Steam Generator B Instrumentation No.2 Level 1-

, ,

  • f

.

.

,

. ,

<

s

,

'

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 N N Title E-14272-510-006 3 Transmitter Configuration for Mounting Bracket E-14273-510-011 5 Instrument Rack Assembly and Details Bechtel Drawing N 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 drawing s (2) Instruments were correctly and permanently identifie (3) Instruments were not exposed to potential hazards such as high-pressure piping or flammable materia (4)= Physical and electrical independence between redundant parts were properly maintaine 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

,( -

, r

.

, , 9 '

. o

,, - , ' 4 i #.

\ * #

%

~

. ; l__ *n .* A > '

l *

. _ _

, .

"

o 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 anothe In this instance MCN-60196-J was issued to obtain a replacement pressure transmitter from Unit 3 for use in Unit Construction Testing and Calibration This activity is no longer being performed by construction. All testing and calibration activities are done by the startup grou 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. discovere 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 '

. ,

a

&

4 *

. v t

.I .

,

,

.

..

(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"

~

(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"

,

(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

-

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 specification 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 drawing No violations of NRC requirements or deviations were identifie . 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 discusse ,