IR 05000460/1980005

From kanterella
Jump to navigation Jump to search
IE Insp Repts 50-460/80-05 & 50-513/80-05 on 800331-0403.No Noncompliance Noted.Major Areas Inspected:Wkm Valve Flaw Indications,Pipe Support & Restraint Sys & Administrative Controls for Nonconforming Conditions
ML19310A130
Person / Time
Site: Washington Public Power Supply System
Issue date: 04/24/1980
From: Dodds R, Narbut P, Wagner W
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML19310A125 List:
References
50-460-80-05, 50-460-80-5, 50-513-80-05, 50-513-80-5, NUDOCS 8006060141
Download: ML19310A130 (6)


Text

_.

.

_

_ _ _ _ _ _ _ _ -

_

'

,.

i U. S.

UCLEAR FIGUIATORY COMMISSION

,

OFFICE OF INSPECTION AND ENFORCE E!.~r

REGION V

.

50-460/80-05 Report No.

50-513/80-05 Docket No.50-46A, 50-513 License No. ____ Lppp 134 p,174 Safeguards Group Licensce:

Washinaten Public Power Supply System P. O. Box 968 Richland. Washington 99352 Facility Nace:

Washinaten fluclear Proiects flo.1 A 4 (WflP 1 & 4)

Inspection at:

WIP 1/4 Site - Benton County. Washinoton

Inspection conducted: Ma'rch 31 - Aoril 3. 1980

@b

/

[.\\\\

Om fd- [y]

Inspectors:

P., P. flarbyt, eactor Insp'ector

')

u Date signed

,

I h! l. noer 4 /ze/so

'

W. Wagner, Reactor Idspectof Date Signed Date Signed Approved By:

I'

-

'

/ ate' Signed R. T. Dodds, Chief, Engineering Support Section D

c S u:=a ry :

Inspection during the period March 31 - April 3,1980 (Recort flos. 50-460/

,

80-05 and 50-513/80-05)

Areas Insoected:

Routine unannounced inspection by the regional based in-spectors of activities relating to niethods of nonconformance reporting and the associated record keeping activities, followup of investigations regard-ing safety related valves manufactured by WKM, and review of the quality assurance program and selected procedures related to safety related pipe support activities.

The inspection involved 43 inspector-hours onsite by two flRC inspectors.

Results:

No items of noncompliance or deviations were identified.Rv Form 219 (2)

80 06060 lSl

-

-

- -.

_ - - __.

DETAILS 1.

Persons Contacted The inspectors interviewed various engineering, management, inspection and supervision personnel of the organizations listed below.

Key per-sonnel including those who attended the exit interview are specifically identified below, a.

Washington Public Power Supply System (WPPSS)

  • A. D. Kohler, Project Manager
  • T. J. Houchins, Project QA Manager
  • M. E. Witherspoon, Manager of Quality Assurance
  • J. P. Thomas, Deputy Project Manager
  • G. K. Dyekman, Project Engineering Manager R. Webring, Nuclear Engr.

b.

United Engineers and Constructors (UE&C)

  • E. C. Haren, Deputy Project QA Manager J. Lancon, Lead QA Engr. (Mech.)

J. R. Mayne, Construction Management Engineer c.

J. A. Jones Construction Company (JAJ)

B. Roe, Project QA Manager

'

.

J. Felder, QA Engineering, Supervisor

  • Denotes attendance at the exit interview on April 3,1980. Mr.

A. Toth, USNRC Resident Inspector for WNP 1/4, attended the exit interview.

-

2.

, Construction Status Licensee representatives reported that as of February 29, 1980, construc-tion of WNP-1 was 37.8% complete, and WNP-4 was 15.0% comolete.

3.

Site Tour Upon arrival at the site, the inspectors toured the WNP-1 plant area to observe construction activities, completed work, equipment storage ar.d housekeeping. No items of noncompliance or deviations were ident-ified.

4.

Licensee Action on Previous Inspection Findinas a.

(0 pen) Unresolved Item - Welder performance cualification record not available for review (50-460/79-10/02).

.

. -. -

-

..

.

-.

._-

--

.

._

.

-2-The welder performance qualification record (PQR) corresponding to the radiographic test sheet for welder number A-5 dated December 5,1978 for position 6G was missing, as documented in NRC inspection report 5'j-460/80-02. The missing POR could not be lo-cated during this inspection. Therefore, this item will remain unresolved pending review of the PQR.

b.

(0 pen) Open Item - WKM Valve Flaw Indications - 50.55e (50-460/

80-02/0_1).

The existence of unacceptable linear indications-in WKM valve castings was reported by the licensee to the Resident Reactor Inspector on December 7,1979. This was described in NRC inspec-tion report 50-460/79-13. An interim report of these flaw indica-

-

tions was received by the NRC on January 14, 1980. According to the interim report the licensee is in process of prepa,ing

!

a repair program to meet the requirements of ASME Section XI.

Also, as noted in NRC inspection report 50-460/80-02, the repair program will include all valves (28) supplied by WKil.

The repair plan, " Repair Plan for WKM Manufactured Class 1 and 2 Valves" of February 4,1980, was reviewed for proper approvals and technical content. The repair plan was written by B&W with final approval by the licensee. The inspector observed that the repair plan did not address the effects of sensitization on the stain-less steel valve body resulting from the weld repair. Also, the inspector questioned what measures had been taken to assure that WKM's apparent quality assurance program breakdown has not affected other materials, parts or components of these valves.

At the exit interview licensee management comitted to address these items in the final 50.55e report. This item remains open pending review of licensee action in this area and implementation of the repair program.

5.

Safety-Related Pipe Support and Restraint Systems - Unit 1 a.

Review of Ouality Assurance Imolementing Procedures The inspector examined the J. A. Jones QA manual, " Nuclear Quality Manual for ASME Section III Division 1" Revision 3 of October 19, 1979. The QA manual was reviewed to ensure that adequate provisions are established for safety-related activities and conformance to Code requirements. The licensee is committed to the ASME B&PV Code Section III Part NF 1977 Edition through Sumer 1977-Addend '

.

-3-Six J. A. Jones work procedures-pertaining to safety-related pipe support and restraint systems were examined and found to have been approved by authorized licensee personnel.

flo items of noncompliance or deviations were identified.

6.

Administrative Controls for Nonconforming Conditions The inspector examined the licensee's methods of administering controls for the reporting and evaluation of nonconforming conditions in the area of piping, component installation and supports.

a.

Procedure Review The inspector examined the following procedures for conformance to the licensee's commitments in Chapter 17 of the PSAR.

1)

JAJ Procedure flo. P0P-ti-312W Rev.1D of 7/16/79 - Request for Information 2)

JAJ Procedure No. P0P-N-300W Rev. 3A of 12/6/79 - Control of Engineering Documents

'

3)

JAJ Procedure No. P0P-N-703W Rev.1A of 8/8/79 - Nonconform-ance Reporting 4)

Procedure No. FGCP-35 Rev. 5 of 12/3/79 Initiation and Proc-essing of Field Change Notices (FCN)

5)

Procedure No. FGCP-20 Rev. 7 of 3/30/77 - Field Initiation and Processing of Project Change Requests I

i

)

i

'

..

-4-No items of noncompliance or deviations were observed.

b.

Review of Nonconformance reports (NCR's)

The inspector examined a sampling of CNCR's (contractor noncon-formance reports) for Unit 1 written by J. A. Jones Inc. Quality verification (QV) inspectors. J.A. Jones, per contracts 211 and 257, performs the installation of safety related and reactor coolant pressure boundary components, piping and supports.

The inspector examined 15 CNCR's in detail to determine compliance with the requirements of Procedure P0P-N-703W.

The inspector examined the CNCR loc for the months of January, February and March 1980 for Unit 1.

There were 228 CNCR's written during)that time period. Thirty-three CNCR's (14% of the 228 CNCR's involved nonconformances dealing with bypassed hold poirts.

The subject of bypassed hold points was previously addressed in IE Inspection report 50-460/80-01 for the period August 1979 to January 1980.

The continuation of significant numbers of CNCR's dealing with bypassed hold points in the months of February and March 1980 indicates that the correttive actions taken by the lice'nsee to resolve this problem do not appear to be effective. At the exit inter-view licensee management stated the actions were already under way to resolve this problem. This item will be inspected fur-ther in a future inspection. This item is considered unresolved (Item 50-460/80-05/01).

No items of noncompliance or deviations were identified.

c.

Review of Requests-for-Information (RFI's)

The inspector examined the RFI's issued for Contract 211 for Unit 1 for November and December 1979 for conformance to the require-ments of J.A. Jones procedure, P0P-N-312N Rev. 1D.

There were a total of 39 RFI's reviewed.

In six cases there were RFI's which appeared to be items which should have been NCR's rather than RFI's in that RFI's are requests for clarifications only and are not intended as a method of reporting nonconforming conditions. The six RFI's which noted apparent nonconformances were: RFI's 211-79-191; 201; 203; 206; 207 and 209.

In all six cases, the apparent nonconformances dealt with items not constructed by JAJ but items which JAJ had to interface with such as columns, pads etc.

s

__

_ _.

.-

-5-Additionally, three of the 39 RFI's (211-79-221, -213 and -207)

were answered by UE&C engineers specifying work to be perfonned.

Generally, Field Change Notices (FCN's) are issued to perform work (per FGCP-35) rather than RFI's.

The inspector expressed concern about the use of RFI's to document nonconformances and to specify work since RFI's and their answers are not reviewed by the licensees QA organizatiJn as are CNCR's or FCN's.

At the exit interview, licensee management comitted to investigate the RFI situation and take appropriate actions.

This item will be examined further during a future inspection (Item 50-460/80-05/02).

7.

Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of non-compliance, or deviations.

An unresolved item disclosed during this inspection is discussed in Paragraph 6.b. of this report.

8.

Management Interview The inspectors and the NRC Resident Inspector met with the licensee representatives (denoted in Paragraph 1) on April 3,1980.

The scope of the inspections and inspectors findings as noted in this report were discussed.