IR 05000553/1979006
| ML19259C607 | |
| Person / Time | |
|---|---|
| Site: | Phipps Bend  |
| Issue date: | 05/30/1979 |
| From: | Herdt A, Wright R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19259C606 | List: |
| References | |
| 50-553-79-06, 50-553-79-6, 50-554-79-06, 50-554-79-6, NUDOCS 7907260142 | |
| Download: ML19259C607 (6) | |
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REGION 11
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ATLANTA, GEORGIA 30303
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Report Nos. 50-553/ 79-06 and 50-554/79-06 Licensee: Tennessee Valley Authority 500A Chestnut Street Tower II Chattanooga, Tennessee 37401 Facility Name:
Phipps Bend Nuclear Plant, Units 1 and 2 Docket Nos. 50-553 and 50-554 License Nos. CPPR-162 and CPPR-163 Inspection at Phip s Bend Si e near Kingsport, Tennessee Ihh77 Inspector:
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R. W. Wright
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Date Signed Accompanying Per 1-H. Thomas Approved by:
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A. R. Herdt, Section Chief, RCES Branch Date Signed SUMMARY Inspection on May 8-11, 1979 Areas Inspected This routine, unannounced inspection involved twenty nine inspector hours onsite in the areas of licensee action on previous inspection findings; construction engineering personnel changes; the handling of licensee identified items (LII);
the review of licensee QA manuals pertaining to containment steel structures and other safety related steel structures and supports, reactor coolant pressure boundary piping, other safety related piping and the welding associated with those items.
Results Of the four areas inspected, no apparent items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Emplcyees
- W. P. Kelleghan, Project Manager
- G. Wadewitz, Construction Engineer
- J. C. Cofield, Assistant Construction Engineer, PE
- T. V. Abbatiello, Assistant Construction Engineer, QC
- D. E. Hitchcock, Site QA Unit Supervisor
- J. Wills, Power-Reg Staff Engineer J. A. Crittenden, Electrical QC Unit Supervisor W. K. Burner, Welding QC Unit Supervisor E. J. Barnett, Project Engineering Mechanical Unit Supervisor J. Houck, Storage, Records Clerk, DCV Other Organizations A. G. Bishop, General Electric Company Field Representative
- Attended exit interview
- Participated in exit interview by telephone, J. E. Wills, Power-Reg Staff Engineer 2.
Exit Interview The inspection scope and findings were summarized on May 11, 1979 with those persons indicated in paragraph I above. The licensee was advised that no new items of noncompliance or deviations were identified by this inspector.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Infraction 553/79-02-01:
Replacement of 3-inch aggregate with 1 1/2 inch. RII received TVA's letter of response dated March 15, 1979 on the subject matter. The licensee requested that C. F. Braun approve the substitution of 1 1/2 inch agggregate in lieu of 3-inch aggergate presently called for in Specification 300-01, " Concrete".
The RII inspector examined CF Braun approved engineering change notice (ECN2) dated February 13, 1979, which permits the tequested substitution.
In addition on April 13, 1979 TVA reemphasized to appropriate site personnel the need to obtain approval of field initiated changes in accordance with CEP-3.01, Field Change Request, prior to starting any field work to prevent recurrence of similiar problems. This meeting was documented in a Phipps Bend Construction File Note dated April 16, 1979. This item is closed.
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b.
(0 pen) Unresolved item 553-554/78-08-03: Inadequate concrete sampling specification and instruction. IE Report 50-553/554/79-02 incorrectly reported that the licensee was taking samples for strength tests for each design mix poured that day and for each 150 cubic yards of concrete of each design mix placed, i.e. in accordance with ACI 318-71. Actually, the site is sampling each design six for all mixes poured that are less than 100 cubic yards and thereafter sampling each design mir at 300, 200 and 150 cubic yard intervals for the following respective specified strengths of 2000 psi, 3000 psi, and 3000 plus psi. Phipps Bend site sampling being implemented to date exceeds their requirements as specified in QCI C-208 Rev. 4 dated March 7,1978.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Review of QA Manual: Containment steel structure and supports, welding and penetrations; Safety related structures - steel structures, supports and welding; Reactor Coolant Pressure Boundary Piping and welding; Safety related Piping and Welding.
The purpose of this inspection is to ascertain whether QA plans, instruc-tions, and procedures have been established in the f acility QA manual (aggregate manuals) and that they conform to the QA program as described in the Safety Analysis Report.
General TVA's Division of Engineering Design (DED) has the respcasibility for design of the turbine building and balance of plant.
TVA purchased the Standard Reactor Island Design (STRIDE) package from General Electric (GE)
which consists of detailed designs for the reactor building, fuel building, auxiliary building, the radwaste buildings control building, and the diesel generator buildings.
C. F. Braun and Company (CFB) is subcontracted to GE to provide engineering services related to the design of these STRIDE buildings. TVA's Division of Construction (DEC) has the responsibility for construction of the entire plant. TVA's Material Services, Mechanical and Welding Quality Control Units will perform the QC and NDE functions for their respective work activities. QC inspections are to be performed in the field by qualified personnel during such construction quality activities as receiving, storage, fabrication, erection, installation and testing.
TVA's site QA Unit is responsible to perform planned and periodic audits of all construction activities including activities performed by site contractors.
Audit results are documented and reviewed by management.
The following QA/QC manual (s), procedure (s) and construction specification constitute the QA program documents:
QA program Requirements Manual for Design Procurement, Construction a.
(PRM)
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TVA DEC Quality Assurance Program Policy Manual (QAPP)
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TVA DEC Quality Assurance Staff Manual (QASP)
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TVA DEC Quality Assurance Training Program Plan (QATPP)
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OEDC OA Manual for ASME Section III Nuclear Powet Plant Components (NCM)
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Interdivisional QA Procedures Manual (IPM)
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Construction Engineering Procedures Manual (CEP)
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Quality Control Instruction Manual (QCI)
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Receiving Inspection Storage Preventive Maintenance Manual (Welding, NDE, Mechanical) (RIS &PM)
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TVA STRIDE Specification Series 100, 300 and 400 k.
TVA's General Construction Specification G-27, 28 and 29 Implementation Inspection The inspector held aiscussion with responsible licensee personnel, reviewed controlling specifications, QA manuals procedures, and observed that facili-ties are provided for the support of the requirements of the above documents.
The above identified documents confirm that the licensee has established QA/QC plans and procedures to assure that containment, other safety related structures, reactor coolant pressure boundary piping and other safety related piping work will be accomplished in accordance with the QA program requirements. The following areas were examined:
Organizational structure and QA personnel Audits Corrective Action Document Control Quality Records No items of noncompliance or deviations were identified 6.
Construction Engineering Personnel Changes Construction Engineering Procedure CEP 1.01 describes the Construction Engineering (CE) Organization for Phipps Bend Nuclear Plant and defines the duties and responsibilities of CE personnel in relationship to quality assurance functions at the site. The following staffing changes have been 2100 241
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executed in accordance with the subject procedure.
J. C. Cofield and T. Abbatiello were promoted to Assistant Construction Engineer positions in Projects and QC Engineering Sections respectively.
B. Andrews is now the Materials Services Unit Supervisor and H. Lollar and G. Hogg were selected to fill the Mechanical and Materials & Civil QC unit supervisor positions vacated by Abbatiello and Cofield respectively.
7.
Licensee Identified Items (LII)
Prior to the inspection, the licensee identified several items which were considered pontentially reportable under 10CFR 50.55(e). The items are as follows:
a.
(Closed) Items 553-554/78-03-01:
Inadequate review of certain design activities.
The inspector reviewed certain design activities. The inspector reviewed the TVA responses to Region II dated February 6, July 3, August 28, and October 30, 1978, for NCR M77-7. The inspector reviewed current revisions to the engineering procedures (EP) 1.26, 2.02, 4.02, 4.03, 4.10, 5.34, 5.44 6.01; OEDC QA procedure QAS-QAP 3.1 and Const QA procedure QAP 18.01 noted in the corrective action proposed in the final report. These revisions provide for reviewing, identifying, documenting (including the cause of deficiency) analysing the repetitive deficiencies, and reporting of deficiencies to the NRC. RII has no further questions regarding this matter at this time.
b.
(Open) Item 553-554/78-08-02: Personnel airlock components procr. red to non-stfety Class 2 requirements.
The licensee has issued cwo interims reports on this matter, dated November 2,1978 and Februsry 15, 1979. The licensee's last report indicated that a final report, will be transmitted on or before August 16, 1979. This item will remain open pending receipt and review by Region II of the licensee's final report in the matter.
c.
(Closed) Item 553-554/79-06-01: BWR/6 HPCS Local Control Panels. On March 6,1979, TVA notified RII of a potentially reportable condition regarding differential relays type CFD on the high pressure core spray local control panel H22-P028 failing to pass seismic qualification testing.
The licensee submitted a final report on this deficiency dated April 5,1979. The subject defect was discovered before Phipps Bend Unit I and Unit 2 HPCS Local panels were shipped from GE to TVA.
GE has notified the appropriate TVA personnel of this situation and is in the process of purchasing seismically qualified differential relays for replacement of the defective relays.
The new relays will be installed in all panels by December 1, 1979.
To preclude recurrence condition release procedure which of the matter GE has written a requires GE's project manager's signature certifying the correctness of the component prior to its shipments. This item is also being tracked by GE procedure 7042 for identifying potential reportable deficiencies. This item is opened and closed in this report.
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(0 pen) Item 553-554/79-06-02: Lower than required factor of safety for actual design of welded anchorages. On May 7, 1979, the licensee notified RII that their Civil Engineering Branch review of anchors and plates revealed that if plates acted flexibily cracking could occur due to stress concentrations in a zone of brittleness (heat affected zone). TVA reported that a smaller load carrying capability occurs which also results in a lower factor of safety than required by TVA Specifications. A writtern report is due June 6,1979.
(open) Item 553/79-06-03: Piping elbows made of unspecified materials e.
(Tube Turns). On April 25, 1979, TVA notified RII that the received a letter from Guyon Industrires requesting the return of piping fitting manufactured by Tube Turns.
A U. S. Steel representative examined suspect fittings onsite and found one of eighty-two, 4 inch, 45 degree elbows nonconforming. TVA plans to submit a report on this subject by May 25, 1979.
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