ML20150F382

Amend 40 to License DPR-50,reducing Allowable Measured Neutron Flux Tilt,Allowable Axial Power Imbalance & Allowable Position Limits for Axial Power Shaping Rods

ML20150F382
Person / Time
Site:	Three Mile Island
Issue date:	05/19/1978
From:	Reid R Office of Nuclear Reactor Regulation
To:
Shared Package
ML19210A291	List: ML20150F382
References
NUDOCS 7910290536
Download: ML20150F382 (8)

Text

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1. p aaeg o '@ UNITED STATES

1. NUCLEAR REGULATORY COMMISSION S I REGION ll Q, 101 MARIETTA ST., N.W., Sulf E 310o

%, * . . . f[ ATLANTA, G EORGIA 3o3o3 Report No. 50-553/79-12 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37431 Facility Name: Phipps Bend Unit 1 Docket No. 50-553 License No. CPPR-162

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Inspection at Cb) a 4 on Nuclear - Memphis, Tennessee Inspectea by: ' / f m m ,[ '

i MO, 6M orge Da@ Signed h.

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79 Cro ley ~ ' Da'te Signed Approved by:  !' k A. R. lierdt, S'ection Chief, RC&ES Branch h

Date Signed

SUMMARY

Inspected on August 7-9, 1979 Areas Inspected '

This routine, unannounced inspection involved 44, inspector-hours at Chicago Bridge and Iron Nuclear in the areas of preservice inspection - Review of Program and Procedures, and Observation of Work and Work Activities.

Results In the area inspected, one apparent item of noncompliance was found (Inf raction -

Failure to 0btain Inspection Plan Approval - Paragraph 5) 7010250 l J ,

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DETAILS

1. Persons Contacted Licensee Employees

• G. L. Belew'- Mechanical Engineer Rockwell International

• T. G. Parker - Site Representative

• G. J. Hallinan - Project Engineering

• D. C. Empey - Manager Qaality Assurance Engineering EBASCO Services

• D. G. Nuzzo Jr. - Site Eupervisor Authorized Nuclear Inspector

• J. L. Walker Other contractor employees contacted included 7 technicians.

• Attended exit interview

2. Exit Interview The inspection scope ano findings were summarized on August 9,1979 with those persons indicated in Paragraph 1 above. One inspector follow-up item was identified and discussed in detail. This item was changed to an item of noncompliance and the licensee notified by telephone on August 13, 1979.

No dissenting comments were received from the licensee.

3. Licensee Action on Previous Inspection Findings Not inspected.

4. Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or deviations. One new unresolved item identified during this inspection is discussed in paragraph 7.

S. Preservice Inspection - Review of Program The applicable Code for preservice and inservice inspection is the ASME D acd PV Code Section XI 1974 Edition through summer 1975 Addenda as imp'emented by TVA QA Program.

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While inspecting the Preservice Inspection of the reactor pressure vessel, the inspectors reviewed the below lasted documents to ascertain whether the Preservice Inspection (PSI) Program had been approved by the licensee and whether adequate QA plans and procedures had been established (written, reviewed, approved and issued) to assure that, organization structure and QA personnel, audits, general QA requirements, work and quality inspection procedures, control of processes, corrective action, document control, examination control and control of examination equipment, qualtty records, and qualification of personnel were controlled and accomplished. The following documents were examined.

a. TVA letter of July 18,1979 f rom 11. J. Green to T. G. Pa rker.

b. Rockwell International " Quality Assurance Program Plan for Preservice and Inservice Inspection Programs" N00lPP100-017 Rev. C of March 9, 1979.

c. Energy Systems Group, Rockwell International "ASME Code Section !!!

Division 1 Manual" Edition III of May 25, 1979.

d. Rockwell International QA0P N1.04, " Quality Assurance Audits."

e. Rockwell International QA0P N1.05, " Qualification of Audit Personnel." l l

f. Rockwell International QA0P N3.00, " Calibration of Measuring and Test Equipment."

g. Rockwell International QA0P-N6.02, " Qualification and Certification of NDE Personnel."

h. Rockwell International QA0P-N6.03, " Qualification of NDE Procedures."

Within the areas examined the inspectors noted August 9,1979, that Rockwe!!

International was inspecting to an informal inspection p'.an not approved by TVA. The above is contrary to Paragraph Nos. 11.2.1 anJ 15.2.1 of Rockwell International Quality Ass'irance Program Plan for Preservice and Inservice Inspection Programs N00lPi100-017 Rev. C. The above is in noncompliance with 10 CFR 50 Appendix B Criteria VI. This is an infraction and was assig cd itew number 553/79-12-01 " Failure to Obtain Inspection Plan Approval"

6. Ereservice Inspection - Review of Procedures The inspectors reviewed the preservice inspection procedures indicated in the following paragraphs to determine whether the procedures w$re consistent with regulatory requirements and licensee commitment. See paragraph 5 above for the applicable code.

, a. The following procedures were reviewed in the areas of procedure approval, requirements for qualification of NDE personnel, and procedure scope: i Procedure Number Title N318TP000001, Rev. A Ultrasonic Examination of Reactor Vessel Welds (Phipps Bend)

ISI-UT-76-1, Rev. 8 Ultrasonic Manual Examination of Pipe and Safe-End Welds ISI-UT-76-2, Rev. 9 Ultrasonic Manual Examination of Reactor Pressure Vessel Welds ISI-UT-76-4, Rev. 9 Ultrasonic Manual Examination of Nozzle-to-  :

Reactor Vessel Welds ISI-UT-79-2, Rev. 1 Strip Chart Recording of Ultrasonic Indications -

b. Procedure Nos. N318TP000001 and ISI-UT-76-2 were reviewed for technical i content in the areas of type of apparatus, extent of coverage, calibra-tion requirements, size and frequencies of search angles, methods of  ;

compensation for metal distance traveled by ultrasonic beam, reference level for monitoring discontinuities, method of demonstrating penetra-tion, limits for evaluation and recording of indications, method of -

recording significant indications, and acceptance limits.

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c. Procedure hos. N318TP00001 and ISI-UT-76-2 were reviewed in conjunction (

vith the QA Manual to determine if compilation of required recerds were specified.

In the areas inspected, no items of nor. compliance or deviations were identi-fied.

7. Preservice Inspection - Observation of Work and Work Activities The inspectors observed the preservice activities described below to deter-mine whether these activities were being performed in accordance with regulatory requirements and licensee approved program and procedures. See paragraph 5 above for the applicable code.

a. Personnel qualification records for two Level 1, one Level II and two

. Level III examiner were reviewed.

b. In-Process ultrasonic examination, including portions of the calibra-tion sequence were observed for the following welds:

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$ (1) Weld AE (Flange to Vessel Shell 300'-330') straight and angle

, beam with manual equipment j

j (2) Weld BR (Vertical) angle beam with manual equipment.

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. (3) Weld BD 1-1 (vertical) straight and anglA beam with automatic .

equipment. $

The above Linspections were compared with the applicable procedure in the following areas:

_Use of specified type of apparatus Extent of coverage and scanning technique '

Calibration method including frequency and use of regt. ired calibration block Size and frequencies of search units Beam andes and DAC curves Definition of reference level for monitoring discontinuities Demonstration of penetration Limits for evaluating and recording indications Acceptance limits Use of instruction manual or prograra procedure l'

Personnel thoroughly fa:siliar with inspection system Examination provides for 100% volumetric coverage Continuous recording of reproducible data with accurate orientation to  ;

the reference points.  ;

Prior to the inspaction, TVA informed the inspector that.Rockwell Interna- '

tional uses a cable for calibration and calibration checks different from the cables use.d for inspection of the vessel. The extra cable used for calibration and calibration checks is demonstrated to be equivalent to the inspection cables at the beginning and end of each inspection, i

Paragraph I-4210 of the ASME B and PV Code Section XI states " Calibration shall include the complete ultrasonic examination system. Any change la .

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. . cables . . . shall be cause for calibration check." Rockwell Inter-

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national considers the " complete system" to include the extra cable, used for calibration and calibration checks. During the course of the inspection

• ,. it could not be determined whether the above position met the intent of the ASE b and PV Code.and is identified as unresolved item No. 553/79-12-02~

"Conformance of Calibration Cable to ASE Code."

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