IR 05000275/1982022

IE Insp Repts 50-275/82-22 & 50-323/82-11 on 820526-28 & 0628-0702.No Noncompliance Noted.Major Areas Inspected: Action on Previous Items,Mods to Piping & Electrical Raceway Supports & Unit 2 Vessel

ML20062H674
Person / Time
Site:	Diablo Canyon
Issue date:	07/26/1982
From:	Burdoin J, Eckhardt J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:
Shared Package
ML20062H672	List: IR 05000275/1982022 ML20062H668
References
TASK-2.F.2, TASK-TM 50-275-82-22, 50-323-82-11, IEB-79-02, IEB-79-2, NUDOCS 8208160129
Download: ML20062H674 (8)

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U. S. NUCLEAR REGULATORY COMMISSION

REGION V

50-275/82-22 Report No. 50-323/82-11 Docket No. 50-275, 50-323 License No. DPR-76, CPPR-69 Safeguards Group Licensee: Pacific Gas and Electric Company P. O. Box 7442

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San Francisco, California 94120 Facility Name: Diablo Canyon Units 1 and 2 Inspection at: Diablo Canyon Site, San Luis Obispo County, California & Corporate Office Inspection conducted: May 26-28, and June 28 - July 2, 1982 Inspectors: / d 7- EJ-fL J'. F. Burdoin, Reactor Inspector Date Signed V

Approved by:[d/.d et/b 7 - 2.6- 92_

M J. y Eckhardt'f Acting Chief Date Signed

/ Reactor Projec'ts Section 1 Summary:

Inspection during period of May 26-28 and June 28 thru July 2,1982 (Report Nos. 50-275/82-22 and 50-323/82-11).

Areas Inspected: Announced inspections by regional based inspector of construction and modification activities including: a site tour, licensee actions on previous identified items, modifications to piping and electrical raceway supports resulting from the revised annulus spectra, and preservice examination of unit 2

vesse The inspection involved 50 inspection hours by one inspecto Results

No items of noncompliance or deviations were identifie PDR ADOCK 05000275 G PDR

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. DETAILS Individuals Contacted Pacific Gas and Electric Company (PG&E)

+*R.-D. Etzler, Project' Superintendent

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M. N. Norem, Resident Startup Engineer

+* A. Rockwell, Resident Electrical Engineer

+ J. A. Ammon, Resident. Mechanical Engineer

+ F. M. Russell, Resident Civil Engineer K. A.,Nilson, Mechanical Field Engineer

+*J. R..Bratton, Lead QC Inspector J. J..Nystrom, QC Inspector T. E. Pierce, QC Inspector'

C. H. Issel, . Electrical Inspector M. J.'Mello, Mechanical Inspector

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R. T. Twiddy, QA Supervisor

• C M.'Seward, QA Engineer

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+ R. W. Taylor, QA Engineer

• T. D. Smith, ISI, Lead QC Engineer S. J. Friedrich, DER, Project Engineer -

D. F. Powell, DER, NDE Engineer i

j Various other engineering and QC personne H. P. Foley Company (Foley)

A. E. Moses, Project Manager V. H. Tennyson, QC Manager J. L. Thompson, QA Engineering Group Supervisor Pullman Power Products Corporation H. W. Karner, QA/QC Manager J. C. Schultz, Drafting Supervisor R. J. Balka, Design Engineer Bechtel Corporation

+ A. G. Weedman

• W. L. McCullough t

+ R. E. McMechan

+ R. C. Montgomery

• A. L. Sandel

• Denotes attendees at exit meeting on May 28, 1982. ;

+ Denotes attendees at exit meeting on July 2,198 i

} NRC resident inspector Mr. M. M. Mendonca attended the May 28, 1982 exit ;

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-2- Site Tour A tour was made of the new (relocated in June) Class IE cable storage yard and selected areas of unit 2. In the pipe rack area (elev. 115)

adjacent to unit 2 containment 500 beam FW16 area magna-fluxing of a weld on gusset bracing of a rupture restraint was in proces In the containment, conduit for containment. evacuation alarm and emergency lighting was being installed in the annulus area. The work in process on the items described was inspecte No deviations or items of noncompliance were identifie . flodification of Battery Racks and Replacement of Vital Batteries for Units 1 and Licensee Event Report 81-005/0IT-0 reported that a Unit 1 vital battery cell case was found seeping electrolyte. Further. investigation of Units 1 and 2 vital batteries revealed 17 cells (3 in Unit 1 and 14 in Unit 2) with cracks emanating near molded support ribs on the bottom of the case. The corrective measures include modifying the battery racks in accordance with the manufactures recommendation This entails relocating the existing support rails and the addition of two new support rails. All battery cells will be replaced with cells, of a new case bracing desig The modifications to the battery racks and. installation of the new batteries was inspected in the field. Job orders E-1085'and E-1108

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which identified the work and specifications (8802) which prescribe the procedures for accomplishing the task.were examined. No deviations or items of noncompliance were identifie The status of the task is: Batteries 11, 13 and 23 are completed, and-batteries 12, 21 and 22 are in various stages of completion. This -

item remains open, and the status will be reported in a subsequent-inspection report (50-275/82-22/01). Safety-Related Pipe Support and Restraint Systems, Unit 1 The seismic verification of pipe supports to date has resulted in 171 large bore piping hangers requiring modifications. As of this inspection, modifications to 122 hangers have been complete Approximately 76 small bore (2" diameter and smaller) piping hangers reouire modifications. Forty-nine of these modifications are to provide two-way vertical restraint of the pipe. To date, modifications to 73 small bore hangers have been complete .

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The inspector examined modifications to large and small bore pipe supports in Unit 1 containment and auxiliary building to ascertain by visual examination whether the pipe supports met the requirements specified by licensee's drawings, procedures, and specification The following pipe supports which had been inspected and accepted by the contractor's Quality Control were examined, and appeared to satisfy the applicable requirements of ESD-223, " Installation and Inspection of Class 1 Pipe Supports."

Large Bore Pipe Supports Small Bore Pipe Support 22-3385L 47-15 66-27 2151-200 No items of noncompliance or deviations were identifie . Modifications to Electrical Raceway Supports (0 pen) Suooort Detail, S-102B

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Sixteen electrical raceway supports, detail S-102B (listed below)

located in Auxiliary and Turbine Buildings were inspected in the field to determine conformance with applicable design requirements of work request 1113 (DCI-EE-1278). The QC records for five of !

the supports were reviewed for completeness and found acceptabl The review of QC records for the remaining eleven supports will be completed during the next inspection. This item remains open (50-275/82-22/02).

H-100-6-6 K-85-2-85

• H-ll5-1-35 GE/GW-ll5-2-205

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K-85-1-40 CSR-127-4-287 l K-85-1-40A *K-154-1-366

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H-85-4-44 *K-154-1-400 A-119-5-73 K-154-1-402 H-115-4-79 *K-154-1-425

• A-119-3-80 CSR-127-7-429

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• QC record review complete ,

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-4- (Closed) Supports, Details-as Identified Twenty-two electrical raceway supports (details identified below)

located in the annulus area of the containment were inspected in the field to determine conformance with applicable design requirements of Work Request 1111 (DCI-EE-1279); the QC records for these support details were examined in Foley's OC offic The supports identified below were found acceptabl Detail S-4B Detail S-318 F-140-1-59 G-140-8-(24).

F-140-1-66 Detail S-319 F-140-1-67 G-140-8-(21).

F-140-2-112 Detail S-325 F-140-2-116 G-140-8-(25).

G-140-7-(37) G-140-8-(26)

G-140-7-243 G-140-8-(27)

G-140-7-243A G-140-8-(28).

G-140-8-1019 G-140-8-(29)

G-140-8-1023B Detail S-493 G-140-8-1033 G-140-7-273 G-140-8-1033A Detail S-226 G-140-8-(22)

G-140-8-1047 This item is close . Preservice Inspection (Baseline), Unit 2 Preservice Inspection Program The licensee's preservice inspection program as described in the following ultrasonic examination procedures, for Unit 2 reactor vessel was reviewed.

f Procedure 2501 Ultrasonic Instrument Linearity Test Procedure 2503 UT Couplant Materials Procedure 2504 Ultrasonic Beam SpreadfDetermination a

Procedure 2505 UT System Calibration for Data Recording

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Procedure 3525 Ultrasonic Examination of Reactor Vessel Welds

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and Adjacent Base Metal Procedure 3526 RVIT Document Control Procedure 3528 Operating Instructions for Examination of the Reactor Vessel Nozzle Bore and Inner Radii with RVIT' j The licensee's Department of Engineering Research performed the nondestructive examination of Unit 2 reactor vessel with the Reactor Vessel Inspection Tool (RVIT), a pulse-echo type ultrasonic flaw detection instrument modified for use with the UTS-5 Syste b. Observation of Work Activity The work performed during the period of the inspection was an ultrasonic examination of the shell surface portion of the nozzle to vessel weld of three reactor vessel nozzles. Features examined were; frequency and linearity of equipment used, extent of coverage, i calibration (s), sizes and frequency of search units,-beam angles (s),

distance compensation methods,. discontinuities reference. .

demonstration of penetration, limits of evaluation, recording method (s), and acceptance limit '

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c. NDE Personnel Qualifications *-

The qualification records for three of the NDE; personnel

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involved in the NDE ' activities observed during Lthis 'inspectiont were reviewed. This included one Level I, one Level II, and 4

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one Level III, NDE personnel from the licensee's~ Department *

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of Engineering Research. The persons concerned were qualified to perform ultrasonic testing within their certification levels.

l Plant operating personnel have raised a question concerning whether

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all areas of the reactor vessel and nozzle safe-end welds can be

adequately examined with the RVIT machine, to successfully complete .

the preservice inspection.

The procedures portion of the licensee's preservice inspection-

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program is considered satisfactory. However. because of the above concern of adequate examination of all vessel areas; this item

remains open'and will be reported in a subsequent Inspection

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Report (50-323/82-11/01).

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-6- Licensee Actions on Previous Identified Items (Closed) Noncompliance (50-275/82-13/02) Pre-Hydrostatic Test Walkdowns ,

This item of noncompliance involved an allegation concerning pre-hydrostatic test walkdowns of piping systems performed by Pullman Power Products, the mechanical contracto An audit conducted by Pullman Power products on February 27, 1981 identified a condition where a required pre-hydrostatic test walkdwon had not been performed, and the Piping Release form was signed in the'

required spaces by the Quality Engineer Leadman instead of the QC. Field -

inspector. The specified corrective action only addressed future pre-hydrostatic test walkdowns and did not address past tests.. The_

specific corrective action taken by Pullman at the time was to instruct both the QE Leadman and the QC Inspectors that all such tests must be documented by the QC inspector, the person responsible for performing

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the walkdow The particular walkdown in question was for a piece of pipe approximately six feet long, undergoing a bench test. A section of pipe of that length is normally in full view during a bench test, and any defects

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would have been readily detectable. Also, subsequent test walkdowns of the entire system which this six foot section became a part of did not reveal any defects in the six foot section of pipe in question.

i Subsequent to the NRC inspection, Pullman took additional actions to address the past sign-off practice regarding pre-hydrostatic test These actions consisted of Pullman confirming with both the QE Leadman and the QC Inspectors involved, that the documentation on previous tests were based on proper and satisfactory completion of the walkdowns by the responsible QC Inspector. Additionally, Pullman determined that the previous test walkdowns demonstrated the acceptability of the areas included in these walkdowns. However, the licensee notes that it is not always possible to detect indications 1/64-inch in size or smaller during a routine pre-hydrostatic walkdown. In addition the licensee i

believes that, due to the type and nature of the indications noted above, the length of time since the completion of the test walkdowns, and the amount of construction constantly'being performed in the areas where the indications found; that these indications could have been caused by events subsequent to the walkdowns. Nevertheless, both PG&E and Pullman have evaluated the indications found by the NRC inspector

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and have taken appropriate steps to have them remove It is considered that the actions described above will assure full compliance with quality assurance requirements and should preclude

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similar violations in the futur This item is close r

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-7- Licensee Resoonse to IE Bulletin (Closed for Unit 1) Bulletin 79-02: Pipe Support Base Plate Design using Concrete Expansion Anchor Bolts Inspection Report 50-275/80-18 dated October 9, 1980, identified the last requirement of the licensee was to . forward to NRC the final report upon completion of the actions required by this bulletin. The final report for Bulletin 79-02 for Unit 1 was forwarded December 3, .

1980. Additional information in response to specific NRC questions (February 5,1982) was contained in the licensee's submittals of March 12 and June 11, 198 The final report along with the responses to specific NRC questions was reviewed. It is concluded that sufficient information has been provided to satisfy the requirements of the Bulletin 79-0 ..

This bulletin is close . TMI Task Action Plan Items for Unit 2 Work in progress in containment on TMI . Task Action Plan l Item II.F.2, instrumentation for detection of inadequate core cooling was' observed during the site tour. Stainless steel tubing supports were being installed for seal table tubing portions of.the reactor vessel level instrument system. On.the reactor vessel head; beta radiation shielding of thermocouples connectors was being installed. .These items;,

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are in the early stages.of construction so will be followed ~and the status reported in future inspection reports (50-323/82-11/02).

1 Management Interview Meetings were held with the licensee representatives (identified in Section 1) on May 28 and July 2, 1982. The scope of the inspections and summaries of the findings, as noted in this report, were discussed.