ML19345E209

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Discusses Status of Preservice Insp of Facility & Forwards Two Addl Requests for Relief from ASME Code Requirements Re Safety & Relief Nozzles & Containment Spray Heat Exchangers
ML19345E209
Person / Time
Site: McGuire 
Issue date: 12/15/1980
From: Parker W
DUKE POWER CO.
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
References
MC-1-007, MC-1-034, MC-1-34, MC-1-7, NUDOCS 8012230458
Download: ML19345E209 (7)


Text

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DUKE POWElf COMMNY Powen Deumixo 402 Sourn Cucacu Srnr.ET, CuAHLoTTE, N. C. 282 42 i

WI LU AM O. PAR M ER. J R, V*cr Potsicewt frtrawont: Anga 704 Strane Paouwchow 373-4063 December 15, 1980 i

Mr. liarold R. Denton, Director Office of Nucicar Reactor Regulation U. S. Nuclear Regulatory Commission l

Washington, D. C.

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2l Attention: Mr. B. J. Youngblood

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.a Subj ect: McGuire Unit 1 Docket No. 50-369

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Dear Mr. Denton:

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'The preservice inspection of Unit 1, McGuire Nuclear Station is

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approximately 99% complete. The following items have not been l

completed:

1.

Supports and restraints for Class 1, 2 and 3 piping systems.

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The design of supports and restraints on several systems is being reviewed and changes may be required.

i 2.

Several Class 2 valves are being replaced to correct problems found during hot functional testing of the unit. The new welds will be inspected when the modifications are complete.

4 3.

The' design specification on a section of the Ice Condenser j

Refrigeration System was recently changed from non-code piping to Class 2 piping.- The system is being reviewed by Babcock &

Wilcox to determine the inspection required.

Volumetric examinations performed to date have revealed no Code rejectable indications.

Several Code rejectable indications.have.

been found by surface examination methods. All of these have i

been repaired, re-inspected, and found acceptable.

Duke Power has submitted requests for relief'in those cases where we were unable to meet all of the-ASME Code requirements in performing the preservice inspection at McGuire Unit 1.. These k

requests for relief have been granted by the'NRC. Two additional l I requests for relief.are attached. The first of these requests

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Mr. Harold R. Denton Page 2 December 15, 1980 (MC-1-007) is an addendum to an earlier request which omitted four welds on which visual inspection is impractical. The second request (MC-1-034) had incorrectly been ir.cluded in an earlier request (MC-1-025).

It has been determined that requests MC-1-032 and MC-1-033 are not required. The conditions covered by these two requests have aircady been addressed in the McGuire FSAR.

truly yours 0 Ve u.+ _ = dl. u L w

,WilliamO. Parker,Jr.

THH:vr Attachments cc:

Mr. J. P. O'Reilly

_._._______m Serial No.

MC-1-007 Addendum r

i Page 1 of 2 DUKE POWER COMPANY i

Request For Relief From Inservice Inspection Requirement j

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Station: McGuire l

Unit:

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Reference Code: ASME Boiler and Pressure Vessel Code,Section XI, 1971 l

Edition throagh Winter 1972 Addenda I

1.

Component for which exemption is requested:

a.

Name and Identification Number 6

j Pressurizer National Board Number: 68-213 Safety Nozzles to safe-end welds (3)

Relief Nozzle to safe-end weld (1) l b.

Function:

l Primary coolant pressure control.

c.

ASME Section III Code Class:

Class 1 i

d.

Valve Category:

I NA II.

Reference Code Requirement that has been determined to be impractical:

Table IS-261 Item 4.1 Visual Examination III. Basis for Requesting Relief Table IS-261' Item 4.1 requires volumetric, surface, and visual.examina -

tions of the pressurizer safe-end welds (MC-1-007 requests for surge I

line safe-end).

The surface and volumetric examinations have been performed.. The visual examination is considered impractical because no visual acceptance standards exist. Later editions of Section XI do not require a visual examination.

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Serial No. MC-1-007 Addendum Page 2 of 2 DUKE POWER COMPANY Request For Relief From Inservice Inspection Requirement III. Basis for Requesting Relief (cont.)

IV.

Alternate Examination:

No alternate examiaation is proposed.

V.

Implementation Schedule:

Volumetric and surface examination data will become the Preservice Inspection record.

Inservice inspections will be performed in accordance with the Section XI edition required by 10CFR 50.55(e),

paragraph g.

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Scrial No. MC-1-036 Page 1 of 2 l

1 DUKE POWER COMPANY r

t Request For Relief From i

Inservice Inspection Requirement i

Station: McGuire Nuclear Station Unit:

No. 1 Reference Code: ASME Boiler and Pressure Vessel Code,Section XI, 1971 Edition Including Addenda Through Winter 1972 i

I.

Component for which exemption is requested:

a.

Name and Identification Number:

l Containment Spray (NS) Heat Exchangers (2) b.

Function:

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Containment Heat Removal c.

ASME Section III Code Class:

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Class II d.

Valve Category:

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II.

Reference Code Requirement that has been determined to be impractical:

1 Category C-B Item C1.2 Volumetric Examination of nozzle to vessel welds (2 per heat exchanger). Due to welded reinforcing collar, the nozzle j

to vessel weld is inaccessible.

See Attachment 1.

III. Basis for Requesting Relief Material:

Shell-SA516 Grade 70 Inlet Nozzle - SA 106 Grade B l

Outlet Nozzle - SA 312 Type 304 Reinforcing Collars - SA 516 Grade 70 Estimate of Preservice Examination Performed - 0%

Original Fabrication Examination - Radiography and Liquid Penetrant Examination.

Measures which would be required to make the areas accessible - Removal 1

of the welded collars.

Reference Drawing - Attachment 1 4

9

Serial No. MC-1-034 Pego 2 of 2 DUKE POWER COMPANY Request For Relief From Inservice Inspection Requirement III.

Basis for Requesting Relief (cont.)

Volumetric inspection of the nozzle to shell weld would not provide enough added assurance of reliability to justify the time and expense of removing and re-installing the reinforcing collars. The shop ex-aminations provide adequate assurance of component reliability.

IV.

Alternate Examination:

The welds attaching the collar to the nozzle and shell vill be examined by the magnetic particle method. The vessels have been hydrostatically tested with no evidence of leakage.

V.

Implementation Schedule:

Inservice inspections will include a surface examination of the collar welds and hydrostatic tests of the vessels.

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