ML19270F311

Responds to 780426 Questions.Forwards Requests for Relief from ASME Section Xi,Class I & Class II Requirements. Withdraws Requests for Relief MC-1-014 & MC-1-015 Dtd 780724,since There Are No Welded Class I Supports

ML19270F311
Person / Time
Site:	Mcguire, McGuire
Issue date:	02/01/1979
From:	Parker W DUKE POWER CO.
To:	Baer R, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 7902060236
Download: ML19270F311 (36)

Text

.

DUKE POWEH COM PANY Powicu liciwiso 422 Sot:Tu Cir c ucri STunce:T, CII ARI.OTTE, N. C. 2n242 www o. ma n n. s n. February 1, 1979

/t C F P#ts:OrNY 'r . C Pw C N E ' A D E 4 7C4 SffaM PRODUCT'ON 3 73 4CS 3 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. Robert L. Baer Light Water Reactors Project Branch No. 2

Subject:

McGuire Nuclear Station Docket Nos. 50-369 and 50-370 Preservice Inspection Plan

Dear Mr. Denton:

Your letter of April 26, 1978 transmitted questions 121.15 and 121.16 requesting additional information with regard to the McGuire Unit No. 1 preservice inspection plan. Our response to this request was trans-mitted by a May 31, 1978 letter to .:r. Edson G. Case. After further dir.eussions with members of the NRC staf f Duke provided more detailed request for relief from ASME Section XI requirements. These requests for relief are summarized in Attachoent 1.

Attachment 2 consists of requests for relief MC-1-025 through MC-1-031.

MC-1-025 and MC 326 cc splete the known requests for relief from ASME Claso II, requirements. Requests for relief MC-1-027 through MC-1-031 are further requests for relief frem ASME Class I and Class II require-ments which supplement our May 31, 1978 letter.

It is requested that requests for relief MC-1-014 and MC-1-015, trans-mitted by our July 24, 1978 letter, be withdrawn. It has been deter-mined that there are no welded supports on Class I systems thus making MC-1-014 and MC-015 unnecessary.

Very truly yours, pa.~ a. a; l[.

g/ William O. Parker, Jr. ~

GJP:ses Enclosure O s

x 790206023p q

McGuire Nuclear Station

. ATTACHMENT 1 Relief Request Summary Date Of Relief Submittal Serial No. Code Class Description of Component / Relief July 24, 1978 MC-1-001 N/A Request for relief from requirement of ASME Boiler & Pressure Code Section /,

1971 Edition thru Winter 1972 Addenda.

Article 6, Paragraph T-630.

MC-1-002 I Reactor vessel primary nozzle to safe-end welds.

MC-1-003 I Pressurizer Longitudinal and Circum-ferential weld seams-National Board Number 68-123.

MC-1-004 I Pressurizer integrally welded supports-National Board Number 68-123.

MC-1-005 I Steam Generator Circumferential weld seams-National Board Nos. lA: 68-107, IB: 68-108, IC: 68-109, ID: 68-110 MC-1-006 I Steam Generator Nozzle to safe-end welds-National Board Nos. same as MC-1-005.

MC-1-007 I Pressurizer safe-end to surge line-National Board No.68-213.

MC-1-008 I Piping-Longitudinal and Circumferential weld seams.

MC-1-009 I Branch piping welds exceeding 4 inches (NPS) - Visual Inspection impractical.

MC-1-010 I Branch piping welds exceeding 4 inches (NPS) - 4 inch NPS changed to 6 inch NPS.

MC-1-011 I Branch Piping Welds 4 inch (NPS) &

smaller - Visual Inspection impractical.

MC-1-012 I Branch Piping Weids 4 inch (NPS) &

smal:er - 4 inche NPS to 6 inch NPS MC-1-013 I Piping Socket Welds MC-1-014 I Piping Integrally Welded Supports MC-1-015 I Valve Integrally welded Supports MC-2-001 N/A Same as MC-1-001 September 5,1978 AC-1-016 I, II All componente requiring preservice hydrostatic test.

MC-1-017 I ASMS Class I valves > 3 inches (NPS)

September 25, 1978 MC-1-018 I Reactor Coolant Pumps lA, IB, IC, ID MC-1-019 I Reactor Coolant Pumps lA, IB, 1C, ID Lower Seal Housing Belts (12 per pump)

McGuire Nuclear Station ATTACIIMENT 1 Page 1%o Relief Request Summary Date Of Submitta? Serial No. Code Class Description of Component / Relief September 25, 197's MC-1-020 I Reactor Coolant Pumps lA, 1B, IC, ID Lower Seal llousing Ligament Area MC-1-021 I Reactor Vetsel licad, Control Rod Drive Penetratfor.s - National Board No. 20766 MC-1-022 I Reactor Vessel Incore Instrument Penetrations - National Board No. 20766 MC-1-023 I Control Rod Drive Mechanisms llousing Welds MC-1-024 I Reactor Vessel Closure IIead-National Board No. 20766

Mr. Ilarold R. Denton, Director February 1, 19'9 DUKE POWER COMPANY Requests For Relief From Insecvice Inspection Requirement McGuire Nuclear Station ATTACIIMENT 2

Serial t;o. _MC-1-025

, Page 1 of 2 DUKE POWER COMPANY Request For Relief From inservice inspection Requirement Station: McGuire Unit: 1 Reference Code: ASME Boiler and Pressure Vessel Code,Section XI, 1971 Edition through Winter 1972 Addenda

1. Conponent for which exemption is requested:

a. Name and identification Mumber:

Residual Heat Removal (ND) Heat Exchangers (2)

National Board Numbers 635, 636

b. Function:

Primary Coolant Heat Removal

c. ASME Section ll1 Code Class:

Class 11

d. Valve Category: NA

11. Reference Code Requircuant that has been determined to be ir.pra c t i ca l :

Category C-B ltem C1.2 Volumetric examination of nozzle to vessel welds (2 per heat exchanger) . Due to welded collar, the nozzle to vessel welds are inaccessible. See attachment 1.

111. Basis for Requesting Relief Material - Shell SA-240 Type 304 SS, Nozzles SA312 Type 304SS Estimate of preservice examination performed - 0%

Original fabrication examination - Radiography and dye penetrant examina* ion Measures which would be required to make the area accessible - Removal o ?

the welded collars Reference Drawing - Sketch Attached

a Serial No. MC-1-025 Page 2 of 2 DUKE POWER COMPANY Reque s t Fo r Re l i e f F rcr1 Inservice inspection Requirement 111. Basis for Requestin9 Relief (cont.)

To grind off the welded collars would not justify the high cost and loss of time to inspect the nozzle to vessel welds. The shop examinations provide adequate assurance of component reliability.

IV. Alternate Examination:

The fillet welds attaching the collar to the nozzle and shcIl will be examined with dye penetrant. The vessel has been hydrostatically tes ted wi th no evidence of leakage.

V. Impicmentatico Schedule:

Inservice inspections will include a surface examination of the collar velds and hydros tatic tes ts.

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• Serial IJo. MC-1-026

• - . Page 1 of 2 DUKE POWER C0tiPANY Request For Relief Fran Inservice Inspection Requirement Station: McGui re Unit: 1 Reference Code: ASME Boiler & Pressure Vessel Code, Se .on XI, 1971 Edition through Winter 1972 Addenda

1. Component for which exemption is requested:

a. flame and Identification Number:

Steam Generators I A, IB, I C, ID National Board Numbers68-107, 68-108,68-109, 68-110 respectively

b. Function:

Primary to Secondary coolant heat exchanger

c. ASME Section lli Code Class:

Class 11

d. Valve Category: NA

11. Reference Code Requirement that has been determined to be impractical:

Category C-A Item Cl.1 of Table ISC-261 volumetric examination of steam generator transition cone to lower shell barrel circumferential weld. Due to location of seismic res.raint, approximately 60% of the weld is obscured.

Ill. Basis for Requesting Relief Material - ASME-SA-533, Grade A Class 2 Estimate of preservice examination performed - 40%

Original fabrication examination - Radiography Measures which would be required to make the area accessible - Removal of seismic restraint.

Reference Drawing - Sketch Attached

Serial No. MC-1-026 Page 2 of 2 DUKE POWER COMPANY Request Fo r Re l i e f f rom inservice inspection Requirement 111. Basis for Requesting Relief (cont.)

The welds in question have been ultrasonically tested from one side using 0 , 45 , and 600 transducers. Due to the location of the restraint, it is impossible to perform the 0 s can on the weld centerline or the 45 and 60 scans f rom the lower side of the weld.

All other steam generator welds are accessible. It is believed that the limited scan plus the periodic hydrostatic tests provide adequate assurance of weld integrity. The high cost in time and money does not Justify relocating the seismic restraint.

IV. Alternate Examination:

None V. Implementation Schedule:

Inservice inspections will be performed by using the limited scan described above.

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I Serial No. MC-1-027 Page 1 of 2 DUKE PCWER COMPANY Request For P.clief From Inservice inspection Requirement Station: McGui re Unit: , i Reference Code: ASMS Boiler and Pressure Vessel Code,Section XI, 1971 Edition through 1972 Winter Addenda I. Component for which exemption is requested:

a. Name and Identification Number:

Steam Generators I A, IB, IC, ID National Board Numbers,68-107, 68-108,68-109, 68-110 respectively

b. Function:

Primary to Secondary coolant heat exchanger

c. ASME Section III Code Class:

Class I

d. Valve Category:

NA II. Reference Code Rcquirement that has been determined to be impractical:

Category F l tem 3.3 of Table IS-261 Volumetric examination of primary nozzle to safe end welds. Due to presence of ground out areas and the contour of the nozzle, the safe-end weld cannot be fully inspected.

III. Basis for Requesting Relief Material - ASME SA-216 Grade WCC casting, buttered with Type 309 austenitic stainless steel, welded to centrifugally cast ASME SA-351 CF8A stainless steel piping.

Estimate of Preservice Examinaton Performed - 90% volumetric, 100% surface Original Fabrication Examination - Radiography and liquid penetrant Measures which would be required to make the area accessible - Cosmetic welding then post weld heat treatment Reference Drawing - Sketch attached

1 Serial fio. MC-1-027-.. _ -

Pcge 2 of 2 DtlKE PC'.!ER COMP /d;Y Request for Re1ief Fro, inservice inspec t ion Requirer:ent lil.

Basis for Requestin9 Relief (cont.)

The ground out areas are present on all eight nozzle to safe-end welds and vary in depth from 1/32 inch to 1/8 inch. As can be seen from the attached sketch, the ground-out areas only slightly limi t the ultrasonic scan. Both the manufacturer and an cutside consultant have recommended that cosmetic welding not be performed. Because of our concern that cosmetic welding might be deleterious to the weld joints, this request for relief is submitted.

IV. Alternate Examination:

The welds have been examined ultrasonically, visually, and with dye penetrant in accordance with the Section XI Code.

V. Implementation Schedule:

Inservice inspection will be performed in accordance with the Section XI Code Edition specified by 10CFR55.55 a, paragraph (g) .

In addition, the welds will be examined using liquid penetrant every third refueling outage.

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. Serial No, MC-1-028 Page 1 of 2 DUKE POWER COMPANY Request For Relief Fron Inservice inspection Requirement S ta tion: McGuire Unit: , 1 Reference Code: ' ASME Boiler and Pressure Vessel Code,Section XI, 1971 Edition through Winter 1972 Addenda

1. Component for which exemption is requested:

a. Name and identification Number:

Containment Penetration Assemblies:

Type 1 - Main Steam (4) Type 111-3 -RHR discharge to hot legs (1)

Type 11 - Feedwa ter (4) Type 111 Upper Head injection (2)

Type 111 RHR discharge to cold legs (2)

Type lil RHR supply (1)

b. Function:

Provide air tight seal for piping through the containment boundary

c. ASitE Section lli Code Class:

Class 11

d. Valve Category:

NA II. Reference Code Requirement that has been determined to be impractical:

Ca tegories C-F, C-G - I tem C2.1 of Table I SC-261 vol ume t ri c exami na t ion of piping circumferential butt welds. Due to the design of the penetration assemblies, the penetration flued head to process pipe welds are inaccessible.

In addition ~, the Type I and Type 11 penetration flued head to guard pipe welds are inaccessible.

III. Basis for Requesting Relief Reference Drawings - See figures 1, 2, 3, 4 attached Material - See figures 1, 2, 3, 4 Estimate of Preservice Examination Performed - 0% of the inaccessible welds Original Fabricaton Examination - Radiography. Type I (Main S team) fl ued head to guard pipe welds received penetrant and ultrasonic examination Type il (feeJaater) flued head to guard pipe welds were exan.ined by radiography.

Measures whien would be requi red to make the areas accessible - complete redesign, manufacture, and installation.

Seriai !!o . MC-1-028 I'cge 2 of 2 DUKE PO*ilER COMPANY Request for Relief Frcn Inservice inspection Require. rent 111. Basis for Requesting Relief (cont.)

At the time of purchase, the penetration assemblies were state of the art in design and manufacturing technique. Redesign and replacement would result in extended delay and enormous cost. Component integrity can be assured with examination of similar welds in the process pipe coupled with hydrostatic tests and penetration leak tests.

IV. Alternate Examination:

Piping systems have been hydros tatically tested and penetrations will be leak tested.

V. Implementation Schedule:

Inservice inspection will consist of testing described in IV above.

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Serial No. MC-1-029

- Page 1 of 2 DUKE POWER COMPANY Request For Relief From inservice inspection Requirement S ta tion: McGui re Unit: ,

I Reference Code: ASME Boiler and Pressure Vessel Code,Section XI, 1971 Ed', tion through Winter 1972 Addenda

1. Component for which exemption is requested:

a. Name and identification Number:

Main Steam and feedwater systems See attached Figures 1, 2, 3,4,5,6,7,8

b. Function:

Circulate secondary coolant

c. ASME Section lli Code Class:

Class 11

d. Valve Category: NA

11. Reference Code Requirement that has been determined to be impractical:

Category CG, item C2.1 of Table IEC-261, Volumet ric Examination of piping ci rcumfe rential butt welds. Due to presence of guard pipe, approximately 16% of the feedwater and 75% of the Main Steam welds are inaccessible.

III. Basis for Requesting Relief Reference Drawings - see figures 1 through 8 Material - Listed on reference figeres Estimate of Preservice Examination Performed - 0% on inaccessible portions 100% on accessible portions Original fabrication examinaton - 100% Radiography heasures which would be required to make the areas accessible - Removal of the guard pipe

Serial flo MC-1-029

. Pcge 2 of 2 4

DUKE POWER C0!iPANY Request for Relief From Inservice inspection Requirement Ill.

Basis for Requesting Relief (cont.)

The guard pipe was designed and installed for pipe rupture and jet impingement protection required by NRC directives. Section XI requi rements to inspect Class 11 piping systems had not been developed at the tine of system design.

Component integrity can be assured by examining the accessible welds (Section XI only requires examining 50% of the welds at s tructural discontinui ties, and this number is further reduced by applying the multiple s t ream concept) and hydros ta ti c tests. The purpose of the guard pipe and support systems is to maintain plant safety in the unlikely event of system f a i l u re. We believe the extreme neasures required to make the areas accessible without compensating increase in the level of quali ty assurance do not justify the hl h cost and. loss of time.

IV. A'IternSteExamination:

No alternate examination is possible.

V. Implementation Schedule:

Preservice examination has been completed on the accessible welds.

Inservice examinations will be p;rformed on the accessible welds as required by the Section XI speci fied by 10CFR50.55a paragraph (g) .

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32" NPs M>W. 1.375" 34' NPS, ".W. 1.250", 1.75", 2.03" MAIN STEAM ASME SA-!C5 GRC See l e s e.

Fitting;. .

ASME C/~234 GR VPC Se.nlet, -

Fa y r e 9

T Serial No. MC-1-030

.. Page 1 of 2 DUr.E POWER COMPANY Request For Relief Froa Inservice inspection Requirement ,

S ta t ion: McGuire Unit: ,

I Reference Code: 'ASME Boiler & P ressure Vessel Code,Section XI, 1971 Edition through Winter 1972 Addenda

1. Component for which exemption is requested:

a. Unme and identification Number-Main Steam System welded restraint attachments Rl A through R8A RIC through R8C Rla through R8B RlD through R8D

b. Function:

Wear pads welded to main steam piping encased by guard pipe

c. ASitE Section 111 Code Class:

Class 11

d. Valve Category:

NA II. Reference Code Requirement that has been determined to be impractical:

Ca tego ry C-C , I tem C2.4 of Table ISC-261 surface examination of integrally welded support-to pipe welds. Due to the presence of guard pipe the welded wear pads of la above are inaccessible.

Ill. Basis for Requesting Relief Material - SA-515 Grade 70 plate or SA-155 KC70 pipe wear pads fillet welded to SA-106 Gr C main steam piping Estimate of Preservice Examinaton Performed - 0%

Original Fabrication Examination - Magnetic particle surface examination Measures which would be required to make the areas accessible - remova l of the guard pipe Reference Drawing - Sketch attached.

F Serial i;o MC-1-030

, l'q;e 2 of 2 DUKE PO',f:R COlPMlY ,

hequest for r, e 1 i c f F rce, inservice i nspec t ion Requ i re:.:en t Ill. liasis for heques t ing nelie f (cont.)

The main steam guard pipe was designed and purchased before there was a Section XI req u i remen t to inspect Class 11 components. These wear pads are only subject to compress ive stresses . The welds have been verified defect f ree by original fabrication examination.

Component integrity can be assured by inspecting similar system welds

-nd hydrostatic tests.

IV. Alternate Examination:

No alterndte examination is possible.

V. Implementation Schedule:

The system is installed and field hydrostatically tested.

I nse rvi ce inspections will not be poss:ble because of inaccessibility.

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• Serial No. MC-1-031

• ' ' Page 1 of 2 e

DUF.E PL./ER COMPANY Request for Relief Frca

' Inservice inspection Recui rcment .

S ta t ion: McGuire Unit: ,

I Reference Code: ASME Boiler & Pressure Vessel Code,Section XI, 1971 Edition through Winter 1972 Addenda

1. Component for which exemption is requested:

a. llame and Identification Number:

Feedwate r sys tem welded attachments , CF-H1 and CF-H2.

See attached sketch,

b. Function:

Wear pade welded to feedwater piping encased by guard pipe

c. ASME Section 111 Code Class:

Class 11

d. Valve Category:

NA II. Reference Code Requirement that has been determined to be impractical:

Ca tego ry C-C , item C2.4 of Table ISC-261 surface examination of integrally welded support-to pipe welds. Due to the presence of guard pipe the wear pads are partially inaccessible.

Ill. Basis for Requesting Relief Material - CF-H1 and CF-H2 each cbnsists of 4 segments of ASME SA-106 Gr. B pipe 3/8 in x 8 ir. x 6 in fillet welded to ASME SA-106 Gr. B pipe.

Estimate of Preservice Examination Area Accessible - 35%

Original Fabrication Examination Performed - Magnetic particle surface examination Measures which would be required to make the area accessible - Removal of the guard pipe Reference Drawing - Sketch attached.

Serial I;o. MC-1-031

. .. , Page 2 of 2 DUKE PO'..T R C0".PA"Y -

Request Fo r P,e l i e f F rca inservice i n s;,;-c t i e n Re qu i r ca:e n t Ill. i;as i s for i cques t ing Relief (cont.)

The feedwater guard pipe was designed and purchased before there was a Section XI req ui remen t to inspect Class 11 components. The welds have been veri fied defect f ree by original fabrication examination. Component integrity can be assured by inspecting the 35% of the accessible area, inspe,ction of similar system welds, and hydrostatic tests.

IV. Alternate Examination:

No alternative examination is possible.

V. Implementation Sciedule:

The system is installed and field hydrostatically tested. The accessible areas will be examined in January 1979 Inservice '

examination of the accessible areas will be in accordance with the Section XI code required by 10CFR50.55a, paragraph 9 4

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