ML20087N973

Forwards Revised Requests for Relief CN-1-001 & CN-1-002 & Original Request for Relief CN-1-003,in Response to SER Section 5.2.4,per Confirmatory Item 11 Re Preservice Insp Program

ML20087N973
Person / Time
Site:	Catawba
Issue date:	03/30/1984
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8404050282
Download: ML20087N973 (15)

Text

{{#Wiki_filter:-- 9 DUKE POWER GOMPANY P.O. BOX 33180 CHARLOTTE. N.C. 28242 . HAL B. TUCKER TELEPHONE ,,,~."//"",,, March 30, 1984 Mr.- Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: Catawba Nuclear Station Docket Nos. 50-413 and 50-414

Dear Mr. Denton:

Section 5.2.4 of the Catawba Safety Evaluation Report discusses Confirmatory Item 11, Preservice Inspection Program. As discussed in this section the Staff requested that Duke identify all plant specific areas where ASME Code .Section XI requirements could not be met, along with a supporting technical -justification. Ralief requests were previously submitted as follow: Serial No. Date of Submittal CN-1-001~ December 1, 1981 ~ CN-1-002 April 5,1982 CN-1-003 March 25, 1983 With the Preservice. Inspection Program essentially complete for Unit.1, the relief requests can now be finalized. Attached are revised Requests for Relief CN-1-001 and CN-1-002. A copy of CN-1-003 is also attached for completeness. No additional Requests for Relief on Unit 1 are expected. Very truly yours, dbf Hal B. Tucker ROS/php . Attachment- \\ 2P i

8404050282 840330'.

\\ I -PDR.ADOCK 05000413 -E PDR s

5 - - Mr. Harold R. Denton, Director March ' 30,- 1984 Page 2 cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Connission -Region II 101 Marietta Street, NW,- Suite 2900 Atlanta, Georgia 30303 NRC Resident Inspector Catawba Nuclear Station Mr. Robert Guild, Esq. Attorney-at-Law .P. 0. Box 12097 ~ Charleston, South Carolina 29412 Palmetto Alliance 21351 Devine Street-Columbia, South Carolina 29205 Mr. Jesse L. Riley Carolina. Environmental Study Group 854 Henley Place Charlotte, North Carolina 28207 i i [ b

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Serial No. CN-1-001 Page 1 of 2 d' DUKE ~ POWER COMPANY- . Request for Relief-from Inservice Inspection Requirement i ~ Station: Catawba Nuclear Stations -Unit:.#1'and.#2 Reference ' Code - ASME' Boiler and Pressure Vessel Code, Section XI 1974 Edition including Adenda through Summer 1975. I. Component for. which exemption is requested: -a. Name and Identification Number: Reactor Coolant Loop Piping ' Branch Connection Welds. See Attachment 1 for a complete list of assemblies and welds. b. ' Function: Reactor Coolant Pressure Boundary c. ASME Section III Code Class:

Class 1 d.

Valve Category: .N/A' II.. Reference code requirement that has been determined to be impractical:

Table IWB-2600 Item No B4.6 requires volumetric' examination for branch pipe' connection' welds exceeding six inches in diameter. Ultrasonic exam-ination is impractical due to configuration, and radiography cannot be performed for inservice inspection due.to accessibility.

-III. Basis for...-Requesting Relief: a. Material - SA 182-F304-N nozzle welded to SA 351 CF8A pipe. Eb. ' Estimate of extent of preservice examination which could be performed ..20%. Original' fabrication examination - Liquid penetrant on inside-and outside Ec. -surfaces and radiography of the entire weld volume plus ultrasonic testing of the entire volume of the forged nozzle,

d. -Measures which would be required to make the welds inspectable - the nozzles would have to be re-designed and replacement nozzles prepared and welded in place.

.e. Reference. drawing - CNM 1201.01-50 Sheet 1 (Attachment 2)

.r-- Serial No. CN-1-001 Page 2 of 2 p. DUKE POWER COMPANY-Request for Relief from Inservice Inspection Requirement IV.' JAlternate Exam'ination: The welds listed on Attachment I will be inspected by the liquid penetrant imethod. V. Implementation Schedule: The alternate examinations listed above will be performed for all preservice and inservice inspections. 2 A ? -^ e 1 p. f er-e g-- --w e = - err m-r e,, e ,-.e, ,e--- ww -e m ,-w-e w

s' 1. Serial No. CN-1-001 ~ ~ -The following is a list of branch connection welds for which volumetric exam-ination has been determined to be impractical: Unit 1 Manu facturer's Assembly' Serial Number

Loop 1:

Crossover. 17002 RTD Return 3"Sch. 160 6.700

Cold Leg

-15177 Pressurizer Spray 4"Sch, 160 7.200 Regenerative HX 3"Sch. 160 6.700 ' Loop 2: 1 Crossover 17004' RTD Return 3"Sch. 160 6.700 < Cold-Leg

15178 Pressurizer Spray 4"Sch. 160 7.200 Loop 3:

Crossover 17006 RTD' Return 3"Sch. 160 6.700 Regenerative HX 3"Sch. 160 6.700 . Loop'4: Crossover 17008 RTD Return 3"Sch. 160 6.700 Cold Leg 15180 Regenerative HX 3"Sch. 160 6.700 Unit 2 ~ Manu facturer's Assembly Serial Number Loop'1: Crossover-18836 RTD Return 3"Sch. 160-6.700 - Cold Leg 18837 Pressurizer Spray 4"Sch. 160 7.200 Regenerative HX 3"Sch. 160 6.700

Loop 2:

Crossover. 18840 .RTD Return _ 3"Sch. 160 6.700 Cold' Leg-18841 Pressurizer Spray 4"Sch. 160 7.200

Loop 3:

Crossover-18844 RTD Return. 3"Sch. 160 6.700 Regenerative HX 3"Sch. 160 6.700 t Loop 4: .18848 RTD Return 3"Sch. 160 6.700 Crossover Cold. Leg; 18849 Regenerative Hx 3"Sch. 160 6.700 er- .-se

-7 E Serial Noe CN-1-002 Page 1 of 2 DUKE POWER COMPANY Request for Relief from Inservice Inspection Requirement Station: Catawba Nuclear Station ' Unit: #1 and #2 Reference Code: ASME Boiler and Pressure Vessel Code Section XI 1974 Edition . including Addenda through Summer 1975. I. Component for which exemption is requested: a. .Name and Identification Number: Main Steam Piping First 61 bow wald off the top of each generator See Attachment for complete list of assemblies and v. elds. b. Function: . Main Steam Pressure Boundary c. ASME Section III Code Class: Class 2

d.. Valve Category:

N/A II. Reference code requirement that has been determined to be impractical: Table IWC-2600 Item #C2.1 requires volumetric examination for circumferential - butt welds. Table IWC-2520 examination category C-G requires that 50% of the total number of circumferential butt welds at structural discontinuities be . examined. Radiography cannot be performed for, inservice inspection due to accessibility. -III. Basis for Requesting Relief: ~a. Material - SA-106C

b. ' Estimate of extent of preservice examination which could be performed -

0%. c.: Original fabrication examination - nagnetic particle inspection is . performed on.the ~outside surface and radiography is performed on the . entire weld volume. d. Measures which would be required to make the welds able to be inspected - the_ guard pipe which makes the process pipe welds inaccessiole would have-to be removed. a e. Reference' drawings - CN-1491-SM002 CN-2491-SM013 CN-2491-SM016 CN-1491-SM003 CN-2491-SM014 -CN-1491-SM004 CN-2491-SM015

.g s1 Serial:No. CN-1-002-Page 2 of 2 + 1 , DUKE POWER COMPANY Request for Relief-from - Inservice Inspection Requirement IV. - : Alternate Examination: ~ There are no alternate examinations that can be performed due to the inaccessibility of the welds. Implementation-Schedule: V. The fabrication radiography records will be used in lieu of the on site preservice inspection examination. 3 e [ 4-4 s ~ -,r--r-ws

2F Serial No. CN-1-002 4 a

-a L h'eifo11owing fis a" list of circumferential butt welds for which volumetric -

T examination has'been determined to be impractical: Unit l' ' Weld Number Size Assembly ' .h'! Generator: CT-SM-1 A-C 32" g Main Steam B, Generator: CT-SM-1B-C 32" LMain Steam-C Generator: CT-SM-1C-C 32" -Main ~ Steam-

D1 Generator:

CT-SM-10-C 32" . Main Steam- -Unit-2= cAssembly Weld Number Size L AL:-Generator: 'CW-SM-1A-C 32" ' Main Steam B-' Generator: CW-SM-1B-C 32"

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Serial No. CN-1-003 Page 1 of 2 DUKE POWER COMPANY ' Request For Relief From lnservice inspection Requirement . Station: CATAW8A NUCLEAR STATION Unit: 1&2 Reference Code: ASME Boiler and Pressure Vessel Code Section XI 1974 Edition including addenda through Summer 1975 -1. Component for which exemption is requested: a. Name and identification Number: Pressurizer integrally welded supports Seismic Lugs to shell Support Brackets to shell

National Board Number 72a5 (Unit 1) il b.

Function: Restraint of Class -1 Vessel c. ASME Section ill Code Class: Class 1 d. Valve Category: NA 'll. - Reference Code Requirement that has been determined to be impractical: Section XI' Table IWB-2500. Examination Category B-H, requires that 100% of all support lug attachments to Class 1 Vessels shall be examined. Section XI Table IWB-2600, Item #B2.8, requires volumetric - examination for integrally welded vessel supports. Ill.' Basis for Requesting Relief: The Inservice Inspection Plan will be written to the ASME Boiler and ' Pressure Vessel Code Section "I 1980 Edition, or later edition if adopted prior.to canmercial operation. Section XI Table IWB-2500-1, - Examination Category B-H integral attachments for vessels, will require - _ surface examination of these attachment welds. Performing a surface ,'r ' examination for the preservice inspection will provide a basis for comparing future ' inservice inspection data. 1e m ,,+e ,,-e -w ,--m-r-,-r-, --.r, -w-w*m- ,~ =e-, ,,-.2,m.,, w ,-m e. =

3 Serial No. CN-1 -003 Page 2 of 2 - lil. Basis for Requesting Relief (cont.) Reference drawing # - Cf!?1-1201.01-175 Reference figure #'s - IWB-2500-13 IWB-2500-15 IV. Alternate Examination: Surface examination will be performed on all seismic lug .and support bracket welds to the Class 1 pressure boundary. 4 V. Implementation Schedule: Surfacc examination data will become the Preservice Inspection record. l l o e 9 1 g w --,,,g-r- ,,-.--w, a m,,,,,,,, ,e

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REQUIREMENTS FOR CLASS I COMPONENTS Hg. IWB-250013 / 6 s,-e u, N s /f pf n / // / l/ l p / l // / //p/h - (- - /// // .,/ / / sua..um. aree A - 8 t // p is t C i y 't h IWS Soundary .g, FIG. IW8-2500-13 INTEGRAL ATTACHMENT WELD l 79 e 9 g 9 ,,,r-- -y---- r -., - -.,

e e-9 REQUIREMENTS FOR CLASS I COMPONENTS Fig. IWB-2500-15 f. Pressure retsimng component } Ji ( \\ t ) 1 1 Jk 8 C % in. e- - g in, + Surf, exam.# % 5"* % in-Surf. exam. aree A - 8 y, k ares C - O s, g ( l s,, A D jg $,LLQt t SapphLV W W y swa soundary so,,,,, lug 9 FIG. IWB-2500-15 INTEGRAL ATTACHMENT A. 81 O w p q p-

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