ML20206S498

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Forwards Response to NRC 860507 Request for Addl Info Re 841107 Inservice Insp (ISI) Plan.Info Includes Flow Diagrams & Preservice Insp/Isi addendums.W/52 Oversize Drawings
ML20206S498
Person / Time
Site: Mcguire, McGuire  Duke Energy icon.png
Issue date: 06/20/1986
From: Tucker H
DUKE POWER CO.
To: Harold Denton, Youngblood B
Office of Nuclear Reactor Regulation
Shared Package
ML20206S501 List: ... further results
References
NUDOCS 8607070368
Download: ML20206S498 (6)
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DUKE POWER GOMPANY P.O. DOx 03180 CHARLOTTE, N.O. 28242 HALH. TUCKER TELEPHONE vice ramminawr (704) 37J-4531 Nt;CLRAE PRODt CTION June 20, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: B.J. Youngblood, Director PWR Project Directorate #4

Subject:

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

Dear Mr. Denton:

By my letter dated November 7,1984, Duke submitted for information purposes a copy of the Inservice Inspection Plan for McGuire Nuclear Station Units 1 and 2 which addresses the requirements of 10CFR 50.55a(g). (The application fee for the NRC review of the McGuire ISI Plan was provided by my February 15, 1985 letter to Ms. R.M. Diggs (NRC/0A)) . Mr. D.S. Hood's May 7, 1986 letter indicated that NRC ctaff review (with technical assistance of an NRC contractor, Science Applica-tions, Inc.) of this program for the first ten-year inspection interval at McGuire finds that additional information is needed for completion of the review, and eccordingly requested the additional information.

Please find attached responses to the items contained in the above referenced request for additional information (flow diagrams indicated in this response are clso enclosed, as well as PSI /ISI Plan addendums reflecting various portions of this response). Note that some of the requests are impractical and the infor-mation is not provided at this time. An NRC site visit may be desirable to obtain cny further information. Also, NRC/ Region II has reviewed this plan in some detail during routine site inspections at McGuire (as documented in NRC/OIE inspection reports, etc.) - advantage could be taken of these prior reviews, and come effort should be made to coordinate future reviews by Region II and ONRR so (

cs to not duplicate effort and conserve NRC and Duke Power Company resources. In cddition, the NRC review is based on Revision 6 of the plan, while Revision 8 is currently in effect and Revision 9 is planned for the near future - Duke could provide a later revision if it would aid in resolving these issues.

Should there be any questions concerning this submittal or if additional infor-8607070368 860620 h 7 11 PDR ADOCK 05000369 i: /p G PDR D f pt QvtO DDII DP/VJINCr 5 % &::-

Mr. Harold R. Denton, Director

~ June 20, 1986 Page 2 nation / site visit is desired, please advise.

Very truly yours, Wt Hal B. Tucker

PBN/16/j gm l Attachments Enclosures xc
(with attachments only)

Dr. J. Nelson Grace '

Regional Administrator U.S. NRC 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Darl Hood, Project Manager Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555  ;

l Mr. W.T. Orders Senior Resident Inspector McGuire Nuclear Station i

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ATTACHMENT DUKE' POWER COMPANY McGUIRE NUCLEAR STATION INSERVICE INSPECTION PROGRAM MAY 7, 1986 NRC REQUEST FOR ADDITIONAL INFORMATION RESPONSE

1. (a) Color coded flow diagrams identifying Class 1 & 2 non-exempt inspection boundaries are enclosed. Any other information may be obtained at the site.

(b) This request would require obtaining and marking up approximately 5000 drawings. No diagrams or drawings are being sent, copies of the appropriate drawings are uvailable for review at the site.

(c) Sections 4.1, 5.1 and 6.1 of Volume 1 of the ISI Plan are being revised.

(d) The inspections for McGuire were based on the following outage schedule:

Unit 1, Dec.1, 81 thru Dec.1, 84 1st Period Out. 1 Dec. 2, 84 thru Dec. 1, 88 2nd Period Out. 2,3,4,5 Dec. 2, 88 thru Dec. 1, 91 3rd Period Out. 6,7,8 Unit 2, Mar. 1, 84 thru Mar. 1, 87 1st Period Out. 1,2,3 Mar. 2, 87 thru Mar. 1, 91 2nd Period Out. 4, 5, 6 Mar. 2, 91 thru Mar. 1, 94 3rd Period Out. 7,8,9

1) Component description already in plan listing
2) Section XI Item Number already in plan listing
3) Examination method already in plan listing l
4) First. interval sample size is covered by projected

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outage schedules and periods

5) Number or length of welds or component supports to be examined in each of the inspection periods covered by projected outages
6) Class 1 & 2 piping: the plan listing covers total welds, Item & IWB and IWC Tables. Welds selected on the basis of stress calculations and terminal ends are identified in the plan.

(e) IWC-2500-1 Category C-Il Note-7. We do not use this exemption.

(f) Class 3 systems are scheduled under categories D1.10, D2.10 and D3.10 as shown in Table IWD-2500-1. Integral attachments are scheduled in the F1.03 Category.

Comments will be added to those items including integral attachments.

2. The ISI Plan for Unit 1 was submitted to the NRC for approval on 11/7/84 per 10CFR50.55a (g) (4) (iv) .
3. (a) Steam Generator nozzle-to-safe and butt welds are I scheduled for surface examination under B5.30

! Category per Table IWB-2500-1.

1 (b) There are no integrally welded attachments with thick-ness 5/8 inches and greater on Class 1 piping, pumps or valves at McGuire. Reactor coolant pumps have integrally cast supports, which are being inspected at i Duke's option and are under no regulatory requirements j or commitments.

(c) Class 1 pump casing internal surfaces Item Number B12.20: Duke Power's Reactor Coolant Pumps are not welded, therefore no inspection is required by Table IWB-2500-1 Category B-L-2, Note 1.

(d) Branch connections are volumetrically examined from one side due to configuration (Fig. IWB-2500-11). The exam gives full coverage of the area of interest.

j l (e) The Unit 1 core support is scheduled to be examined when structure is removed by the end of the 10-year outage. (Item No. B13.030.001, Unit 1 Outage 6). The.

' Unit 2 inspection will be added.

(f) RHR system Weld Number 1ND69A-3 is listed to be

  • examined during outage number 4 per Table IWC-2500-1.

I (g) Snubber test are scheduled by station under McGuire Technical Specifications and are not included under the l

scope of this ISI Plan.

4. (a&b) B-A Category consists of 27 welds, however 19 welds have a deferral permissible to end of interval. These welds will be completed during outage 7 during the Reactor Vessel examination.

1' (c) BB Category consists of 8 welds, 4 welds have been completed.

!- (d) B-G-2 Category consists of 80 connection, 40 connection  !

have been completed.

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J (e) Item B7.20 is included in the B-G-2 Category. All pumps

! are listed for Outage 3 but only pumps that were disassembled were to be inspected.

, (f) Unit 1 Reactor Vessel interior examination Category (B-N-1) Item B13.10 will be inspected during Outages 4

& 7. This inspection was also done in Outage 1.

2 (g) Class 1 System Leakage Test Category (B-P): A Class 1

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hydrostatic test will be done at the end of Outage 7 per Table IWB-2500-1.

5. Flywheel and pipe rupture examination are listed in outage j schedule. The Steam Generator modification was covered by i letters dated Feb. 3, 1983; April 28, 1983; and May 5, 1983 l

from H.B. Tucker to H.R. Denton. The Safety Injection System Modifications were covered by letters dated September 14, 1982 l and October 19, 1982 from H.B. Tucker to H.R. Denton, and NRC response letter dated December 29, 1982 from Thomas M. Novak to H.B. Tucker. Area of inspection was limited due to Geometry 1

of valve to the tee welds. These were done in accordance with l ASME Code. Thermal Sleeve removal was covered by letters dated

, July 13, 1982 from William O. Parker, Jr. to H.R. Denton, NRC response letter dated July 19, 1982 Docket No. 50-369 l from Darrell G. Eisenhut to William O. Parker, Jr., and i Westinghouse letter (Duke 5937) to Duke dated September 1

! 1982.

y 6. Duke has received no response from the NRC granting approval i of the changes requested in H.B. Tucker's letter of November i 5, 1984. The items in the ISI Plan are listed based on the original commitment of February 9, 1979 which is considered i

! to still be in effect pending receipt of approval of the l 4

November 5, 1984 request.

7. All Class 2 systems are included as required by 10CFR50.55a.

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26085 (1-82) Ferm QA-513A gd8 Procedure QA-513 Revision i ut DUKE POWER COMPANY QUALITY ASSURANCE DEPARTMENT OPERATIONS OlVISION Serial No. 2McG -cottl PSI /tSi PLAN ADDENDUM Station p)(Gmat Unit 2.

PSI Plan 151 Plan Current Plan Revision A Section h. Deandts .n _' VetR Page d/A

' .ciar. vj 7 Detailed Description of Proposed Change: Th hm9a2 E13. oio . co l Rd Mos.,ts 4 and 1 .

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