ML20210Q679
| ML20210Q679 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 05/07/1986 |
| From: | Hood D Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8605140214 | |
| Download: ML20210Q679 (9) | |
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-4.A MAY 0 7 1985 Docket Nos.: 50-369 and 50-370 Mr. H. B. Tucker, Vice President Nuclear Production Department Duke Power Company 422 South Church Street Charlette. North Carolina 28242
Dear Mr. Tucker:
Subiect: Request for Additional Information on Inservice Inspection Program - McGuire Nuclear Station, Units 1 and 2 The NRC staff is reviewing you letters of November 5 and 7,1984 submitting the inservice ir.spection (ISI) program for the first ten-year inspection interval at McGuire Nuclear Station, Units 1 and 2.
This review is being perfonned with the technical assistance of an NRC contractor, Science Applications, Inc. We find that additional information identified in the enclosure is needed for completion of this reviev.
Your response to the enclosure is requested within 45 days of this letter.
Contact me if you have questions regarding the enclosure.
Sir.ce rely,
Darl d'-Project Manager PWR Project Direct 0 rates #4 Division of PWR Licensing-A
Enclosure:
As stated
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cc: See next page DISTRIBUTION:
Docket File NRC PDR-Local PDR-PRC Systera NSIC PWR#4 Rdg.
BJYoungblood Rdg MDuncan DHood OELD ACRS,(10) 860514o214 e60507 i
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'gDR ADOCK 05000369 BGrimes PDR EJardan GJohnson, PAEB Qp 33li In p3/i{n PWR#4/DPWR-A PWR#4/DPWR-A PWR#4/DPWR-A DHood/mac MDuncan BJYoungblood CS/ f /86 05/6 /86 05/4 /86
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F Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station cc:
Mr. A. Carr Dr. John M. Barry Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 Mr. F. J. Twogood County Manager of Mecklenburg County Power Systems Division 720 East Fourth Street Westinghouse Electric Corp.
Charlotte, North Carolina 28202 P. O. Box 355 Pittsburgh, Pennsylvania 15230 Chairman, North Carolina Utilities Commission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Pr_oduction Department Raleigh, North Carolina 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief Radiation Protection Branch J. Michael McGarry, III, Esq.
Division of Facility Services Bishop, Liberman, Cook, Purcell Department of Human Resources and Reynolds P.O. Box 12200 1200 Seventeenth Street, N.W.
Raleigh, North Carolina 27605 Washington, D. C.
20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Commission Route 4, Box 529 Hunterville, North Carolina 28078 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W., Suite 2900 Atlante, Georgia 30323 L. L. Williams Operating Plants Projects Regional Manager Westinghouse Electric Corporation - R&D 701 P. O. Box 2728 Pittsburgh, Pennsylvania 15230
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r EllCLOSURE REQUEST FOR ADDITIONAL INFORMATION INSERVICE INSPECTION PROGRAM McGuire Nuclear Station By letter dated November 7, 1984,(2) from H. B. Tucker (Duke Power Co.)
to H. R. Denton (NRC), you submitted a proposed inservice inspection (ISI) program for McGuire Nuclear Station, Units 1 and 2 first ten-year inspection interval. We will be evaluating these programs and using them with the documents referenced in them and other documents (see attached document review' list) to review your ISI program and exemptions from examination.
If there are any relief requests or supporting information you wish considered, please provide us with copies.
If they have been previously furnished to the NRC, please document by reference.
However, any previous relief requests, regardless of being previously -
furnished to the NRC as a preservice inspection or preliminary inservice inspection relief request, must be resubmitted with the current inservice inspection program.
The following questions address the ISI program for both units except where specifically noted.
1.
Additional plant detail is needed for adequate evaluation of inservice inspection program compliance with the requirements of ASME Section XI. The following is a list of such additional documents, drawings, and information.
For each item, a brief reference to the applicable Code requirement is given.
(a) Provide color-coded flow diagrams identifying Class 1, 2, and 3 systems and the examination requirements on each portion of th'ose systems, including pressure and hydrostatic test boundaries and test pressures.
(These are contained, except pressure and hydrostatic test boundaries, in controlled copies of the ISI program but not in NRC review copies.)
a
p-(b) Provide applicable piping and instrument diagrams and pump and vessel drawings showing ID nunbers from the ISI program plan for welds, components, and component supports. Diagrams should also indicate which systems or vessels are examined when the similar multiple train concept is used.
(IWB, IWC, and IWD allow weld examination based on minimum weld sampling size or similar multiple system design.)
(c) Sections 4.1, 5.1, and 6.1 of Volume 1 of the ISI plan list Class 1, 2, and 3 components to be examined, by Code item number, in Tables IWB-2500-1, IWC-2500-1, and IWD-2500-1. These lists do not include all items defined in these tables. Provide a complete Section XI item number list with non-applicable item numbers clearly marked.
(d) Volumes 2 and 3 list the detailed examination schedule for Units 1 and 2.
The examination schedule is a computer listing of compo-nent examination by outage number.
Section XI examinations are based on inspection periods, defined in Table IWB-2412-1, with certain percent of weld examinations to be performed in specific inspection periods. Provide a recompiled computer listing of examinations specifying the.following information for each Section XI item nunber:
(1) component description (2)Section XI item nunber (3) examination method (4) first interval sample size (either total number of welds, length of weld or number of component supports, as applicable)
(5) number or length of welds or component supports to be exam-ined in each of the three inspection periods.
(6)
For Class 1 and 2 piping, also give the total number of,
wel ds. List the nunber of welds by item nunter, broken into the number of welds conforming to each of the applicable notes in the IWB and IWC tables.
(Table IWB-2500-1, Exami-nation Category B-J, bases sample size on notes la, lb, ic, 2
id; Table IWC-2500-1, Examination Category C-F, allows sampling size criteria for piping welds based on notes la, lb,id(3),id(4).)
(e) List Class 2 systems required to operate or support safety system f unctions.
(IWC-2500-1, Examinations Category C-H, Note 7)
(f) List Class 3 systems and their integral attachments which support reactor shutdown, ECC, containment heat removal, atmospher clean-up, reactor residual heat removal, and residual heat removal from spent fuel storage pool.
(IWC-2500-1 requires examination of these items and their integral attachments.)
2.
The ISI program plan for units 1 and 2 is written to be in accordance with the 1980 Edition of ASME Section XI, including all addenda through Winter 1980. This edition is appropriate for Unit 2; however, Unit 1 operating license is dated July 8,1981, which gives the Code of record as 1977 through Sumer 1979. Approval must be requested per 10 CFR 50.55a(g)(4)(iv) to update the Unit 1 ISI program to the 1980 Edition of ASME Section XI, including all addenda through Winter 1980.
3.
Complete determination of compliance with Sect. ion XI examination requirements and extent of components examined is not possible until information requested in Item 1 above is provided. However, the list below gives Unit 1 items or examinations currently omitted from the ISI pl an. Any such requirements deemed impractical must be justified by requests for relief.
(a) Steam generator nozzle-to-safe end butt welds (Examination Category B-F, Item numer 85.10) are not to be surface examined (see comment section in Volume 2 of the ISI plan).
(b) No Class 1 integrally welded attachments on piping, pumps, or' valves, are identified under the applicable category (Examination Category B-K-1, Item nusers B10.10, B10.20, and B10.30). How-ever, a reactor coolant pump 1A support lug is mentioned under the.
augmented inspection of reactor coolant pump flywheel.
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t (c) Class 1 pump casing internal surfaces (Examination Category B-L-2, 2
Item number B12.20) are not to be examined.
(d) Branch connections on safety injection loops 1, 2, 3, and 4 (Examination Category B-J, Item number 89.31) are to be volumet-rically examined from the pipe side only.
(e) Reactor vessel core support structure (Examination Category B-N-3, Item number 813.30) is not to be examined.
(f) RHR System weld number IND 69A-3 (Examination Category C-F, note 1(a)) is not to be examined as required.
(g) Snubber tests are not scheduled, as required by Paragraph IWF-5000.
4.
Section XI requires meeting certain schedule requirements for
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performing examinations, with deferral of some canponent examinations
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allowable, as specified in the applicable tables. A complete evalu-ation of compliance with these requirements is not possible until information requested in Item 1(d) above is provided. However, with information currently available, the items listed below apparently now do not conform to the Code schedule requirements.
Items that cannot meet schedule requirements will require relief requests.
(a) Unit 1 reactor vessel shell-to-flange weid (Examination Category B-A, Item number B1.30) to be examined during Outage's 1 and 6.
(b) Unit 1 reactor vessel head-to-flange weld-(Examination Category B-A, Iten Bl.40) to be examined during outages 1, 3, and 6.
(c) Unit 1 pressurizer shell-to-head laigitudinal and circumferential welds (Examination Category B-8, Item numbers 82.11 and B2.12) to be examined during Outages 2 and 6.
(d) Unti i pressurizer pressure-retaining bolting, 2 inches and less in diameter (Examination Category B-G-2, Item number B7.20) to be examined during Outage 3.
(e) Unit i reactor coolant pump seal gland bolting, 2 inches and less in diameter (Examination Category B-G-2, Item number 87.60) to be examined during Outage 2.
(f) Unit i reactor vessel interior (Examination Category B-N-1, Item number 813.10) to be examined during Outages 1 and 6.
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(g) Class 1 systems leakage tests (Examination Category B-P) not to be 2
performed during Outage 7.
5.
Several augnented inspection commitments were made during plant licensing.
Little review information on these augmented inspections, other than pump flywheel and pipe rupture protection examinations, has been provided.
Background information and commitments should be sub-mitted. This should include enough information to enable evaluation of the volumetric examination, defined as "best effort UT due to con-figuration," for augnented inspection of steam generator modification, safety injection system modifications, and thermal sleeve removal.
6.
The licensee's letter dated November 5,1984,(I) changed the augmented inspection plan for pipe rupture protection. The previous commitment called for accumulator injection line with inspection at system pres-sure and temperature of 450 psig and 1500F. Reference 1 proposed to.
examine the subject welds while the system is depressurized. The current ISI program plan calls for inspection at 450 psig and 1500F.
The licensee is requested to resolve this conflict.
If the-ISI program is changed to reflect the Reference 2 plan, relief must be requested from the previous commitment.
7.
Section 2.1.2 of the ISI program plan defines Class 2 exempted components as those systems with design pressure and temperature less than 275 psig and 2000F. However, IWC-1220 defines the exemptions as 5
above but excludes Residual Heat Removal Systems and Emergency ' Core Cooling Systems from the exemption. The licensee should state if these Class 2 systems are included in the ISI program. Relief must be requested for any portions of these systems that cannot be examined.
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References 1.
H. B. Tucker (Duke Power Co.) to H. R. Denton (NRC), McGuire Units 1 and 2, Nove2er 5,1984.
2.
H. B. Tucker (Duke Power Co.) to H. R. Denton (NRC), McGuire Units 1 and 2, Noveder 7,1984.
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REVIEW DOCUMENT RECORD Unit (s)
W. B. McGuire Units 1 & 2 ID number and Date Author - Recipient Type Subject Matter 2/ 1/79 Parker (Duke)to Denton (NRC)
Sub.
Unit 1 PSI Relief Request and PreliminatrISI Relief Request 2s 9/79 Boyd (NRC) to Parker (Duke)
Ltr.
Augmented ISI for Pipe Rupture Protection 3/ 22/79 Parker (Duke) to Denton (NRC)
Ltr.
1/81 SER NUREG-0422 Supp. 4 - Unit 1 ISI 7/ 13/82 Parker (Duke) to Denton (NRC)
Sub.
Thermal Sleeve Evaluation Report 1 L/24/82 Adensam (NRC) to Tucker (Duke)
Ltr.
Request of Outstanding Information 1l?/22/82 Tucker (Duke) to Denton (NRC)
Ltr.
Prelimina.ry ISI and PSI Relief Requests u
1314/83 Tucker (Duke) to Denton (HRC)
Ltr.
Removal of Thermal Sleeves 1/11/83 Tucker (Duke) to Denton (NRC)
Ltr.
Unit 2 Hydro Testing Relief Request 1s 19/83 Tucker (Duke) to Denton (NRC)
Ltr.
Unit 2 PSI Relief Request 2/83 SER NUREG-0422 Supplement 6. Unit 2 ISI 11 /5/84 Tucker (Duke) to Denton (NRC)
Ltr.
Augmented ISI for Accumulator Infection Line Welds Denton-and 1: /7/84 Tucker (Duke) to Adensam (NRC)
Sub.
ISI Plan: '!olumes I, II, III (Rev. 6)
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McGuire FSAR Q-121-7 to Q121-13 Sub.
PSI and ISI Questions and Responses
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