ML20041G421
| ML20041G421 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/12/1982 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Beckham J GEORGIA POWER CO. |
| References | |
| TAC-07811, TAC-08019, TAC-7811, TAC-8019, NUDOCS 8203220247 | |
| Download: ML20041G421 (7) | |
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ilARCH 1 2 1982 DISTRIBUTI0ft:
ORB #4 Rdg GJohnson, MTEB Docket File DEisenhut DChaney, ORBI flRC PDR liFai rtile OELD L PDR RIngram AE0D Dockets tios. 50-321 and IE 50-366 ACRS-10 Gray File =2 yjs e
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!!r. J. T. Beckhan, Jr.
y Vice President - fluclear Generation 3
Georgia Power Company 2
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P. O. Box 4545 6-ts C Atlanta, Georgia 30302 4
Dear Mr. Beckhan:
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c1 In order to corplete our review of the flatch Plant Unit No.1 Inserv c
Inspection Program relief requests, we find we need the enclosed addi-tional information.
The review 19 being conducted by:
Dr. D. A. Outlaw Science Applications, Inc.
1710 Goodrich Drive liclean, Virginia 22102 and we would appreciate your providing Dr. Outlaw a copy of your response to expedite our review.
Kindly respond to this request within 30 days of the date of this letter.
O!B clearance is not required for this naquest as it is unique to llatch Unit 110. 1.
The flatch Unit Ib. 2 questions will follow within four weeks of this request.
Sincerely,
'CRIGURL:.:1;3D w JOIciF. n e g o John F. Stelz, Chief Operating Reactors Branch f4 Division of Licensing
Enclosure:
Request for Additional Information cc w/ enclosure:
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NRC FORM 318 (10-80) NACM 024o OFFiClAL RECORD COPY usa m ini-su m
Hatch 1/2 Georgia Power Company 5.0-321/355 cc w/ enclosure (s):
Mr. James P. O'Reilly, Regional Adminis trator G. F. irowbridge, Esq.
Shaw, Pittman, Potts and Trowbridge U. S. ~ Nuclear Regulatory Comission Region 11 1800 M Street, N.W.
101 Marietta Street, Suite 3100 Washington, D. C.
20036 Atlanta, Georgia, 30303 Ruble A. Thomas __.
Vice President P. O. Box 2625 Southern Company Servi'ces,!Inc.
Bimingham, Alabama 35202 Ozen Batum Charles H. Badger Southern Company Services, Inc.
Office of Planning and Budget Post Office Box 2025 Room 610 Eirmingham, Alabama 35202 270 Washington Street, S.W.
Atlanta, Georgia 30334 Appling County Commissioners County Courthouse Baxley, Georgia 31513 Mr. L. T. Gutwa Geo'gia Power Company Engineering Department P. O. Box 4545 Atlanta, Georgia 30302 Mr. Max Manry Georgia Power Company Edwin I. Hatch Flant P. D. Box aa?
Ea).iey, Georgia 31E13 Regional Radiation Representative EPA Region IV 3'5 Courtland Street, N.E.
Atlante, Georgia 3030S Appling County Public Library 301 City Hall Drive Baxley, Georgia 31513 fir. R. F. Rogers U. S. Nuclear Regulatory Comission Route 1, P. O. Box 279 Baxley, Georgia 31513 l
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REQUEST FOR ADDITIONAL INFORMATI0H INSERVICE INSPECTION PROGRAM' Hatch 1 1.
Repair Procedures (Section 2.0, Pg 2-1; Section 3.0, Pg 3-1; Section 4.0, Pg 4-1; all Ref. 1)
Some components included in this program were not built to the ASME Section III Code because it was not in effect at the time the component was purchased.
However, these components will be inspected in accordance with the requirements of Subsection IWB to the extent practicable. The repair procedures of IWB-4000 will be applied to those components constructed to Section III of the ASME Code.
For those components not constructed to Sectio?. III of the ASME Code, the rules of IWA-4000 will be applied.
There are three similar statements relating to repai.r procedures; i.e., for m
Class 1, Class 2, and Class 3 components. The following additional information
~is requested:
l1.
Please identify which Class 1 components will not be repaired according to the Code, i.e.,
IWB 4000.
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2.
What is the technical basis for not repairing the abovr listed Class 1 components according to IWB-4000?
3.
What is your evaluation of the degree of safety provided by the appli-cation of IWA-4000 rather than the application of IWB-4000?
2.
Hydrostatic Testina (Section 2.0, Pg 2-1; Section 3.0, Pg 3-1; and Item 7 of Section 4.0, Pg 4-2; all Ref. I) h.,decstatic testing will be concocted in a manner tr.at will satisfy the requirements of IWA-5000 and IUB-5000.
Where adjoining pipe. sections have dif-ferent test pressures, they will' be separated whenever practicable, and each section tested at its specified pressure. Where it is not practicable to separate adjoin-ing sections of piping (e.g., boundary is check valve), t'he sect' ions will be tested together at the lower of the specified test pressures.
No point in the j
piping shall be permitted to experience a pressure greater than the specified test pressure.
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The,re are three si(ilar stafements relat,ing-t;o hydf ostatic 4esting, i.e.,
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for Clais 1,' Class 2,'and,, Class 3 components., The foll'ouing jdditional information
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v s-1.[ Jesse idjntify which adjoining sections'of pipiing that have different.'/,
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. test pres'sures gill be,teste<i"at die lower of the specified test pressur6.
' Pleastj;' submit a' tode relief request for these-item's.
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ASME' Class.J1(Equivalent) Valves ExcSaping' 4-Inches Hominal Pipe Size g
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Table IWB22500, Category / B-M-2, and.Tatle fi.'B'2600, Item B6.7 require visual a
i examination of the internal p'NssTre boundary sef'ce'? of one, valve in each; s i
Group Qf v31ve,'of the same design! manufac.turing method' marMfacturer, and-
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function {o be der. formed once per insrection, interval.
The.tpl10 wing additional, informatin'nisrequ[egted:
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Has ultrasoni,c wall th'ickness measurementsTf the salve'h6 dies been 1,
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c6nlidered a Pan alternative examination ~ method?
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4.
Flued Head Peidtrh.tions (Section 2.1-4, Pg 2-3,def. 1)
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. Table IWB-2500, Category B-J and B-K-1, requires the examiliati6n of cirr4m-r
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.sferential butt,weldi and integrally weldedgipe supports, thjt,are locat.ed within-
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The followirig-additional inforna-flued head containment penetration assemblies'.
. tion is G,nuesteof t.
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m 1&O6stribe tne leak detection systems,tn.at would -ser7e, an/ their.fproximity
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,tD, the-area 5 in which the subject 12 pipe Iaelds 'are }ocatEd.
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PipiEg_Prossure Counfary Welds ~ (Secticn 2.1.6, Pg 2-3b, Ref.1)
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YiabJi 1 6 2600, Cataq q v B-J (Itens"$.5 and 54.6) and',bategory B-K-1 k1 (Item B4.0)', re(uires the volumetric examination of pressure-retaining piping weld 7/ Rddjfisrequestedfrom-performinganexamination'wheretheweldis
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inaccel,sible,' or the geometric configuration prohibits a. full Code inspection.
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i The fol. lowing cdditional,information is reques'ted:
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1.
Plea (e idd.gi(y 2ny we16h for which, code relief can'be requested at thistime.Q
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2.
Estimate the amount of'each' weld theit cannot be excmined according-to
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Provide plans for alternative examinations.
Bolting (Section 3.1[2, Pg 3-2; and Section 3.1.3, Pg 3-3; both Ref.1) 6.
Table IWC-2520, Category C-D, requires examination of pressure-retaining-bolting over one inch in diameter.
The closure fasteners for the HPCI pump are studs and cap nuts. The cap nuts completely. obscure the studs making an in-place volumetric examination impossible.
These studs will receive a surface examination when the pump i.s di.sassembled for maintenance.
The closure studs for the HPCI and RCIC turbine have rounded ends making an in-place volumetric examination impossible.
Relief from inservice examination of these fasteners is requested.
The following additional information is requested:
1.
Is any of the bolting for which code relief is requested', 2-inches in diameter or less, so that exemption under a later code revision would apply?
2.
Based on past experience of these_ and similar pumps and' valves in the industry, what is the likelihood that these pumps and valves would not be disassembled for maintenance during an inspection interval? -
7.
Piping Pressure Boundary Welds (Section 3.1.4, Pg 3-3, Ref.1)
Table IWC-2600, Categories C-F and C-G (Items C2.1, C2.2 and C2.3) requires the volumetric examination of pressure-retaining piping welds.
Relief is requested from performing an examination where the weld is inaccessible or the geometric configuration prohibits a full Code inspection. The following additional informa-tion is requested:
1.
Please identify any welds for which code relief cqn be requested at this time.
2.
Estimate the amount of each weld that cannot be examined according to the Code.
3.
Provide plans for alternative examinations.
8.
Class 3 - Testing of Buried Piping (Section 4.0, Pg 4-1. Ref. 1)
The designs of the service water systems do not include provisions for
' testing buried piping as required by IWD-2600(b).
Visual inspection for leakage at ground' level is also impossible for portions which are buried.
flormal system 3
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functional testing demonstrates leaktight integrity of all buried or encased piping. The following additional information is requested:
'1.
Please identify all buried piping that cannot be tested as required by IWD-2600(b).
9.
Class 3 - System Pressure Testing (Item 5, Pg 4-2, Ref.1)
The system pressure testing requirements of IWD-2410(b) will not be per-formed on lines 2-inches and smaller unless:
(a) They are connected to larger lines which will be pressure-tested.
(b) Isolation valves are not provided so that these smaller lines may be isolated in case of leakage.
The following additional information is requested:
1.
Please identify all lines for which code relief would be required.
Please submit a request for code relief, including specific technical
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justification for each line.
10.
Class 3 - System Pressure Testing (Item-6, Pg 4-2, Ref.1)
System pressure testing as required by IWD-2410(b) is impractical for certain portions of the plant -service water system because it operates. continu-ously during all modes of plant operation.
This functional operation demonstrates the structural and leaktight integrity of the system.
Visual inspection will be performed while the system is under normal operating pressure to,erify leak-tightness, The following additional information is requested:
1.
Please identify all subsystems of the plant service water system for which code relief would~be reauired.
Please submit a request for code relief. ' including specific technical justification for each subsystem.
j '
Can the system be pressure-tested during times when the plant has been i
shut down long enough so the system can be taken safely out of service?
11.
Program Interval (Section 1.2, Ref.1)
'Under the change in Regulation 10 CFR 50.55a effective November 1, 1979, i
l the ISI program for Unit 1 when finally approved, will cover the last 80 months of the current 10-year inspection interval, i.e.,
from April 30, 1979 to I
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December 30, 1985.
Does this result in any changes GPC wishes to make in the relief requests? Does GPC require other ISI relief?
REFERENCE:
1.
Submittal, NRC from W. A. Widner (Georgia Power Company), "Edwin I. Hatch Nuclear Plant, Unit 1 - Inservice Inspection Program", January 27, 1981.
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