ML20083K045
| ML20083K045 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 04/09/1984 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-791, NUDOCS 8404160048 | |
| Download: ML20083K045 (5) | |
Text
{{#Wiki_filter:& m-a E g UNION ELECTRIC COM PANY 1901 GRATIOT STREET ST. Louis, MISSOURI coNato 7. =cHNELL o SOM 14. April 9, 1984 er. Lou..mi..ou...... Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Denton:
ULNRC-791 DOCKET NUMBER 50-483 CALLAWAY PLANT, UNIT 1 STEAM GENERATOR LEAKAGE TEST FOLLOWING PLUGGING
Reference:
FSAR Section 3.9(N) During the life of the plant it may be necessary to plug certain steam generator tubes. It is not Union Electric's intent to repressurize the secondary side to visually clieck for leakage on the underside of the tube sheet following plugging. This is consistent with the exemption from pressure testing and examination in paragraphs IWA-4400(b) and IWA-4500(b) of ASME Section XI, Summer of 1978 Edition. A copy of the revised page from the SNUPPS Standard Plant FSAR page is attached, along with the referenced sections of the ASME Code. This change will be included in FSAR Standard Plant Revision 15. Very truly yours, f h Lk C d'L Donal schnell . DS/jm Attachments cc: J. Holonich e __,. m, ,' F (
STATE OF MISSOURI ) ) SS CITY OF ST. LOUIS ) 1 Robert J. Schukai, of lawful age, being first duly sworn upon oath says that he is General Manager-sugineering (Nuclear) for Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief. l f-By Rob t t J. chukai Gene nager-Enginee:. ing Nuclear SUBSCRIBED and sworn to before me this M day of 198d BARBARA $PFAF[ NOTARY FUBUC, STATE OF MIS 3OURI ,y ~_. NY COMMISSION EXPIRES APRIL 22,1935 ST. LOUIS COUNTY c. ,y L ~ ^ 'r Y b 4
9 1 cc: Glenn L. Koester ~ Vice President 1 4 i Operations. Kansas Gau & Electric P.O.. Box 208 (. Wichita, Kansas 67201 s Donald T. McPhee N, Vice President \\ s -Ne Kansas City-Power and Light Company 1330 Baltimore Avenue ~ l Kansas City, Missouri 'G4141 x. i e,2 ~ Gerald Charnoff, Esq. S N ~ s Shaw, Pittman, Potts & Tro4bri'dge 1800 M. Street, N.W. ' *N Washi~ngtoy,'D,C. 20036 s t x m Nicholas A. Petrick Executive Director \\ 'f ' \\ 'SNUPPS - \\ 5 Choke Cherry Road Rockville, Maryland 20R50 ' John H.'Neislier '. s Callaway: Resident Office -ss\\ U.S.YNuclear' Regulatory Commission A ~ RR$1 e-s S teedman, 'Miesouri : 65077 6 William;Forney_ l Division of Profectc 'and . Resident. Programs, Chief, Section -1A U.S.-. Nuclear Regulatory Commission Region III .s 799 Roosevelt-Road. ( Glen -Ellyn,. Illinois 60137 4 Harold-R.[Denton, Director- --Office of tiuclear-Reactor Regulation ,[ U.S. Nuclear: Regulatory Commission Washington, D.C. 20555 _j g \\ O, 4- ^- s'.. x h ' x- - x i 'g 't b
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SNUPPS i (). t pressure of 0 psig. The RCS is designed for 10 cycles of these hydrostatic tests, which are performed prior to plant star cup. Additional hydrostatic tests will be performed to meet the in-service inspection requirements of the ASME Code, Section XI, subarticle ISS-20. A total'of four such tests is expected. i The increase in the fatigue usage factor caused by these tests is easily covered by the conservative numLer (200) of primary side leakage tests that are considered for design. l Secondary Side Hydrostatic Test l } The secondary side of the steam generator is pressurized to 1,481 psig with a minimum water temperature of 120 F coinci-l' dent with the primary side at 0 psig. j For design purposes, it is assumed that the steam generator l will experience 10 cycles of this test. j i -These tests may be performed either prior to plant startup, or subsequently following shutdown for major repairs or both. i Tube' Leakage-Test During the life of the plant, it may'be.necessary to check the steam generator for tube leakage and tube-to-tube sheet leak-age. This is done by visual inspection of the underside (channel head' side) of the tube sheet for water leakage, with the secondary side pressurized. Tube leakage tests are'per- ' formed during plant cold shutdowns. (ma.ximum. Pre 6Sure on seconchry side. is BAO psig) For these1 tests, the secondary side of the steam gendrator is pressurized with water, initially at a relatively low pres-sure,.and the primary system remains depressurized. ..The underside.cf the tube sheet is examined visually for leaks. If.any.are observed, the secondary side is:then depressurized and repairs made by tube plugging.~ The accondary sidc is.thanA: - repressuriscd ( to c highcr' prcasurc), and thc undcrsidc of thc S
- tubc chect in again checked for leaks. _Thic procecc ic re "-
peatcd until all thc leak; crc repaired. The maximur ( fincl-FL accondcry aide tect precourc recched ic 810 p ig t -The= total number of tube. leakage' test cycles-is-defined as 800 -duringlthe'40-year life ofLthe plant. Following~is a break- .down 'of. the anticipated number of. occurrences at each second-- ary side test pressure: Number of ' Test Pressure'(psig) . Occurrences es. , ' )- 200' 1400 '400 '200 600 120 .840 z 80 Rev.u7 3.9(N)-19
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S GENEQAL REQUIREMENTS IWA-4300-lWA-4700 [ I the repair organiiation. This Program shall include ated valves thit are f in. nominal pipe size and the following: smaller (1) requirements for complete and exclusive Repairs made in accordance with a procedure which p administration and technical supervision of all allows exception from postweld heat treatment shall [ . cider? by the repair orgamzation; not be exempted. j (2) requirements for contractual control which j provides the necessary authority to assign and ( IWA-4500 EXAAIINATION [ remove welders at the discretion of the repair organization; (3) evidence that the Quality Assurance Pro-(a) The repaired areas shall be examined to gram is acceptab!c to the Owner's Authorized establish a new preservice record. The examinations Nuclear Inservice Inspector. shallinclude the method that detected the flaw. (b) If the repair includes the complete removal or isolation of the item bearing the flaw, such as heat exch ng r tub plugging, (a) above shall not apply. i IWA-4400 PRESSURE TEST (a) After repairs by welding on the pressure retaining boundary, a system pressure test shall be IWA-4600 REPLACESIENTS performed m accordance w,th IWA-5000. l i (b) The following may be exempted from the He rules and requirements of this Article shall system hydrostatic pressure tests: apply to the attaching of replacements (as defined in (1) cladding repairs IWA-7tl3) to the system where such attachment is l (2) heat exchanger tube plugging by welding.- [ (3) piping, pump, and valve repairs that do not penetrate through the pressure boundary ,(4) pressure vessel repairs where the repaired IWA-4700 RECORDS cavity does not exceed 107o of the minimum design wallthickness ne records required by IWA-6000 shall be (J) component connections, piping, and associ-completed for all repairs. 4 / ,/ r e 9 e O t ,Y f I e .m +, - 20.1 .+ M}}