ML20002C447
| ML20002C447 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/12/1978 |
| From: | Skibitsky W CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8101100313 | |
| Download: ML20002C447 (7) | |
Text
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' s Consumers PocCr
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C0mpBRy c.n.r.i ome..: 2i2 w.st Wcnigen Avenue. Jackson. Mecnigen 49201 e Area Code 517 788 OSSO
,i June 12, 1978 i
Director, Nuclear Reactor Regulation Att: Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 v4 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - REACTOR VESSEL SURVEILLANCE ADDENDUM By letter dated July 29, 1977, Consumers Power Ccmpany responded to an NRC staff request to provide information concerning reactor vessel materials and associated surveillance programs.
Much of the information required by the staff was unavailable at the time. A search of vendor documentation was conducted and all available information was retrieved.
Thus, a revised response is now being submitted as follows:
ITEM 1.
Provide the estimated maximum fluence (E > 1 Mev) at the inner surface of the reactor vessel wall as of March 31, 1977.
RESPONSE
1.
1.5 x 10 m/cm.
ITEM 2.
Provide the effective full power years (EFPY) of operation accumulated as of March 31, 1977.
RESPONSE
2.
Approximately 10.5 EFPY.
ITEM 52 I 8 8-5616000;c.-
3.
Identify the firm that fabricated your reactor vessel.
RESPONSE
3.
The vessel was fabricated by Combustion Engineering for General Electric.
8101100313
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ITEM 4.
a) Provide a sketch of the reactor vessel showing all material welds in the beltline region and provide an identification number for each material.
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RESPONSE
4.
a) combustion Engineering Dwg No E-201-794-8 is provided.
A single 360*
circumferential weld exists in the beltline. Additionally, the two longitudinal welds above the circumferential weld and the two below are shown.
ITEM 4.
b) Provide the following information for each of the welds in the beltline region:
(1) Shop control number of procedure qualification number; (2) Filler matal and heat number; (3) Type o F7x and batch number; t
(4) Welding r cess (sub arc, electroslag, manual metal arc, etc);
(5) Post-weld 2.at treatment; (6) Chemical compositica (particularly Cu, P and S content);
(7) Drop weight Tndti (8) RTndt3 (9) Charpy upper shelf energy (unirradiated);
(10) Tensile properties (unirradiated);
(11) Firm performing' weld if more than one firm participated in welding; (12) The maximum end-of-life fluence at the vessel inner wall.
RESPONSE
4.
b)
(1-3) No definitive records are available.
As noted on Dwg No E-201-794-8, a very general GE specification along with a CE general welding procedure were employed.
ASME Boiler Code Section I (1953Ed) and appropriate nuclear code cases were considered.
GE reactor vessel specification DP-19889 also provided some specific welding. delines.
4.
b)
(4) A submerged metal are welding process was employed - CE Specification SAA-33A(3).
4.
b)
(5) The post-weld heat treatment involved 21.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of total stress relief heat treatment at 1125*F
- 25"F.
4.
b)
(6) The chemical composition is documented in weight percent as:
.12C, 1.25Hn,.28Si,. 014P s.
.012S,.10Ni,.19Cr,.53Mo,.03V, and.27 Cu.
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4.
b)
(7-8) There were no tests conducted to determine these characteristics. There were no drop weight tests and no full Charpy curves.
4.
b)
(9) Three Charpy V-notch tests were per coupons welded as a continuation of the circumferential weld seam.
These tests were conducted at + 10*F and yielded 50.0, 53.5 and 53.5 ft-lb energy.
Assuming that each of the specimens reali. zed.035 in lateral expansion, present day ASME Section IIT. requirements would provide for an RT f -50*F.
ndt 4.
b)
(10) Two.505 in tests were performed to result in a yield / ultimate data pair of 64.75/83.0 KSI and 64.0/82.0 KSI.
Two reduced section transverse tensile tests were also pr.rformed to provide a yield /ultimste data pair of 102.5/11'.5 KSI and 102/5/133.75 KSI.
4.
b)
(11) All welding was performed by Combustion Engineering.
4.
b)
(12)
Themaximumend-ofgifegluenceatthevesselinnerwallis 3
estimated to be 5.8 x 10 m/cm (E > 1 Mev) for 40 years at 240 MW.
ITEM 4.
c)
Provide the following information for each of the plates for forgings in the beltline region:
(1) Plate or forging serial number; (2) Plate or forging heat number; (3) Plate or forging material specification number; (4) Plate or forging supplier; (5) Plate or forging heat treatment; (6) Chemical composition (particularly Cu, P and S content);
(7) Drop weight Tndti (8) RTndt (unirradiated);
(9) Charpy upper shelf energy (itnirradiated);
(10) Tensile properties (unirradiated);
(11) The maximum end-of-life fluence at the vessel inner wall.
RESPONSE
4.
c)
(1-2) Four plates surround the vessel beltline region per CE Dwg No F. -201 - 7 34 - 8.
These plates and their heat numbers are:
Plate No (CE)
Heat No (Lukens Steel)
S-5503-1 19246-1 S-5503-2 19246-2 S-5503-3 19246-3 S-5503-4 19246-4 i
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c)
(3-4) The plate was purchased by CE to an ASTM A-302-56 Gr B specification nodified by CE specification P-3-F2(b). The plate wa.s provided by Lukens Steel.
4.
c)
(5) The plates were melted in a basic open hearth furnace and aluminum treatd in the ladle to achieve fine grain size.
The plates were air cooled and hot rolled and shipped to Combustion Engineering.
At CE, the plate was heat-treated as full plate as follows:
(1) 1600 + 25*F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(2) Brine quenched.
(3) 1225 + 25*F for 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
(4) Furnace cooled.
(5) 1125 + 25*F for 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.
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(6) Furna e cooled.
4.
c)
(6) The plate chemistry per Lukens Steel is weight per cent:
.18C, 1.42Mn,.25Si,.016P,.021,.18Ni,.13Cr,.51Mo,.02V and.10Cu.
4.
c)
(7-8) There were no tests conducted to determine these characteristics.
There were no drop weight tests or full Charpy curves.
4.
c)
(9) Charpy upper shelf energy information is not available for the vessel plate.
However, a number of Charpy tests were conducted at
+10 F.
The results of these base metal tests are listed below:
Direction Charpy - V, 10*F Plate No Heat No to Rolling in Ft-Lb S-5503-1 19246-1 Parallel 69.5, 65.5, 54.0 Transverse 30.0, 26.5, 30.0 S-5503-2 19246-2 Parallel 63.0, 54.0, 40.5 Transverse 27.0, 26.5, 29.5 S-5503-3 19246-3 Parallel 54.5, 47.5, 32.0 Transverse 20.5, 34.5, 28.0 S-5503-4 19246-4 Parallel 47.0, 44.0, 43.0 Transverse 29.0, 22.5, 27.5 The above tests were cut from a full 6-inch plate after its heat treatment as is 4.c) (5) above.
4.
c)
(10) The tensile properties of the four plates were determined from Lukens tests during which samples were heat-treated as follows:
Austenitize 1650-1700*F - 4 Hours Water Spray to 400*F in 12 Minutes Temper 1200-1250 F - 6 Hours Furnace Coal to 600 F
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Lukens Heat No Yield Psi Tensile Psi
% & Long (2 In) 19246-1 56,900 84,200 23 19246-2 58,200 86,100 22 19246-3 52,300 86,400 22 19246-4 56,500 81,500 20 4.
c)
(111 The end-of-life fluence used for all welds and pla*.es is 5.8 x 1019 m/cm2 (E > 1 Mev) evaluated at 240 MW for 40 years.
ITEM 5.
a) List the weld, plate and forging materials included in the vessel surveillance program.
RESPONSE
5.
a) For the surveillance program, the ends of two plates were provided to General Electric Company by Combustion Engineering. These ends were taken from plate numbers S-5503-2 and S-5503-3.
The base metal samples for the surveillance prr dram were taken from S-5503-2.
A test weld for the surveillance prog
- am was fabricated to simulate a shell 4
plate longitudinal weld. The 4etails of this weld fabrication are in Appendix G of the surveillance program description (attached).
ITEM 5.
b) For each weld listed in 5.a), provide the information in items (1) through (11) of 4.b).
RESPONSE
5.
b) Tbe weld specified in 5.a) was intended to simulate the actual characteristics of the vessel wald; therefore, the information of 4.b) applies.
During the execution of the surveillance program, the weld metal surveillance coupons were tested. This test information is provided in the attached NRL report.
ITEM 5.
c) For each plate or forging specimen listed in 5.a), provide the information listed in items (1) through (10) of question 4.c).
RESPONSE
5.
c) Consistent with the response to item 5.b) above, the attached NRL report is again referenced for the tabular detail on vessel plate i
coupon testing.
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5.
d). Provide a copy of the report which describes that surveillance program for your reactor vessel.
RESPONSE
5.
d) The Manual is: attached.
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7 William S Skibitsky.
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- Senior Licensing Engineer CC: 'JGKeppler, USNRC' e
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATER 11L 50-155 REC: ZIEMANN D L ORG: SKIBITSKY W S DOCDATE: 06/12/78 NRC CONSUMERS PWR DATE RCVD: 06./15/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED LTR 1 ENCL 40
SUBJECT:
FURNISHING REVISED RESPONSE TC APPLICANT"S SUBMITTAL OF 07/29/78 WHICH PROVIDED INFO CONCERNING THE REACTOR MATERIALS AND ASSOCIATED SURVEILLANCE PROGRAMS OF GUBJECT FACILITY.
W/ATT.
U CA' REVIEWER INITIAL:
XJM PLANT NAME: DIG ROCK PT DISTRIBUTOR INITIAL: $JL
- DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
REACTOR VESSEL MATERIAL SURVEILLANCE (DIGTRIDUTION CODE A021)
FOR ACTION:
BR CllIEF ORBtt2 BC**W/3 ENCL ZWETZIG**W/ ENCL
- W/ ENCL NRC PDR**W/ ENCL
[1 IVilt/2 ENCL OELD**LTR ONLY INTERNAL MIPC**W/ ENCL HANAUER**W/ ENCL t1ATERIAL ENG BR**W/ ENCL AD FOR OPER TECH **W/ ENCL ENGINEERING BR**W/ ENCL REACTOP SAFETY BR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL,
EEB**W/ ENCL HAZEL. TON **W/ ENCL HOGE**W/ ENCL R GAMBLE **W/ ENCL RANDALL**W/ ENCL EXTERNAL:
LPDR'S CHARLEVOIX, MI**W/ ENCL TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL DISTRIBUTION:
LTR 40 ENCI 39 CONTR._ JER:
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N P00R ORIGINAL
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