ML20030A340
| ML20030A340 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 06/29/1973 |
| From: | Walke G CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101090342 | |
| Download: ML20030A340 (3) | |
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Ponct 6Q"/' / C0mp3Hy General Onces; 212 West ui igar. Avenue. Jackson. Machigan 49201. Area Code S17 788 0550
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t-R : Docket 50-155 Mr. John F. O' Leary Director of Licensing C: r :: :[#. [2 DPR-6 US Atomic Energy Co==ission
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/Y Proposed TS 39
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Dear Mr. O' Leary:
Transmitted herewith as Attachment A are three (3) executed and thirty-seven (37) conformed copies of a Request for Change to the Technical Specifications of License DPR-6, Docket 50-155, issued to Consumers Power Ccmpany on May 1,1964 for the Big Rock Point Plant.
This proposed change (No 39) is submitted as a result of the study performed pursuant to Mr.'Angelo Giambusso's request of December 18, 1972 regarding the consequences of postulated pipe failures outside the contain=ent structure at the Big Rock Point Plant.
The study of the postulated break, also submitted, is in two parts. The results of these studies are contained in Attachments B and C, respectively.
Attachment B - Effect of Compartment Pressurization Due to Pipe System Break Outside Containment Attachment C - Evaluation of the Effects of Jet Thrust and Pipe Whip Due to Pipe System Break Outside Containment These studies were performed by Bechtel Corporation at Consumers Power Company's request.
The results of the stress analysis performed for the main steam and feed-water lines (which are the only lines of concern) reveal thct total stresses are in all cases less than 50% of the value allowed by the evaluation criteria and in many cases less than 25% of the criteria allowed values. Based on these stress levels, we consider a break in lines not to be credible and thus have concluded that the =cd-ifications discussed in Attachments B and C are not required.
In addi-tion to the low stress levels, we have determined that the nil ductility 5150
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Mr. A. Giambusw.
2 Dockst 50-155 DPR-6 June 29, 1973 transitiori temperature for the type of material used in the main steam
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and feed-water lines (ASTM A-106 GrB) is approximately TO F.
The piping system design is such that these lines are not pressurized during plant operations.to full operating pressures unless the temperatures are several hundred degrees above this temperature. Thus, essentially no potential exists for brittle type failures.
In order to further reduce the probability that this piping might crack in a ductile manner, we are proposing to expand the scope and increase the frequency of the ASME Section XI, In-Service Inspection Program. This expanded inspection program would include all circumfer-i ential velds in the main steam line from the containment penetration to l
the turbine stop valve and the feed-water line from the containment' I
penetration to the main feed-water pu=p discharge valve. The piping in these lines is seamless. All circumferential velds in these lines vill be inspected during a ten-year period, the first period cccmencing in 197h. Further, we vill upgrade the pipe tunnel leak detection sys-tem such that it is sensitive to small leaks and we are proposing a Technical Specifications limit requiring plant shutdown if a leak rate from the main stea= and feed-water lines of greater than one gallon per minute develops. These actions vill ensure that if a crack vere to de-l velop, it would be detected at an early stage prior to progressing to a point of major pipe failure.
Proposed Technical Specifications Change No 39 ( Attachment A) is submitted for your consideration assuming that you will agree that the more rigorous in-service inspection and leak detection programs are an acceptable alternative to plant modifications. When you indicate agreement, we vill proceed with the necessary equipment purchases to implement the leak detection system.
It is estimated that this leak detection system can be operational about' three months after purchasing action is started.
Yours very truly, i
l Gerald J. Walke (Signed)
RBS/mel Gerald J. Walke Nuclear Fuels Administrator
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CC: BHGrier, USAEC
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AEC DIST'tIEUTICN FOR PART 50 T00'".T PATERI AL
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DATE OF DOC DATE REC'D LTR IC2:0 RET OEk Consumers Power Company Jackson, "!ichigan 49201 rcrald J. Walhe 6-29-73 7-2-73 X
TOs SOiT LOCAL FDR Mr. O' Leary 3 signed CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DCCKET 1:0:
XX 40 50-155 y
DESCRII' TION:
ENCLCSULES:
Ltr rc our 12-18-72 Itr, trans the ATTACli:!ENT A - Recuest for Change to the following:
Tech Specs (Change No. 39)
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