ML20040A723

Notifies That Proposed Revision to Tech Specs Re Reactor vessel-temp Limits Are Not Acceptable.Amended Proposal Should Be Forwarded within 30 Days

ML20040A723
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	12/29/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Hoffman D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
LSO5-81-12-091, LSO5-81-12-91, NUDOCS 8201220008
Download: ML20040A723 (7)

Text

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DISTRIBUTION Docket December 29, 1981 NRC PDR Local PDR ORB Reading NSIC e)

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Docket No. 50-155 4,

DCrutchfield f,

LS05-81 091 REmch ggCEW60 WPaulson HSmith 6

OEC301981* O OELD Mr. David P. Hoffman 7 samanwisasus 4 OI&E (3)

Nuclear Licensing Administrator o

asa massa n ACRS (10)

Consumers Power Company g

SEPB 1945 W. Parnall Road C6 WJohnston Jackson, Michigan 49201 SPawlicki PRandall

SUBJECT:

BIG ROCK POINT - REACTOR VESSEL PRESSURE - TEMPERATURE LIMITS The staff has completed a review of your proposed revision of the reactor vessel pressure - temperature limits in the Technical Specifications for Big Rock Point Plant, which were submitted by your letter of September 18, 1981. We find that your proposed revisions are not acceptable. Enclosed comments explain why the proposed revisions are not acceptable and should be used as guidance in preparing an amended proposal.

Please forward your amended proposal to us within 30 days of the receipt of this letter.

Sincerely, Original signed by Walter A. Paulson for/

Dennis M. Crutchfield, Chief Operating Reactors Branch f5 Division of Licensing

Enclosure:

As stated cc w/ enclosure:

See next page DL,:

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8201220008 811229

- PDR ADOCK 05000155 OFFICIAL RECORD COPY uscro; issi-ass 9eo Nn PDR

m Mr. David P. Hoffman December 29, 1981 cc Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Conpany Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office ATTN: Regional Radiation Representative Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Power Company Chicago, Illinois 60604 212 West Michigan Avenue Jackson, Michigan 49201 Herbert Grossman, Esq., Chairman Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Commission Isham, Lincoln & Beale Washington, D. C.

20555 1120 Connecticut Avenue Room 325 Dr. Oscar H. Paris Washington, D. C.

20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Consission Peter W. Steketee, Esquire Washington, D. C.

20555 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Regulatory Consission Atomic Safety & Licensing Appeal Board Washington, D. C.

20555 U. S. Nuclear Regulatory Comission Washington, D. C.

20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, II Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Mic' igan 49664 n

Christa-Maria Charlevoix Public Library Route 2, Box 108C 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, Michigan William J. Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigan 48103 Charlevoix County Charlevoix, Michigan 49720 Resident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S. NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Michigan 49720 Herbert Semel Mr. Jim E. Mills Counsel for Christa Maria, et al.

Route 2, Box 108C Urban Law Institute Charlevoix, Michigan 49720 Antioch School of Law 2633'16th Street, NW Washington, D. C.

20460

i Mr. David P. Hoffman December 29, 1981 l

j EC Dr. John H. Buck l

Atomic Safety and Licensing Appeal Board j

U. S. Nuclear Regulatory Comission Washington, D. C.

20555 1

l Ms. JoAnn Bier i

204 Clinton Street Charlevoix, Michigan 49720 Thomas S. Moore Atomic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Comission Washington, D. C.

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ATTACHMENT COMMENTS ON PROPOSED BIG ROCK POINT PRESSURE-TEMPERATURE LIMITS The proposed revision give; pressure-temperature limits in tabular form n/cm2 (E y 1 MeV) and a shift of 135 degrees F.'

for a fluence of 4.5 x 1019

. Appendix A, Paragraph B implies that shift is' considered to be independent of fluence in the range 1.2 to 4.5 >,10l9, i.e., that situration has taken place, as evidenced L.,

the surveillance data cited in the report

" Analysis of Capsule 125...", which was attached to the submittal.

No information is given in the proposed revision regarding the present condition of the vessel as tc fluence or EFPY, nor does it give a date l9 or value of EFPY associated with the fluence of 4.5 x 10 Capsule 125, which was withdrawn in February 1979, was reported to have received a fluence of 2.27 x 1019 n/cm2 (E71 MeV) after 8.6 EFPY.

No lead factor was cited for this capsule.

In a telephone conversation with Rolfe Jenkins, he indicated that the capsule was located roughly one-half inch from the wall, and the lead factor was therefore only slightly greater than one.

Our principal problem with the submittal is with the saturation concept that is the basis for the proposed use of a " flat" 135 degrees F as the shift value to be considered applicable throughout the period until a fluence of 4.5 x 10 is received at the vessel ID wall.

Despite considerable effort (funced by EPRI) to prove saturation in recent years,

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and despite some evidence that A302B material and low-nickel welds accumulate neutron damage more slowly in the fluence range in question than A533B material and high-nickel welds, the staff feels it is necessary to assume that the trend curves have some upward slope.

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. The surveillance results cited in the submittal"show a shift of 135 degrees F 18 l

for a ' fluence of 7.1 x 10 and the identical shift for a fluence of 2.27 x 10l9 (both were wall capsules).

In addition, the shift measured l9 from two accelerated capsules was 130 F for a fluence of 2.3 x 10 and 20 1700F for a fluench of 1.07 x 10 n /cm (E > 1 MeV). -The latter is not a credible surveillance data point.

Serpan and Watson, the original authors, reported the shift as 230 F, having drawn the Charpy curve to bound some badly scattered data.

From its analysis of the data cited above, the staff is willing to agree that surveillance data show the present value of shift to be 135 degrees F; I9 i.e., that the fluence (I.D. wall) is about 2.3 x 10 or slightly higher at the present time.

The following steps are suggested to select the value of RT use for NDT l

calculating the amended prsssure-temperature limits.

(1)

Estimate the value of fluence - per - EFP.Y for the vessel at the 1/4 T position.

(2) Determine the present value of EFPY.

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l (3) From (1) and (2) determine the present value of flue' ce at the 1/4 T n

position an'd also the value predicted for the end of the desired time period, say 7 more EFPY, hs discussed in our telephone conversation.

(4) Plot the present condition of the vessel ( A RTNDT = 135 F at whatever fluence was calculated above) on the attached tentative trend curve

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for low-nickel material.

This curve was developed recently as an empirical upper bo.und fit of the PWR surveillance data for A302B plate and weld of matching composition.

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Extrapolate from the present fluence to the fluence at the end of

.the desired time period, following the slope of the tentative trend Curves.

(6) Add at least 30 degrees to cover the current uncertainties in the at present.

procedure and in the value of 135* for ZiRTNDT

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(7) d RI is the lower of the value obtained above and the value read NDT

'directly from the trend curve for 0.27% copper.

(8) AddsdRT to the initial RT give RT at the end of the NDT NDT NDT operating period for which these pressure-temperature limits are to apply.

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