ML17324B252
| ML17324B252 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/27/1987 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:0561B, AEP:NRC:561B, NUDOCS 8703040232 | |
| Download: ML17324B252 (8) | |
Text
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ACCESSION l4BR:
FACIL:5q-3i5 50;3i6 AUTH. NANE ALEXICH,N. P.
RECXP. NANE REQULATORY FORNATION DISTRIBUTION.SY< EN (R IDS) 8703046232 DOC. DATE: 87/02/27 NOTARIZED:
NO DOCKET 0 Donald C.
Cook Nuc.lear Power Plant>
Unit i> Indiana 5
050003i5 Donald C.
Cook Nuclear Power Plant.
Unit 2> Indiana 5
050003ib AUTHOR AFFILXATION Indiana h Michigan Electric Co.
RECIPIENT AFFILIATION Document Control Bl anch (Document Control Desk)
SUBJECT:
Advises of commitment to update prospected ref temp for PTS using new methodology within next three mrs h-confirms info given berballg to NRC on Sbi222. Reanalysis of i984 fluence calculations unnecessarM.
DISTRIBUTION CODE'049D COPIES RECEIVED: LTR g ENCL i SI ZE:
TXTLE; OR,, Submittal:
Thermal Shock to Reactor Vessel.
NOTES:
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MXQQINQTON.D PNR-A RSB INTERNAL: ADN/LFNB
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 February 27, 1987 AEP:NRC:0561B 10 CFR 50.61 Donald C.
Cook Nuclear Plant Unit Nos.
1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 10 CFR 50.61 PRESSURIZED THERMAL SHOCK RULE U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555
Dear Sirs:
This submittal is made pursuant to a concern raised by the NRC staff on the methodology used to calculate the peak neutron fluence values contained in the Southwest Research Institute (SwRI) reports referenced in submittal AEP:NRC:0561A, dated January 22,
- 1986, and serves to confirm information given verbally to the NRR staff on December 22, 1986.
The SwRI reports for Donald C.
Cook Units 1 and 2 were transmitted to the NRC via letter AEP:NRC:0894A, dated July 20, 1984.
The NRC staff indicated concern that we were using a first order Legendre polynomial (P ) rather than the third order, (P3) in development of the finite-order Legenhre expansion of the differential scatter cross sections.
In particular, the staff's concern centered around SwRI's use of a Pl expansion of the scattering matrix in lieu of the P
expansion for calculation of cumulative neutron fluence values.
)he NRC staff also noted that use of P3 expansion of the scattering matrix would result in a higher cumulative neutron fluence.
This higher fluence would result in higher projected Reference Temperature for Pressurized Thermal Shock (RT-PTS) values.
Discussion with SwRI indicated that P
expansion was the state-of-the-art technique in 1984, when tI1e latest Unit 1 and Unit 2 reports were prepared.
They also verified that transport calculations using the P
approximation are greater than those using the P
approximation by 15-203.
Subsequent to preparation of those reports, Swill began using newer methodology.
SwRI is currently evaluating the recently removed Unit 2 reactor vessel material surveillance specimen (Capsule X) using more 8703000232 870227 PDR ADOCK 050003%5 P
POR
+
~
AEF:NRC:0561B advanced techniques.
These include use of the P
expansion of the scattering matrix.
The report on this Capsule X analysis, which is scheduled to be submitted to the NRC in mid-1987, will be used to update our submittal on projected Reference Temperatures (RT-PTS) for Unit 2.
Similarly, the Unit 1 projected RT-PTS will be updated following analysis of Capsule U, scheduled to be removed at the end of the Cycle 10 (estimated to be mid-1989).
Our submittal AEP:NRC:0561A shows the projected RT-PTS values for both Unit 1 and Unit 2 to be well below the screening criteria of 10 CFR 50.61.
Sensitivity calculations demonstrate that significant increases in fluence (on the order of 100$ for Unit 1 and 700% for Unit 2) would be necessary to exceed the screening criteria prior to expiration of the operating license for either unit.
Increases in projected fluence as a result of using the new methodology (i.e.,
P3 expansion of the scattering matrix) are not expected to be of such magnitude and should have a minor effect on projected RT-PTS values.
Based on the relatively minor impact of the new methodology on projected RT-PTS and our commitment to update both units'rojected RT-PTS values using the new methodology within the next three years, we believe reanalysis of the 1984 fluence calculations is unnecessary, and we request that the staff complete the review of letter AEP:NRC:0561A as previously submitted.
This document has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its accuracy and completeness prior to Signature by the undersigned.
Very truly yours, I
P.
lexich g$~l'lg.
Vice President cm cc:
John E. Dolan W.
G. Smith, Jr.
- Bridgman R.
C. Callen G. Bruchmann G
~ Charnoff NRC Resident Inspector J.
G. Keppler
- Region III
February 13, 1987 DOCKET NO(S).:
50-315 Nr. John Qolan> Vice President Indiana and Michigan Electric Ccetpany c/o 2hmrican Electric Power Service Corporation 1 Riverside PlBRaza Ccxbumbus F Ohio 43216
SUBJECT:
D. C. Cook Nuclear Plant, Unit 1 DZETRIlg'.ON: w/o enclosure
~DOCKET FILE PNRI4 Rdg NDuncan DWigginton OGC-Bethesda
~CRS (lo)
JPartlow BGrimes EJordan NThompson NRC PDR Local PDR The following documents concerning our review of the subject facility are transmitted for.
your information.
Notice of Receipt of Application, dated Draft/Final Environmental Statement, dated Notice of Availability of Draft/Final Environmental Statement, dated Safety Evaluation Report, or Supplement No.
dated Environmental Assessment and Finding of No Significant Impact, dated Q Notice of Consideration of Issuance of Facility Operating License, or Amendment to Faci1 ity Operating License, dated Q Bi-Meekly Notice; Applications and Amendments to Operating Licenses Involving No Significant Hazards Considerations, dated 02/11/87
[8ee page t'8) ]
4409 Exemption, dated Construction Permit No.
CPPR-
, Amendment No.
dated Facility Operating License No.,
Amendment No.
dated Order Extending Construction Completion Date, dated Monthly Operating Report for transmitted by letter dated
+ Annual/Semi-Annual Report-transmitted by letter dated
Enclosures:
As stated I
fi cc:
See next page Office of Nuclear Reactor Regulation OFFICE/
t SURNAME/
DATE)
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Ngpncan/ ma 02/+ /87
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02/>
/87
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