ML17174B001
| ML17174B001 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/08/1991 |
| From: | Barrett R Office of Nuclear Reactor Regulation |
| To: | Kovach T COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML17174B002 | List: |
| References | |
| TAC-M81346, NUDOCS 9112040030 | |
| Download: ML17174B001 (3) | |
Text
November 8, 1991 *
- 'fl>*1 ~*
.. \\-:,,r "
D~cket No. 50-249 Mr. Thomas J. Kovach Nuclear Licensing Manager Commonwealth Edison Company-Suite 300 OPUS West I II 1400 OPUS Place Downers Grove, Illinois 60515
Dear Mr. Kovach:
DISTRIBUTION o OifiitiiJ'i4iitle'"
PDIII-2 r/f JPartlow BBoger CMoore OGC GHill (4)
GPA/PA RLob~l WShafer, RIII NRC & Local PDRs TMurley/FMiraglia CRossi JZwolinski BSiegel EJordan ACRS (10)
OC/LFMB PDIII-2 Gray File JDavis
SUBJECT:
RELIEF REQUEST NUMBER CR-14 FOR DRESDEN, UNIT 3 (TAC NO.r181346)
In a letter dated August 23, 1991, you requested relief (Relief Request Number CR-14) from the ASME Code Section XI. This relief is related to the sample expansion requirements for fluorescent magnetic particle examination of the reactor vessel closure studs for one refueling cycle if crack indications are found.
The NRC has reviewed and evaluated your request, and the supporting information provided, and concluded that granting relief from Section XI of the ASME Code requirements, pursuant to 10 CFR 50.55a(g)(6)(i) and (a)(3)(ii), is authorized by law, will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Compliance with the specified testing requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety. The staff has also determined that granting of this relief does not significantly reduce the assurance of the plant's structural integrity or safety. Relief is granted for one cycle provided that your fracture mechanics analysis results in a critical flaw size for the reactor vessel closure studs that is greater than the min.imum size detectable by enhanced ultrasonic examinations. A copy of the staff's safety evaluation related to this relief is enclosed.
(
9112040030 911108
)
"I PDR ADOCK 05000249
\\
P PDR. *
\\'------~-- - ---- ---- -
- -\\-~---"'
Enclos.ure:
Safety Evaluation Document Name:
KOVACH 81346 Sincerely, Ofigina1 Signed By:
Richard J. Barrett, Director Project Directorate III-2 Division of Reactor Pr9jects - III/IV/V AA A.A//
Office of Nuclear Reactor Regulation
/vtff 'f'
Docket No. 50-249 Mr. Thomas J. Kovach e
UNITED STATES
- NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 November 8, 1991 Nuclear licensing Manager Corrmonwealth Edison Company-Suite 300
,OPUS West III 1400 OPUS Place
- Downers Grove, Illinois 60515 *
Dear Mr. Kovach:
SUBJECT:
RELIEF REQUEST NUMBER CR-14 FOR DRESDEN, UNIT 3 (TAC N0/181346)
In a letter dated August 23, 1991, you requested relief (Relief Request Number CR-14) from the ASME Code Section XI.
This relief is related to the sample expansion requirements for fluorescent magnetic particle examination of the reactor vessel closure studs for one refueling cycle if crack indicatfons are found.
The NRC has reviewed and evaluated your request, and the supporting information provided, and concluded that granting relief from Section XI of the ASME Code requirements, pursuant to 10 CFR 50.55a(g)(6)(i) and (a)(3)(ii), is authorized, by law, will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility. Compliance with the specified testing requirements would result in hardship or unusual difficulties without a compensating increase in the level
- of quality and safety. The staff has also determined that granting of this relief does not significantly reduce the assurance of the plant's st,ructural integrity or safety. Relief is granted for one cycle provided that your fracture mechanics analysis results in a critical flaw size for the reactor vessel closure studs that is greater than the minimum size detectable by enhanced ultrasonic examinations. A copy of the staff's safety evaluation ine~ated to this relief is enclosed.
Enclosure:
Safety Evaluation cc w/enclosure:
See next page Sincerely, Ric a
~. Barrett, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Mr. Thomas J. Kovach Conmonwealth Edison Company cc:
Michael I. Miller, Esq.
Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. J. Eenigenburg Plant Superintendent Dresden Nuclear Power Station Rural Route #1 Morris, Illinois 60450 U. S. Nuclear Regulatory Conmission Resident Inspectors Office Dresden Station Rural Route #1 Morris, Illinois 60450 Chairman Board of Supervisors of Grundy County
- Grundy County Courthouse Morris, Illinois 60450 Re~ional Administrator Nuclear Regulatory Commission, Region III 799 Rooseve.l t Road, Bldg. #4
£len Ellyn, Illinois 60137 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Robert Neumann Office of Public Counsel State of Illinois Center 100 W. Randolph Suite 11-300 Chicago, Illinois 60601 Dresden Nuclear Power Station Unit Nos. 2 and 3