ML20134C541
| ML20134C541 | |
| Person / Time | |
|---|---|
| Issue date: | 03/21/1996 |
| From: | Crutchfield D NRC (Affiliation Not Assigned) |
| To: | Croneberger D BABCOCK & WILCOX CO. |
| Shared Package | |
| ML20134C544 | List: |
| References | |
| PROJECT-683 NUDOCS 9702030160 | |
| Download: ML20134C541 (5) | |
Text
t p5"4 UNITED STATES j
j NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20665 4 001.
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$9.....,o March 21, 1996 Mr. Don Croneberger Program Director Generic License Renewal Program B&W Nuclear Service Company P.O. Box 10935 Lynchburg, Virginia 24506-0935
SUBJECT:
ACCEPTANCE FOR REFERENCING OF TOPICAL REPORT BAW-2243,
" DEMONSTRATION OF THE MANAGEMENT OF AGING EFFECTS FOR THE REACT COOLANT SYSTEM PIPING"
Dear Mr. Croneberger:
The U.S. Nuclear Regulatory Commission staff has reviewed your, " Demonstration of the Management of Aging Effects for the Reactor Coolant System Piping,"
8AW-2243, applicable to the Babcock and Wilcox Owners Group (B&WOG) Generic License Renewal Program (GLRP) member units, and finds the report acceptable for referencing in license renewal applications to the extent specified and under the limitations delineated in the report and the associated NRC safety evaluation, which is enclosed.
Specifically, a B&WOG GLRP member plant that references the report in a license renewal application, commits to the accepted aging management programs therein, and completes the action items described in Section 4.1 of the safety evaluation, will have provided sufficient information for the staff to find that the effects of aging will be adequately managed so that the intended functions of the reactor coolant system piping components within the scope of the report will be maintained consistent with the current licensing basis for the period of extended operation.
The evaluation defines the basis for the NRC staff's acceptance of the report.
We do not intend to repeat our review of the matters described in the report and found acceptable when the report appears as a reference in license renewal applications, except to assure that the material presented is applicable to
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the specified plant involved.
In accordance with procedures established in NUREG-0390, " Topical Report h)
Review Status," it is requested that the Babcock and Wilcox Owners Group J
publish accepted versions of this report within 3 months of receipt of this
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ip MIU 20 FRE CENTBs CFo 9702030160 960321 (A 9 O l PDR PROJ 683 PDR
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Mr. Don Croneberger March 21, 1996 letter.
The accepted versions shall incorporate this letter and the enclosed safety evaluation between the title page and the abstract.
The accepted versions shall include an -A (dasignating accepted) following the report i
identification symbol.
Sincerely, l
00gtflai Signed Oy Dennis M. Crutchfield, Director j
Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 683 4
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Enclosure:
Safety Evaluation cc:
See next page 683 bN ll d
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Project No. 683 Babcock & Wilcox Owners Group Generic License Renewal Program cc:
Mr. Robert B. Borsum Regional Administrator, Region IV Framatome Technologies U.S. Nuclear Regulatory Commission 1700 Rockville Pike 611 Ryan Plaza Drive, Suite 1000 Suite 525 Arlington, Texas 76011 Rockville, Maryland 20852 Mr. James J. Fisicaro Michael Laggart Director, Licensing Manager, Corporate Licensing Entergy Operations, Inc.
GPU Nuclear Corporation Route 3, Box 137G Bne Upper Pond Road Russelville, Arkansas 72801 Parsippany, New Jersey 07054 Earnest L. Blake, Jr., Esq.
Chairman Shaw, Pittman, Potts Board of County Commissioners and Trowbridge of Dauphin County 2300 N. Street, NW Daughin County Courthouse Washington, D.C.
20037 Harrisburg, Pennsylvania 17120 Regional Administrator, Region 1 Mr. J. W. Hampton U.S. Nuclear Regulatory Commission Nuclear Generation Vice President 475 Allendale Road Duke Power Company King of Prussia, Pennsylvania 19406 Oconee Nuclear Station MC: ON0 IVP B. Gutherman, Manager P.O. Box 1439 Licensing Seneca, South Carolina 29679 Florida Power Corporation (SA2A)
Crystal River Energy Complex Mr. John R. McGaha 15760 W. Powerline Street Vice President, Operations Support Crystal River, FL 34428-6708 Entergy Operations, Inc.
P.O. Box 31995 William Dornsife, Acting Director Jacksonville, Mississippi 39286 Bureau of Radiation Protection 1
Pennsylvania Department of 4
Regional Administrator, Region 11 Environmental Resources U.S. Nuclear Regulatory Commission P.O. Box 2063 101 Marietta St., N.W. Suite 2900 Harrisburg, Pennsylvania 17120 Atlanta, Georgia 30323 Chairman Mr. R. L. Gill Board of Supervisors GLRP Licensing Coordinator of Londonderry Township c/o Duke Power Company R.D. #1 Geyers Church Road EC-12R Middletown, Pennsylvania 17057 P.O. Box 1006 Charlotte, North Carolina 28201-Mr. J. E. Burchfield 1006 Compliance Duke Power Company Oconee Nuclear Site P.O. Box 1439 Seneca, South Carolina 29679
t Mr. Don Croneberger March 21, 1996 letter.
The accepted versions shall incorporate this letter and the enclosed safety evaluation between the title page and the abstract.
The accepted versions shall include an -A (designating accepted) following the report identification symbol.
Sincerely,
' h.
Dennis M. Crutc fiel, Director Division of Reactor Program Management Office of Nuclear Reactor Regulation Project No. 683
Enclosure:
Safety Evaluation cc:
See next page
Mr. Don Croneberger Program Director
)
/
Generic License Renewal Program B&W Nuclear Service Company P.O. Box 10935 Lynchburg, Virginia 24506-0935
SUBJECT:
ACCEPTANCE FOR REFERENCING OF TOPICAL REPORT BAW 243, l
"DEM0hSTRATION OF THE MANAGEMENT OF AGING EFFECTS FOR THE REACTOR COOLANT SYSTEM PIPING"
/
Dear Mr. Croneberger:
,/
3 The U.S. Nuclear Regulatory Commission staff has, reviewed your, " Demonstration of the Management of Aging Effects for the Reactor Coolant System Piping,"
BAW-2243, applicable to the Babcock and Wilcox/0wners Group (B&WOG) Generic License Renewal Program (GLRP) member units,/and finds the report acceptable for referencing in license renewal applications to the extent specified and under the limitations delineated in the r,eport and the associated NRC safety evaluation, which is enclosed.
Specific 411y, a B&WOG GLRP member plant that references the report in a license renesal application and commits to the accepted aging management programs the' rein, will have provided an adequate demonstration that the effects of aging will be adequately managed so that the intended functions of the reactor, coolant system piping components within the scope of the repnrt will be maint4ined consistent with the current licensing basis for the period of extended' operation.
The evaluation defines the basis for the NRC staff's acceptance /of the report.
Wedonotintendtorepeatodrreviewofthemattersdescribedinthereport and found acceptable when the report appears as a reference in license renewal applications, except to adsure that the material presented is applicable to the specified plant inv9 ved.
1 In accordance with pro /
cedures established in NUREG-0390, " Topical Report Review Status," it is' requested that the Babcock and Wilcox Owners Group publish accepted ve/sions of this report within 3 months of receipt of this letter.
The accepted versions shall incorporate this letter and the enclosed safety evaluation'between the title page and the abstract.
The accepted versions shall include an -A (designating accepted) following the report identification / symbol.
Sincerely, 7
Dennis M. Crutchfield, Director
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Division of Reactor Program Management
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Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation Project No. 683 DISTRIBUTION:
See next page (c:
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