3F1294-12, Forwards Proprietary Calculation 32-1235116-00, Fm Assessment of CR-3,Pressurizer WP-15 Weld Flaw Until End-Of- Life & Calculation 32-1235087-00, CR-3,Pressurizer Surge Nozzle Stresses. Encls Withheld (Ref 10CFR2.790(b)(1))
| ML20080D106 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/16/1994 |
| From: | Beard P FLORIDA POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML19311B594 | List: |
| References | |
| 3F1294-12, NUDOCS 9412270200 | |
| Download: ML20080D106 (2) | |
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Florida Power CORPORATION WsNo!
December 16, 1994 3F1294-12 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
Subject:
Evaluation of Cyclic Stresses for a Flaw Indication Detected in Pressurizer Surge Line Nozzle
Reference:
A. FPC to NRC letter, 3F0994-02, dated September 2, 1994
Dear Sir:
Florida Power Corporation (FPC) is providing,in Attachment 1, a comprehensive evaluation of the cyclic stresses affecting the WP-15 surge nozzle-to-lower head weld for your review and approval.
This evaluation is submitted in accordance with Paragraph IWB-3125 of ASME Section XI, 1983 Summer Addenda.
The flaw at this weld was detected during the Refuel 9 Inservice Inspection of the pressurizer.
The attached analysis was performed to demonstrate the acceptability of the detected flaw until the end of the 40-year plant life.
It supersedes the analysis submitted previously in Reference A.
The evaluation demonstrates that the flaw detected is acceptable and meets the criteria of IWB-3612 of ASME Section XI, 1983 Summer Addenda.
The detected flaw will not reach critical length during the remainder of Crystal River Unit 3 plant life.
Augmented inspections will be performed in accordance with Subsection IWB-2420.
CHYSTAL FWVER ENEDGY COMPLEX e 15760 W. Power Une Street e Crystal River. Florida 3442& 6706 * (904) 795 4486 I
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- Page 2 Additionally, FPC is providing in Attachment 2 an analysis documenting the stresses through the thickness of the pressurizer lower head at this location of the flaw.
The stresses at the weld are due to pressure, temperature, and external loads associated with surge line stratification.
FPC is submitting an affidavit for each attachment requesting the analysis of the pressurizer surge nozzle and the analysis documenting the stresses at the flaw in the pressurizer lower head be withheld from public disclosure on the grounds that both analyses contain information proprietary to B&W Nuclear Technologies (BWNT).
The affidavits are provided in accordance with 10 CFR 2.790 (b)(1).
Sincerely,
- p. M. Beard, Jr.
Senior Vice President Nuclear Operations PMB/LVC Attachments xc:
Regional Administrator, Region II i
Senior Resident Inspector NRR Project Manager a
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