ML20248E867: Difference between revisions

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Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 NRC Bulletin 88-02 l
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 NRC Bulletin 88-02 l
Gentlemen:
Gentlemen:
By letter dated March 28, 1988, Duquesne Light Company (DLC) replied to NRC Bulletin 88-02 " Rapidly Propagating Fatigue Cracks in Steam Generator Tubes" and stated there was no evidence of denting at                                                                                                                                  l the upper support plate for Beaver Valley Unit 2 (BV-2). The NRC reviewed our response and issued a safety evaluation by letter dated                                                                                                                                  l February 10, 1989 (TAC 67297)~. Although not required by the Bulletin at this time, DLC has evaluated the susceptibility of the BV-2 steam generator              tubes to rapidly propagating fatigue cracks assuming.that the tubes at the upper support plate are in a " dented" or " tube
By {{letter dated|date=March 28, 1988|text=letter dated March 28, 1988}}, Duquesne Light Company (DLC) replied to NRC Bulletin 88-02 " Rapidly Propagating Fatigue Cracks in Steam Generator Tubes" and stated there was no evidence of denting at                                                                                                                                  l the upper support plate for Beaver Valley Unit 2 (BV-2). The NRC reviewed our response and issued a safety evaluation by letter dated                                                                                                                                  l February 10, 1989 (TAC 67297)~. Although not required by the Bulletin at this time, DLC has evaluated the susceptibility of the BV-2 steam generator              tubes to rapidly propagating fatigue cracks assuming.that the tubes at the upper support plate are in a " dented" or " tube
                   ' locked" condition.                            Based on this evaluation, two (2) tubes (R11C4 and R9C33) in the BV-2 "C" steam generator will be preventative 1.y plugged              with leak limiting plugs during our current refuel _ag outage.              These actions would be required by Item C.2 of the Bulletin if denting is found in the future.
                   ' locked" condition.                            Based on this evaluation, two (2) tubes (R11C4 and R9C33) in the BV-2 "C" steam generator will be preventative 1.y plugged              with leak limiting plugs during our current refuel _ag outage.              These actions would be required by Item C.2 of the Bulletin if denting is found in the future.
We are submitting                          this                                      evaluation for NRC review and approval.
We are submitting                          this                                      evaluation for NRC review and approval.

Revision as of 13:59, 8 March 2021

Forwards Proprietary WCAP-12141 & Nonproprietary WCAP-12142, Beaver Valley Unit 2 Evaluation for Tube Vibration Induced Fatigue, for Review & Approval & Application for Withholding Proprietary Rept (Ref 10CFR2.790)
ML20248E867
Person / Time
Site: Beaver Valley
Issue date: 04/06/1989
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19297H495 List:
References
IEB-88-002, IEB-88-2, TAC-67297, NUDOCS 8904120388
Download: ML20248E867 (2)


Text

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. t Be ver Valley Power Staten Shippingport. PA 15077@04 y NWear Grnup 14W 643 6256 April 6, 1989 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 NRC Bulletin 88-02 l

Gentlemen:

By letter dated March 28, 1988, Duquesne Light Company (DLC) replied to NRC Bulletin 88-02 " Rapidly Propagating Fatigue Cracks in Steam Generator Tubes" and stated there was no evidence of denting at l the upper support plate for Beaver Valley Unit 2 (BV-2). The NRC reviewed our response and issued a safety evaluation by letter dated l February 10, 1989 (TAC 67297)~. Although not required by the Bulletin at this time, DLC has evaluated the susceptibility of the BV-2 steam generator tubes to rapidly propagating fatigue cracks assuming.that the tubes at the upper support plate are in a " dented" or " tube

' locked" condition. Based on this evaluation, two (2) tubes (R11C4 and R9C33) in the BV-2 "C" steam generator will be preventative 1.y plugged with leak limiting plugs during our current refuel _ag outage. These actions would be required by Item C.2 of the Bulletin if denting is found in the future.

We are submitting this evaluation for NRC review and approval.

Enclosed are:

1. Four (4) copies of WCAP-12141 entitled, " Beaver Valley Unit 2 Evaluation for Tube Vibration Induced Fatigue (Proprietary).
2. Four (4) copies of WCAP-12142 entitled, Beaver Valley Unit 2 Evaluation for Tube Vibration Induced Fatigue (Non-Proprietary).

Also enclosed is a Westinghouse authorization letter, CAW-89-038, Proprietary Information Notice, and accompanying Affidavit.

8904120388 890406 PDR ADOCK 05000412 Q PDC Or N lW 0: APM i iM q04 Ne 9?' i iet QDAf ,

.- . Beaver Valley Power Station, Unit No. 2

,. Docket No. 50-412, License No. NPF-73 Page 2 l

As item 1 contains information proprietary to Westinghouse Electric Corporation, it is supported by an affidavit signed by Westinghouse, the owner of the information. The affidavit sets forth the bases on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of Section 2.790 of the Commission's regulations.

l Accordingly, it is respectfully requested that the information which is proprietary- to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section 2.790 of the Commission's regulations.

Correspondence with respect to the proprietary aspects of the Application for Withholding or the supporting Westinghouse Affidavit should reference CAW-89-038 and should be addressed to R. A. Wiesemann, Manager of Regulatory & Legislative Affairs, Westinghouse Electric Corporation, P. O. Box 355, Pittsburgh, PA 15230-0355.

If there are any questions concerning this matter, please contact  ;

my office. l Very truly yours, OC 3 aqs J. D. Sieber Vice President Nuclear Group Enclosures cc: w/o enclosures Mr. J. Beall, Sr. Resident Inspector Mr. W. T. Russell, NRC Region I Administrator Mr. P. Tam, Sr. Project Manager Director, Safety Evaluation & Control (VEPCO) l i

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