L-14-023, FENOC Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ich Accident

From kanterella
(Redirected from ML14057A548)
Jump to navigation Jump to search

FENOC Supplemental Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ich Accident
ML14057A548
Person / Time
Site: Beaver Valley
Issue date: 02/25/2014
From: Emily Larson
FirstEnergy Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
L-14-023
Download: ML14057A548 (3)


Text

FE NOC' FirstEnergy Nuclear Operating Company Eric A. Larson Site Vice President February 25, 2014 L-14-023 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Beaver Valley Power Station P.O. Box 4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 10 CFR 50.54(f)

FENOC Supplemental Response to NRG Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident On March 12, 2012, the Nuclear Regulatory Commission (NRG) issued a letter titled, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 4 of the 10 CFR 50.54(f) letter requested that each licensee perform flood protection walkdowns and report the results within 180 days of NRG endorsement of the flooding walkdown procedure (NEI 12-07). FENOC completed the flood protection walkdowns at Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant, and submitted the results in a letter dated November 27, 2012.

The November 27, 2012 letter contained open items where restricted access prevented walkdown of certain flood protection features. Walkdowns of the restricted access items for Beaver Valley Power Station, Unit No. 1, have been completed, and this letter provides the results. This submittal closes the open items in the letter dated November 27, 2012 for Beaver Valley Power Station, Unit No. 1.

Beaver Valley Power Station, Unit No. 1 L-14-023 Page 2 The attached table provides a list of the restricted access items inspected, their respective disposition, and any action planned or taken. As a result of the inspections:

There were no additional deficiencies found in the supplemental walkdown.

No temporary measures were required as a result of the completed inspections.

Available Physical Margins (APMs) were collected and documented in the walkdown record forms for each applicable item inspected in accordance with NEI 12-07.

All Restricted Items inspected were within the plant maintenance and monitoring programs.

None of the restricted access items were reclassified as Inaccessible.

This letter contains no new regulatory commitments. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager-Fleet Licensing, at 330-315-6810.

I declare under penalty of perjury that the foregoing is true and correct. Executed on February ? 5', 2014.

Sincerely,

~

/',;,/

?, L1 )v---

Eric A. Larson

Attachment:

Walkdown Report Open Items Table cc:

Director, Office of Nuclear Reactor Regulation (NRR)

NRC Region I Administrator NRC Resident Inspector NRR Project Manager Director BRP/DEP Site BRP/DEP Representative

Item Number 12-0066 12-0067 12-0068 12-0069 12-0070 12-0071 12-0072 12-0073 12-0074 Attachment Walkdown Report Open Items Table Feature Description Floor of Reactor Containment Building at 692'-11" Northeast Quadrant Wall of Reactor Containment Building at 692' -11" Southeast Quadrant Wall of Reactor Containment Building at 692'-11" Southwest Quadrant Wall of Reactor Containment Building at 692'-11" Northwest Quadrant Wall of Reactor Containment Building at 692'-11" Northeast Quadrant Wall of Reactor Containment Building at 718'-6" Southeast Quadrant Wall of Reactor Containment Building at 718'-6" Southwest Quadrant Wall of Reactor Containment Building at 718'-6" Northwest Quadrant Wall of Reactor Containment Building at 718'-6" L-14-023 Page 1 of 1 Report Deficiency Reference (yes/no)

Not No Applicable Not No Applicable Not No Applicable Not No Applicable Not No Applicable Not No Applicable Not No Applicable Not No Applicable Not No Applicable Deficiency Description Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Actions Taken Inaccessible?

or Planned (yes/no, if yes, explain below)

None No None No None No None No None No None No None No None No None No