NLS2014011, Response to Nuclear Regulatory Commission'S Request for Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns: Difference between revisions
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Enclosure 4 of Reference 1 contains specific Requested Information associated with Near-Term Task Force Recommendation 2.3 for Flooding. | Enclosure 4 of Reference 1 contains specific Requested Information associated with Near-Term Task Force Recommendation 2.3 for Flooding. | ||
Per Reference 2, the NRC endorsed Nuclear Energy Institute (NEI) 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," dated May 31, 2012. By Reference 3, Nebraska Public Power District (NPPD)submitted the final report in response to the request for information. | Per Reference 2, the NRC endorsed Nuclear Energy Institute (NEI) 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," dated May 31, 2012. By Reference 3, Nebraska Public Power District (NPPD)submitted the final report in response to the request for information. | ||
COOPER NUCLEAR STATION /d b P.O. Box 98 / Brownville, NE 68321-0098 Telephone: | COOPER NUCLEAR STATION /d b P.O. Box 98 / Brownville, NE 68321-0098 Telephone: | ||
(402) 825-3811 / Fax: (402) 825-5211 www.nppd.com NLS2014011 Page 2 of 2 One of the requirements of NEI 12-07 is to identify the available physical margin associated with each applicable flood protection feature, determine if the margin provided is small, and evaluate any small margins that have potentially significant consequences through the corrective action process. The results of this effort were to be maintained on site for future NRC audits.Following the NRC's initial review of the walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the walkdown report reviews and site audits, the NRC identified additional information necessary to allow the staff to complete its assessments. | (402) 825-3811 / Fax: (402) 825-5211 www.nppd.com NLS2014011 Page 2 of 2 One of the requirements of NEI 12-07 is to identify the available physical margin associated with each applicable flood protection feature, determine if the margin provided is small, and evaluate any small margins that have potentially significant consequences through the corrective action process. The results of this effort were to be maintained on site for future NRC audits.Following the NRC's initial review of the walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the walkdown report reviews and site audits, the NRC identified additional information necessary to allow the staff to complete its assessments. | ||
Accordingly, by Reference 4, the NRC has issued a request for additional information (RAI). The RAI questions and NPPD's responses are provided in the Attachment. | Accordingly, by Reference 4, the NRC has issued a request for additional information (RAI). The RAI questions and NPPD's responses are provided in the Attachment. |
Revision as of 12:13, 28 April 2019
ML14035A220 | |
Person / Time | |
---|---|
Site: | Cooper ![]() |
Issue date: | 01/31/2014 |
From: | Higginbotham K Nebraska Public Power District (NPPD) |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
NLS2014011 | |
Download: ML14035A220 (5) | |
Text
N Nebraska Public Power District NLS2014011 Always there when you need us January 31, 2014 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852
Subject:
Nebraska Public Power District's Response to Nuclear Regulatory Commission's Request for Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns Cooper Nuclear Station, Docket No. 50-298, DPR-46
References:
- 1. Nuclear Regulatory Commission Letter, 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, dated March 12, 2012 (Accession No. ML12053A340)
- 2. Nuclear Regulatory Commission Letter to Nuclear Energy Institute, Endorsement of Nuclear Energy Institute (NE1) 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," dated May 31, 2012 (Accession No. ML12144A142)
- 3. Nebraska Public Power District Letter to Nuclear Regulatory Commission, Flooding Walkdown Report -Nebraska Public Power District's Response to Nuclear Regulatory Commission Request for Information Pursuant to 10 CFR 50.540l Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated November 27, 2012 (NLS2012124)
- 4. Nuclear Regulatory Commission Letter, Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns, dated December 23, 2013 (Accession No. ML13325A891)
Dear Sir or Madam:
On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 requesting information pursuant to Title 10 of the Code of Federal Regulations 50.54(f).
Enclosure 4 of Reference 1 contains specific Requested Information associated with Near-Term Task Force Recommendation 2.3 for Flooding.
Per Reference 2, the NRC endorsed Nuclear Energy Institute (NEI) 12-07, "Guidelines for Performing Verification Walkdowns of Plant Flood Protection Features," dated May 31, 2012. By Reference 3, Nebraska Public Power District (NPPD)submitted the final report in response to the request for information.
COOPER NUCLEAR STATION /d b P.O. Box 98 / Brownville, NE 68321-0098 Telephone:
(402) 825-3811 / Fax: (402) 825-5211 www.nppd.com NLS2014011 Page 2 of 2 One of the requirements of NEI 12-07 is to identify the available physical margin associated with each applicable flood protection feature, determine if the margin provided is small, and evaluate any small margins that have potentially significant consequences through the corrective action process. The results of this effort were to be maintained on site for future NRC audits.Following the NRC's initial review of the walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the walkdown report reviews and site audits, the NRC identified additional information necessary to allow the staff to complete its assessments.
Accordingly, by Reference 4, the NRC has issued a request for additional information (RAI). The RAI questions and NPPD's responses are provided in the Attachment.
This letter contains no new regulatory commitments and no revision to existing regulatory commitments.
Should you have any questions regarding this submittal, please contact David Van Der Kamp, Licensing Manager, at (402) 825-2904.I declare under penalty of perjury that the foregoing is true and correct.Executed on: i/ Z///!Sincerely, Kenneth Higginboth General Manager of lant Operations
/bk
Attachment:
Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns cc: Regional Administrator, w/attachment USNRC -Region IV Director, w/attachment USNRC -Office of Nuclear Reactor Regulation Cooper Project Manager, w/attachment USNRC -NRR Project Directorate IV-I Senior Resident Inspector, w/attachment USNRC -CNS NPG Distribution, w/attachment CNS Records, w/attachment NLS201401 1 Attachment Page 1 of3 Attachment Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns Cooper Nuclear Station, Docket No. 50-298, DPR-46 On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a letter requesting information per 10 CFR 50.54(f).
The request for information letter contained specific requested actions, requested information and required responses associated with Recommendation 2.3 for flooding walkdowns.
By letter on May 31, 2012, the NRC endorsed Nuclear Energy Institute (NEI) 12-07 as providing acceptable guidelines for performing walkdowns of plant flood protection features.
Nebraska Public Power District (NPPD) submitted a final walkdown report for Cooper Nuclear Station (CNS) in response to the request for information on November 27, 2012.Following the NRC's initial review of the walkdown reports, regulatory site audits were conducted at a sampling of plants. Based on the walkdown report reviews and site audits, the NRC identified additional information necessary to allow the staff to complete its assessments.
The NRC observed that several licensees did not always determine and document available physical margin (APM) in a consistent manner that met the expected interpretation of NEI 12-07.On December 23, 2013, the NRC transmitted a request for additional information (RAI)regarding the determination and documentation of APM. Below are the NRC's RAI questions and NPPD's responses.
NRC Request: Please provide the following:
NPPD confirms that it has completed a review of the process used at CNS to evaluate APM.2. Confirmation that the APM process is now or was always consistent with the guidance in NEI 12-07 and discussed in this RAI;NPPD Response:
NPPD confirms the original walkdown effort was consistent with the guidance provided in NEI 12-07. A numerical value for a small APM was not initially established.
NLS2014011 Attachment Page 2 of 3 3. If changes are necessary, a general description of any process changes to establish this consistency; NPPD Response:
No changes were necessary as the original walkdown effort followed the guidance provided in NEI 12-07. While a numerical value for small APM was not established, judgment was used to determine if a feature had to be entered into CNS' Corrective Action Program (CAP). In response to this RAI, an engineering report, ER-14-001, was developed to determine a numerical value for small APM. This report concluded that features with one foot or more APM were determined to be not small. Features with less than one foot APM were entered into the CAP. In the case of building walls, the walkdown team judged that excess margin was available.
As such, walls were not entered into the CAP, although the walkdown sheets state that the APM is zero.4. As a result of the audits and subsequent interactions with industry during public meetings, NRC staff recognized that evaluation of APM for seals (e.g., flood doors, penetrations, flood gates, etc.) was challenging for some licensees.
Generally, licensees were expected to use either Approach A or Approach B (described below) to determine the APM for seals: a) If seal pressure ratings were known, the seal ratings were used to determine APM (similar to example 2 in Section 3.13 of NEI 12-07). A numerical value for APM was documented.
No further action was performed if the APM value was greater than the pre-established small-margin threshold value. If the APM value was small, an assessment of"significant consequences" was performed and the guidance in NEI 12-07 Section 5.8 was followed.b) If the seal pressure rating was not known, the APM for seals in a flood barrier is assumed to be greater than the pre-established small-margin threshold value if the following conditions were met: (1) the APMfor the barrier in which the seal is located is greater than the small-margin threshold value and there is evidence that the seals were designed/procured, installed, and controlled as flooding seals in accordance with the flooding licensing basis. Note that in order to determine that the seal has been controlled as a flooding seal, it was only necessary to determine that the seal configuration has been governed by the plant's design control process since installation.
In this case, the APM for the seal could have been documented as "not small".As part of the RAI response, state ifeither Approach A or Approach B was used as part of the initial walkdowns or as part of actions taken in response to this RAI. No additional actions are necessary if either Approach A or B was used.If neither Approach A or B was used to determine the APM values for seals (either as part of the walkdowns or as part of actions taken in response to this RAI), then perform the following two actions: Enter the condition into the CAP (note: it is acceptable to utilize a single CAP entry to capture this issue for multiple seals). CAP disposition of "undetermined" APM values for seals should consider the guidance provided in NEI 12-0 7, Section 5.8. The NLS2014011 Attachment Page 3 of 3 CAP disposition should confirm all seals can perform their intended safety function against floods up to the current licensing basis flood height. Disposition may occur as part of the Integrated Assessment.
If an Integrated Assessment is not performed, determine whether there are significant consequences associated with exceeding the capacity of the seals and take interim action(s), if necessary, via the CAP processes.
These actions do not need to be complete prior to the RAI response.* Report the APM as "undetermined" and provide the CAP reference in the RAI response.NPPD Response:
Approach "A" was used to determine APM for seals as part of the original walkdowns.
As such, no additional actions are necessary.