05000285/LER-2012-013, Regarding Inadequate Calculation of Uncertainty Results a Technical Specification Violation

Regarding Inadequate Calculation of Uncertainty Results a Technical Specification Violation

ML12233A178
Person / Time
Site:	Fort Calhoun
Issue date:	08/17/2012
From:	Bannister D Omaha Public Power District
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
LIC-12-0121 LER 12-013-00
Download: ML12233A178 (7)

LER-2012-013, Regarding Inadequate Calculation of Uncertainty Results a Technical Specification Violation

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(8) 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
2852012013R00 - NRC Website

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~--u Omaha Public Power Oistrict 444 South 16111 Street Mall Omaha, NE 68102-2247 LlC-12-0121 August 17, 2012 u.s. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Reference: Docket No. 50-285

Subject:

Licensee Event Report 2012-013, Revision 0, for the Fort Calhoun Station Please find attached Licensee Event Report 2012-013, Revision 0, dated August 17, 2012. This report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(8).

The following commitment is being made in this letter:

Procedures PED-QP-9, "Setpoint Control," SO-G-30, "Procedure Changes and Generation," and PED-NEI-4, "Interface Requirements for Reload Analysis Process,"

will be revised to include guidance on the development of new Technical Specification limits and the associated administrative limits. These actions will be tracked in the station's CAP and will be completed prior to December 31,2012.

If you should have any questions, please contact me.

Sincerely, j}~

D. f-B~nnister Vice President and CNO DJB /epm Attachment c:

E. E. Collins, Jr., NRC Regional Administrator, Region IV L. E. Wilkins, NRC Project Manager J. C. Kirkland, NRC Senior Resident Inspector INPO Records Center Employment with Equal Opportunity

NRC FORM 366 (10-2010)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (10-2010)

LICENSEE EVENT REPORT (LER)

(See reverse for required number of digits/characters for each block)

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2013

, the NRC may not conduct or sp onsor, and a person is not required to respond to, th e

information collection.

1. FACILITY NAME Fort Calhoun Station

2. DOCKET NUMBER 05000285

3. PAGE 1 OF 4

4. TITLE Inadequate Calculation of Uncertainty Results a Technical Specification Violation

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR SEQUENTIAL NUMBER REV NO.

MONTH DAY YEAR FACILITY NAME DOCKET NUMBER 05000 12 7

2011 2012 - 013 -

0 8

17 2012 FACILITY NAME DOCKET NUMBER 05000

9. OPERATING MODE 5

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(i)(C) 50.73(a)(2)(vii) 20.2201(d) 20.2203(a)(3)(ii) 50.73(a)(2)(ii)(A) 50.73(a)(2)(viii)(A) 20.2203(a)(1) 20.2203(a)(4) 50.73(a)(2)(ii)(B) 50.73(a)(2)(viii)(B) 20.2203(a)(2)(i) 50.36(c)(1)(i)(A) 50.73(a)(2)(iii) 50.73(a)(2)(ix)(A) 20.2203(a)(2)(ii) 50.36(c)(1)(ii)(A) 50.73(a)(2)(iv)(A) 50.73(a)(2)(x) 20.2203(a)(2)(iii) 50.36(c)(2) 50.73(a)(2)(v)(A) 73.71(a)(4) 20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(B) 73.71(a)(5) 20.2203(a)(2)(v) 50.73(a)(2)(i)(A) 50.73(a)(2)(v)(C)

OTHER 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 50.73(a)(2)(v)(D)

Specify in Abstract below or in LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET

SAFETY SIGNIFICANCE

Two instances occurred where TS Limit 2.2.7 was not met as a result of this condition. The 10,000-gallon limit for SIRWT volume (credited for a mode 5 boron dilution event) is in fact not used in USAR 14.3, Boron Dilution Incident. There is no analytical basis for the 10,000-gallon limit associated with SIRWT volume. The 25,000-gallon limit associated with SIRWT volume is enveloped by a larger required limit of 283,000 gallons. Although this resulted in a reportable event, it did not represent a challenge to nuclear safety as the refueling cavity was filled as required by TS. This event did not result in the release of any radiation. Therefore, this event had no impact on the health and safety of the public.

SAFETY SYSTEM FUNCTIONAL FAILURE This event does not result in a safety system functional failure in accordance with NEI-99-02.

PREVIOUS EVENTS No previous events concerning inadequate application of uncertainty have been identifed.

FORT CALHOUN STATION NOD-QP-9.2 QUALITY PROCEDURE FORM R0 LICENSING CORRESPONDENCE REVIEW FORM LIC-12-0121 Date Issued: 8/14/12 Requested Return Date:____8/15/12______

Review/Approval Information Dave Bannister Lynn Smith Susan Baughn Woody Goodell S. Miller Brad Blome Mike Cooper C. Sterba C. Cameron J. Steinke S. Simpson Subject__ Inadequate Calculation of Uncertainty Results a Technical Specification Violation _

Please review and approve the attached draft correspondenc e (referenced above). In order to document your review for our records, please sign this form and return it to the Licensing Coordinator. If n o notification is received by the requested return date, your concurrence with no comment will be assumed.

E. Matzke 6855____

Technical Coordinator (Ext.) Licensing Coordinator (Ext.)

[ ] Approved with no comment. [ ] Approved pending resolution of comments as noted.

Comments:_______________________________________________________________________________

Reviewer's Signature Date

FORT CALHOUN STATION NOD-QP-9.2 QUALITY PROCEDURE FORM R0 LICENSING CORRESPONDENCE REVIEW FORM SUMMARY LIC-12-0121 Date Issued: 8/14/2012 Requested Return Date: 8/15/2012 Name Date Comments Received No Comments1 Comments - How Resolved2 Dave Bannister 8/14/12 X

Susan Baughn 8/15/12 Corrected S. Miller none Mike Cooper none John Goodell 8/15/12 X

C. Sterba none C. Cameron 8/15/12 Corrected or explained Lynn Smith none J. Steinke 8/15/12 Corrected S. Simpson 8/15/12 Corrected Subject: Inadequate Calculation of Uncertainty Results a Technical Specification Violation NOTE - This submittal does ____ does not __X__ include documents/files on CD-ROM.3 NL Comment Coordinator Signature E. Matzke Date 8/17/12 Responsible Dept. Manager (if required)

Date Review by Nuclear Licensing Supervisor Date 1 Attach only signed Licensing Correspondence Review Form.

2 Attach necessary documentation.

3 Ensure that the CD-ROM files are formatted properly for electronic information exchange (EIE) to the NRC. (Reference NL-17)