05000400/LER-2016-003, Regarding Containment High-Range Radiation Monitors Declared Inoperable Due to Potential for Temperature Induced Current

Regarding Containment High-Range Radiation Monitors Declared Inoperable Due to Potential for Temperature Induced Current

ML16279A507
Person / Time
Site:	Harris
Issue date:	10/05/2016
From:	Waldrep B Duke Energy Progress
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
HNP-16-082 LER 16-003-00
Download: ML16279A507 (4)

LER-2016-003, Regarding Containment High-Range Radiation Monitors Declared Inoperable Due to Potential for Temperature Induced Current

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(iv)(A), System Actuation 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)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(ix)(A) 10 CFR 50.73(a)(2)(x)
4002016003R00 - NRC Website

text

Benjamin C. Waldrep Vice President Harris Nuclear Plant 5413 Shearon Harris Road New Hill, NC 27562-9300 919.362.2502 10 CFR 50.73 October 5, 2016 Serial: HNP-16-082 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400/Renewed License No. NPF-63 Subject: Licensee Event Report 2016-003-00 Ladies and Gentlemen:

Duke Energy Progress, LLC, submits the enclosed Licensee Event Report, 2016-003-00, in accordance with 10 CFR 50.73 for Shearon Harris Nuclear Power Plant, Unit 1. This report details a condition affecting the sites containment high-range radiation monitors (CHRRMs).

The CHRRMs were declared inoperable on September 21, 2016, due to the potential impact of temperature induced current on the accuracy of the CHRRMs, as documented per Information Notice 97-45, Supplement 1.

This document contains no regulatory commitments. Please refer any questions regarding this submittal to John Caves, Manager of Regulatory Affairs, at (919) 362-2406.

Sincerely, Benjamin C. Waldrep Enclosure: Licensee Event Report 2016-003-00 cc:

Mr. M. J. Riches, NRC Sr. Resident Inspector, HNP Ms. M. Barillas, NRC Project Manager, HNP Regional Administrator, Region II

LICENSEE EVENT REPORT (LER)

NRC FORM 366 (06-2016)

U.S. NUCLEAR REGULATORY COMMISSION Estimated burden per response to comply with this mandatory collection request: 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />.

Reported lessons learned are incorporated into the licensing process and fed back to industry.

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, DC 20503. If a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (See Page 2 for required number of digits/characters for each block) 1 OF

3. PAGE 05000

4. TITLE

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

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

FACILITY NAME 05000 DOCKET NUMBER FACILITY NAME 05000 DOCKET NUMBER

9. OPERATING MODE

10. POWER LEVEL

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply)

12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT TELEPHONE NUMBER (Include Area Code)CAUSE SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

CAUSE

SYSTEM COMPONENT MANU-FACTURER REPORTABLE TO EPIX

14. SUPPLEMENTAL REPORT EXPECTED YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

NO

15. EXPECTED SUBMISSION DATE YEAR DAY MONTH ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

NRC FORM 366 (06-2016)

YEAR YEAR DAY MONTH 20.2201(b) 20.2203(a)(3)(i) 50.73(a)(2)(vii) 20.2203(a)(2)(ii) 20.2203(a)(2)(i) 20.2203(a)(1) 20.2201(d) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(2)(vi) 20.2203(a)(3)(ii) 20.2203(a)(4) 50.36(c)(1)(i)(A) 50.36(c)(1)(ii)(A) 50.36(c)(2) 50.46(a)(3)(ii) 50.73(a)(2)(i)(A) 50.73(a)(2)(i)(B) 50.73(a)(2)(ii)(A) 50.73(a)(2)(ii)(B) 50.73(a)(2)(iii) 50.73(a)(2)(iv)(A) 50.73(a)(2)(v)(A) 50.73(a)(2)(v)(B) 50.73(a)(2)(v)(C) 50.73(a)(2)(v)(D) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(ix)(A) 50.73(a)(2)(x) 73.71(a)(4) 73.71(a)(5)

OTHER Specify in Abstract below or in Page of 05000-

3. LER NUMBER YEAR SEQUENTIAL NUMBER REV NO.

D. Safety Analysis

The CHRRMs provide a monitoring function only, and do not initiate any specific control actions or provide an actuation signal for other components. These monitors do not perform a specific function in mitigating the consequences of an accident, and are not modeled per Probablistic Risk Assessment. Alternate means of monitoring conditions in containment are available to the operators. This condition does not render the CHRRMs inoperable for all conditions, but only for a period of about 15 minutes immediately following a loss-of-coolant accident or a main steamline break.

Periodic testing of the CHRRMs has not revealed any other conditions that would challenge the monitors accuracy or reliability. Therefore, this condition represents a degradation of low safety significance.

At no point in the potentially impacted period were the CHRRMs required to provide information during a design basis accident. Thus, there is no consequence to the health and safety of site personnel or to the public.

E. Corrective Actions

Completed Actions:

Information regarding this condition has been added to the Operations' Turnover sheet to ensure adequate awareness by operations.

Planned Actions:

Either (1) perform site specific testing on the currently installed cables to implement a correction factor for use with the radiation monitoring system, (2) replace the affected cables with cables not impacted by TIC, or (3) gain NRC approval of a License Amendment Request to restore compliance.

F. Additional Information

There have been no previous Licensee Event Reports due to the impact of TIC on the CHRRMs.

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