05000272/LER-2015-001, Unit 1, Regarding Fuel Movement in Progress with Fuel Handling Building Ventilation Inoperable

Unit 1, Regarding Fuel Movement in Progress with Fuel Handling Building Ventilation Inoperable

ML15075A326
Person / Time
Site:	Salem
Issue date:	03/16/2015
From:	Jamila Perry Public Service Enterprise Group
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N15-0054 LER 15-001-00
Download: ML15075A326 (5)

LER-2015-001, Unit 1, Regarding Fuel Movement in Progress with Fuel Handling Building Ventilation Inoperable

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(v), Loss of Safety Function 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
2722015001R00 - NRC Website

text

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 MAR 16 2015 LR-N15-0054 10 CFR 50.73 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

LER 272/2015-001-00 Salem Nuclear Generating Station Unit 1 Renewed Facility Operating License No. DPR-70 NRC Docket No. 50-272 Fuel Movement in Progress With Fuel Handling Building Ventilation Inoperable The Licensee Event Report, "Fuel Movement in Progress With Fuel Handling Building Ventilation Inoperable" is being submitted pursuant to 10 CFR 50.73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications...,"

and to 10 CFR 50.73 (a)(2)(v)(C), "Any event or condition that could have prevented the fulfillment of the safety function of structures or systems that are needed to control the release of radioactive material... "

The attached LER contains no commitments. Should you have any questions or comments regarding the submittal, please contact Timothy Sexsmith of Salem Regulatory Assurance at 856-339-16 11.

There are no regulatory commitments contained in this letter.

Sincerely, f.;

Site Vice President..l/a1em Attachments ( 1)

MAR 16 2015 Page 2 LR-N15-0054 cc 10 CFR 50.73 Mr. D. Dorman, Administrator - Region 1, NRC Ms. C. Sanders, Licensing Project Manager - Salem, NRC Mr. P. Finney, USNRC Senior Resident Inspector, Salem (X24)

Mr. P. Mulligan, Manager IV, NJBNE Mr. R. Braun, President and Chief Nuclear Officer - Nuclear Mr. T. Cachaza, Salem Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator Mr. D. Lafleur, Salem Regulatory Assurance

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01131/2017 (01-2014)

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.

LICENSEE EVENT REPORT (LER)

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections

-.i.,...,;i.

Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by (See Page 2 for required number of internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and digits/characters for each block)

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 NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

r* PAGE Salem Generating Station - Unit 1 0500027 2 1 OF3

4. TITLE Fuel Movement in Progress With Fuel Handling Building Ventilation Inoperable

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR I SEQUENTIAL I REV MONTH FACILITY NAME DOCKET NUMBER DAY YEAR NUMBER NO.

05000 FACILITY NAME DOCKET NUMBER 01 16 2015 2015

- 001

- 000 03 16 15 05000

9. OPERATING MODE

11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENlS OF 10 CFR §:(Check all that apply) 1 D 20.2201(b)

D 20.2203(a)(3)(i)

D 50.73(a)(2)(i)(C)

D 50.73(a)(2)(vii)

D 20.2201(d)

D 20.2203(a)(3)(ii)

D 50.73(a)(2)(ii)(A)

D 50.73(a)(2)(viii)(A)

10. POWER LEVEL D 20.2203(a)(1)

D 20.2203(a)(4)

D 50.73(a)(2)(ii)(B)

D 50.73(a)(2)(viii)(B)

D 20.2203(a)(2)(i)

D 50.36(c)(1 )(i)(A)

D 50.73(a)(2)(iii)

D 50.73(a)(2)(ix)(A) 100%

D 20.2203(a)(2)(ii)

D 50.36(c)(1)(ii)(A)

D 50.73(a)(2)(iv)(A)

D 50.73(a)(2)(x)

D 20.2203(a)(2)(iii)

D 50.36(c)(2)

D 50.73(a)(2)(v)(A)

D 73.71(a)(4)

D 20.2203(a)(2)(iv)

D 50.46(a)(3)(ii)

D 50.73(a)(2)(v)(B)

D 73.71(a)(5)

D 20.2203(a)(2)(v)

D 50.73(a)(2)(i)(A) 1 50.73(a)(2)(v)(C) 0 OTHER D 20.2203(a)(2)(vi) 1 50.73(a)(2)(i)(B)

D 50.73(a)(2)(v)(D)

Specify in Abstract below or in exhaust fans and one supply fan shall be operable and capable of maintaining slightly negative pressure in the Fuel Handling Building.

This event is reported in accordance with 10 CFR 50. 73 (a)(2)(i)(B), "Any operation or condition which was prohibited by the plant's Technical Specifications... "

The inability of the FHB Ventilation System {VG/AHU} to maintain the required negative D/P constitutes a Safety System Functional Failure, and is reported in accordance with 10 CFR 50.73 (a)(2)(v)(C), "Any event or condition that could have prevented the fulfilment of the safety function of structures or systems that are needed to control the release of radioactive material..."

CAUSE OF EVENT

A causal evaluation is in progress. The results of this evaluation will be published in a supplement to this Licensee Event Report (LER).

SAFETY CONSEQUENCES AND IMPLICATIONS

The safety significance of this event is minimal. The event did not result in any offsite release of radioactivity or increase of offsite dose rates. There were no personnel injuries or damage to any safety-related equipment. The amount of radioactivity released from a postulated fuel handling accident assuming a full release of building volume to the environment was previously evaluated and determined that the release to the Exclusion Area Boundary (EAB) and the Low Population Zone (LPZ) were well below regulatory limits.

SAFETY SYSTEM FUNCTIONAL FAILURE This event constitutes a Safety System Functional Failure (SSFF) as defined in Nuclear Energy Institute (NEI) 99-02, Regulatory Assessment Performance Indicator Guideline.

PREVIOUS OCCURRENCES

A review of Salem Unit 1 and 2 Licensee Event Reports for the previous three years identified no other

CORRECTIVE ACTIONS

A causal evaluation is in progress. Corrective actions with respect to this event will be published in a supplement to this LER.

COMMITMENTS

This LER contains no regulatory commitments.