05000354/LER-2018-001, Operations with a Potential to Drain the Reactor Vessel Without Secondary Containment

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Operations with a Potential to Drain the Reactor Vessel Without Secondary Containment
ML18169A198
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 06/18/2018
From: Casulli E
Public Service Enterprise Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
LR-N18-0060 LER 2018-001-00
Download: ML18169A198 (6)


LER-2018-001, Operations with a Potential to Drain the Reactor Vessel Without Secondary Containment
Event date:
Report date:
Reporting criterion: 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)(v), Loss of Safety Function

10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown

10 CFR 50.73(a)(2)(vii), Common Cause Inoperability

10 CFR 50.73(a)(2)(i)
3542018001R00 - NRC Website

text

JUN t8 2018 LR-N18-0060 PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 0PSEG Nuclear LLC 10CFR50.73 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001

Subject:

Hope Creek Generating Station Unit 1 Renewed Facility Operating License No. NPF-57 Docket No. 50-354 Licensee Event Report 2018-001-00, Operations With A Potential To Drain The Reactor Vessel (OPDRV) Without Secondary Containment.

In accordance with 10 CFR 50. 73(a)(2)(i)(B), PSEG Nuclear LLC is submitting Licensee Event Report (LER) Number 2018-001-00, "Operations With a Potential To Drain the Reactor Vessel (OPDRV) Without Secondary Containment."

If you have any questions or require additional information, please contact Mr. Thomas MacEwen at (856) 339-1097.

There are no regulatory commitments contained in this letter.

Sincerely, Edward T. Casulli Plant Manager Hope Creek Generating Station ttm Attachment: Licensee Event Report 2018-001-00

LR-N18-0060 Page 2 of 3 cc:

Mr. Daniel Dorman, Regional Administrator-Region I, NRC Mr. Jim Kim, Project Manager - US NRC 10CFR50.73 Mr. Justin Hawkins, NRC Senior Resident Inspector-Hope Creek (X24)

Mr. Patrick Mulligan, Manager IV, NJBNE Mr. Thomas MacEwen, Hope Creek Commitment Tracking Coordinator (H02)

Mr. Lee Marabella, Corporate Commitment Tracking Coordinator (N21)

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (02-2018)

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LICENSEE EVENT REPORT (LER) i  )

(See Page 2 for required number of digits/characters for each block)

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1. Facility Name Hope Creek Generating Station
4. Title APPROVED BY OMB: NO. 3150-0104 EXPIRES: 03/31/2020

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

2. Docket Number
3. Page 05000-354 1 OF4 Ooerations With A Potential To Drain The Reactor Vessel (OPDRV) Without Secondarv Containment
5. Event Date
6. LER Number
7. Report Date
8. Other Facilities Involved Sequential Rev Facility Name Docket Number Month Day Year Year Month Day Year Number No.

05000 04 19 2018 2018

- 001
- 00 06 18 2018 Facility Name Docket Number 05000
9. Operating Mode
11. This Report is Submitted Pursuantto the Requirements of 10 CFR §: (Check all that apply) 5 0 20.2201 (b) 0 20.2203{a)(3)(i) 0 50.73(a)(2)(ii)(A) 0 50.73(a)(2)(viii)(A) 0 20.2201 (d) 0 20.2203{a)(3)(ii) 0 50.73(a)(2)(ii)(B) 0 50.73(a)(2)(viii)(B) 0 20.2203(a)(1) 0 20.2203(a)(4) 0 50.73(a)(2)(iii) 0 50.73(a)(2)(ix)(A) 0 20.2203{a)(2)(i) 0 50.36(c)(1 )(i)(A) 0 50.73(a)(2)(iv)(A) 0 50.73(a)(2)(x)
10. Power Level 0 20.2203(a)(2)(ii) 0 50.36(c)(1 )(ii)(A) 0 50.73(a)(2)(v)(A) 0 73.71 (a)(4) 0 20.2203{a)(2)(iii) 0 50.36{c)(2) 0 50.73(a)(2)(v)(B) 0 73.71 (a)(5) 0 0 20.2203(a)(2){iv) 0 50.46(a)(3)(ii) 0 50.73(a)(2)(v)(C) 0 73.77(a)(1) 0 20.2203{a)(2)(v) 0 50.73(a)(2)(i)(A) 0 50.73(a)(2)(v)(D) 0 73.77(a)(2)(ii) 0 20.2203(a)(2)(vi) 181 50. 73(a)(2)(i)(B) 0 50.73(a)(2)(vii) 0 73.77(a)(2)(iii) 0 50.73(a)(2)(i)(C) 0 Other (Specify in Abstract below or in log as an OPDRV.

SAFETY CONSEQUENCES AND IMPLICATIONS

The OPDRVs discussed in this report were performed during the HCGS refueling outage (H1 R21) and were accomplished using the interim actions provided by the NRC in EGM 11-003, Revision 3.

For these events, HCGS adhered to the NRC plain language meaning of OPDRV activities that could potentially result in draining or siphoning the RPV water level below the top of fuel. HCGS also met the requirements that specify the minimum makeup.flow rate and water inventory based on OPDRV activities with long drain down times. Further, an adequate defense-in-depth was maintained to minimize the potential for the release of fission products with secondary containment not operable by (a) monitoring RPV level to identify the onset of a loss of inventory event; (b) maintaining the capability to isolate the potential leakage paths; (c) prohibiting Mode 4 (cold shutdown) OPDRV activities; and (d) prohibiting movement of irradiated fuel with the spent fuel storage pool gates removed in Mode 5.

All other Mode 5 TS requirements for activities were followed. Since these compensatory measures were properly implemented, an adequate level of safety was provided during the OPDRV activities described in this report. Based on this information, the performance of these OPDRV activities were determined to have a low safety significance.

PREVIOUS EVENTS A review of Licensee Event Reports and the corrective action program for the past three years identified the following previous similar concurrences:

LER 2015-002-11, dated June 10, 2015, reported OPDRV activities during the 2015 refueling outage (H1 R19).

Interim actions in accordance with Revision 2 of the EGM were applied. No corrective actions were stated.

LER 2016-004-00, dated December 20, 2016, reported OPDRV activities during the 2016 refueling outage (H1 R20). Interim actions in accordance with Revision 3 of the EGM were applied. No corrective actions were stated.

CORRECTIVE ACTIONS

YEAR 2018 SEQUENTIAL NUMBER

- 001 HCGS has submitted a license amendment request to adopt a Technical Specification Task Force (TTF) traveler associated with generic resolution of this issue.

REV NO.

- 00 One of the two leaking relief valves was replaced during H1 R21. The second relief valve is scheduled for replacement during the next refueling outage.

COMMITMENTS

This LER contains no regulatory commitments NRC FORM 366r'\\ (06-2016)