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LER-2018-002, Safety Relief Valve L (SRV) As-Found Setpoint Failure
Event date:
Report date:
Reporting criterion:	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)(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)
	3542018002R01 - NRC Website
	v • d • e

Safety Relief Valve L (SRV) As-Found Setpoint Failure
	ML18276A022
Person / Time
Site:	Hope Creek
Issue date:	10/03/2018
From:	Casulli E; Public Service Enterprise Group
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	LR-N18-0102 LER 2018-002-01
	Download: ML18276A022 (7)
	v • d • e

PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 LR-N18-0102 OCT 0 3 2918 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Hope Creek Generating Station Renewed Facility Operating License No. NPF-57 NRC Docket No. 50-354 0PSEG NuclearLLC 10 CFR 50.73

Subject:

Supplemental Licensee Event Report 2018-002-01, Safety Relief Valve (SRV) As-Found Setpoint Failure

Reference:

PSEG Letter LR-N18-0065, dated June 18, 2018 Licensee Event Report 2018-002-00 In accordance with 10 CFR 50.73(a)(2)(i)(B), PSEG Nuclear LLC (PSEG) is submitting Supplemental Licensee Event Report (LER) Number 2018-002-01, "Safety Relief Valve (SRV)

As-Found Setpoint Failure." Subsequent to the initial LER, PSEG determined that an additional failure cause existed. This supplemental LER contains information related to the additional cause of failure.

There are no regulatory commitments contained in this submittal. If you have any questions or require additional information, please contact Mr. Thomas MacEwen at 856-339-1097.

Sincerely, Edward T. Casulli Plant Manager Hope Creek Generating Station ttm - Licensee Event Report 2018-002-01

Page 2 LR-N18-01 02 cc:

Administrator, Region I, NRC Project Manager, NRC NRC Senior Resident Inspector, Hope Creek Mr. P. Mulligan, Chief, NJBNE Corporate Commitment Tracking Coordinator Hope Creek Commitment Tracking Coordinator 10 CFR 50.73

LR-N18-01 02 Licensee Event Report 2018-002-01 Safety Relief Valve (SRV) As-Found Setpoint Failure

NRCFORM366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150.0104 EXPIRES: 03/31/2020 (02-2018)

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

1. Facility Name

~- Docket Number

Page Hope Creek Generating Station 05000354 1 OF4

4. Title Safetv Relief Valve l:SRV) As-Found Setnoint Failure

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 20 2018 2018

- 002

- 01 10 03 2018 Facility Name Docket Number 05000

9. Operating Mode

11. This Report is SUbmitted Pl..nuant1D the Requiremenls of 10 CFR §: (Check all that apply) 5-Refuel 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 NRC Form 366A

12. Licensee Contact for this LER Ucensee Contact

~~lephone Number (Include Area Code)

!Tanya Timberman, Senior Nuclear Engineer

~56-339-1426

13. Complete One Unefcr each Component Failure DescriJed in this Report

Cause

System Component Manufacturer Reportable To ICES

Cause

System Component Manufacturer Reportable To ICES B

SB RV T020 y

14. Supplemental Report Expected Month Day Year 0 Yes (If yes, complete 15. Expected Submission Date) ~ No

15. Expected Submission Date

~tract (Limit to 1400 spaces, i.e., approximately 14 single-spaced typewritten lines)

On April 20, 2018, Hope Creek Generating Station (HCGS) received results that the 'as-found' set-point tests for safety relief valve (SRV) pilot stage assemblies had exceeded the lift setting tolerance prescribed in Technical Specification (TS) 3.4.2.1. The TS requires the SRV lift settings to be within +/- 3% of the nominal set-point value.

During the twenty-first refueling outage (H1 R21 ), all fourteen SRV pilot stage assemblies were removed for testing at an offsite facility. Between April 20 and May 11, 2018, HCGS received the test results for all fourteen of the SRV pilot valve assemblies. A total of eight of the fourteen SRV pilot stage assemblies experienced set-point drift outside of the TS 3.4.2.1 specified values. All of the valves failing to meet the limits were Target Rock Model 7567F two-stage SRVs.

This is a condition reportable under 10 CFR 50.73(a)(2)(i)(B) as an Operation or Condition Prohibited by Technical Specifications.

The cause of the set-point drift for the eight SRV pilot stage assemblies is attributed to corrosion bonding between the pilot disc and seating surfaces, which is consistent with industry experience. This conclusion is based on previous cause evaluations and the repetitive nature of this condition at HCGS and within the BWR industry.

NRC FORM 366 (02-2018)

PLANT AND SYSTEM IDENTIFICATION

General Electric-Boiling Water Reactor (BWR/4)

Main Steam - EllS Identifier {SB}*

Safety Relief Valves-EllS Identifier {SB/RV}*

Energy Industry Identification System {EllS} codes and component function identifier codes appear as {SS/CCC}

IDENTIFICATION OF OCCURRENCE Event Date: April 20, 2018 Discovery Date: April 20, 2018 CONDITIONS PRIOR TO OCCURRENCE When the reports of the 'as-found' results were received, Hope Creek was in Operational Condition (OPCON) 5, Refuel, at 0 percent rated thermal power. No other structures, systems or components that could have contributed to the event were inoperable at the time of the event.

DESCRIPTION OF OCCURRENCE During the twenty-first refueling outage (H1 R21) at Hope Creek Generating Station (HCGS), all fourteen Main Steam safety relief valves (SRV) pilot stage assemblies {SB/RV} were removed and tested at NWS Technologies. The SRVs are Target Rock Model 7567F two-stage SRVs. During the period from April 20 through May 11, 2018, HCGS received the results of the 'as-found' set pressure testing required by Technical Specification (TS) Surveillance Requirement (SR) 4.4.2.2. A total of eight of the fourteen SRV pilot stage assemblies had set-point drift outside of the required TS 3.4.2.1 tolerance values of +/-3% of nominal value.

The 'as-found' test results for the eight SRVs not meeting the TS requirements are as follows:

Valve ID As Found TS Lift Setting Acceptable Band

% Difference (psig)

(psi g)

(psig)

Actual F013B 1210 1130 1096.1-1163.9 7.10%

F013D 1191 1130 1 096.1 - 1163.9 5.40%

F013F 1146 1108 1074.8-1141.2 3.40%

F013G 1197 1120 1 086.4 - 1153.6 6.90%

F013H 1200 1108 1074.8-1141.2 8.30%

F013L 1155 1120 1086.4-1153.6 3.10%

F013M 1161 1108 1074.8-1141.2 4.80%

F013P 1199 1120 1086.4-1153.6 7.10%

Technical Specification (TS) 3.4.2.1 requires that the safety function of at least 13 of 14 SRVs be operable with a specified code safety valve function lift setting, within a tolerance of +/- 3%. Action (a) of TS 3.4.2.1 specifies "With the safety valve function of two or more of the above listed fourteen safety/relief valves inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ." Therefore, this is a condition reportable under 10 CFR 50.73(a)(2)(i)(B) as an Operation or Condition Prohibited by TS.

NRC FORM 3668 (02-2018)

Page 2 of 4 (04-2017)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 3/31/2020 r-*'

~~. \\

\\~j

-~.. --J LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET (See NUREG-1 022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/readinq-rm/doc-collections/nuregs/staff/sr1 022/r3L)

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

1. FACIUTYNAME

2. DOCKET NUMBER

3. L.ER NUMBER YEAR Hope Creek Generating Station 05000-354 2018

COMMITMENTS

There are no regulatory commitments contained in this LER. SEQUENTIAL NUMBER

- 002 REV NO.

- 01 Page 4 of 4

05000354/LER-2018-002-01, Safety Relief Valve L (SRV) As-Found Setpoint Failure

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05000354/LER-2018-002-01, Safety Relief Valve L (SRV) As-Found Setpoint Failure

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