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LER-2019-003, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump
Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded; 10 CFR 50.73(a)(2); 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition; 10 CFR 50.73(a)(2)(viii)(B); 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), 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)(B), Prohibited by Technical Specifications
	2932019003R00 - NRC Website
	v • d • e

Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump
	ML19161A283
Person / Time
Site:	Pilgrim
Issue date:	06/10/2019
From:	Miner P; Entergy Nuclear Operations
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	2.19.037 LER 2019-003-00
	Download: ML19161A283 (6)
	v • d • e

-'"* Entergy_

2.19.037 June 10, 2019 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 Peter J. Miner Manager, Regulatory Assurance 10 CFR 50.73 SUBJECT: Licensee Event Report 2019-003-00, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump Pilgrim Nuclear Power Station NRC Docket No. 50-293 Renewed Facility Operating License No. DPR-35 The enclosed Licensee Event Report 2019-003-00, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump, is submitted in accordance with Title 1 O Code of Federal Regulations 50.73.

If you have any questions regarding this information, please contact me at 508-830-7127.

This letter contains no new regulatory commitments.

Sincerely, IJJ~

Peter J. Miner PJM/rjm

Enclosure:

Licensee Event Report 2019-003-00 Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump

Letter No. 2.19.037 Page 2 of 2 cc:

NRC Region I, Regional Administrator NRC NRA Project Manager - Pilgrim NRC Senior Resident Inspector - Pilgrim

Enclosure 2.19.037 Licensee Event Report 2019-003-00, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump

BNRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 03/31/2020 (04-2017) htt12://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/Q{)

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

.PAGE Pilgrim Nuclear Power Station 05000-293 1 OF 3

4. TITLE Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump

5. EVENT DATE

6. LER NUMBER

7. REPORT DATE

8. OTHER FACILITIES INVOLVED SEQUENTIAL FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAR REV MONTH DAY YEAR N/A NUMBER NO.

N/A 04 2019 2019

- 003

- 00 06 10 2019 FACILITY NAME DOCKET NUMBER 13 N/A N/A

9. OPERATING MODE

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

N D 20.2201(b)

D 20.2203(a)(3l(il D 50.73(a)(2)(ii)(A)

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

D 20.2201 (dl D 20.2203(a)(3)(iil D 50.73(a)(2)(ii)(B)

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

D 20.2203(a)(1 l D 20.2203(a)(4l D so.73(a)(2)(iiil D 50.73(a)(2)(ix)(A)

D 20.2203(a)(2)(il D 50.36(c)(1 )(i)(A)

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

D 50.73(a)(2)(x)

10. POWER LEVEL D 20.2203(a)(2)(iil D 50.36(c)(1 )(ii)(A)

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

D 73.71 (a)(4)

D 20.2203(a)(2)(iii)

D so.36(c)(2l D 50.73(a)(2)(v){B)

D 73.71 (a)(S) 100 D 20.2203(a)(2)(iv)

D so.46(a)(3){iil D 50.73(a)(2)(v){C)

D 73.77(a)(1J D 20.2203(a){2)(v)

D 50.73(a)(2)(i)(A)

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

D 73.77(a)(2)(il D 20.2203(a)(2)(vi) 181 S0.73(a)(2){i)(B)

D 50.73(a)(2)(vii)

D 73.77(a)(2)(iil D so.73(a)(2)(i)(C) 00THER Specity in Abstract below or,n NRC Form 366A

12. LICENSEE CONTACT FOR THIS LER LICENSEE CONTACT r,LEPHONE NUMBER (Include Area Code)

!Mr. Peter J. Miner - ReQulatory Assurance ManaQer

~08-830* 7127 CAUSE SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TOEPIX FACTURER TO EPIX A

JC RI GOBO y

14. SUPPLEMENTAL REPORT EXPECTED

15. EXPECTED MONTH DAY YEAR D YES (If yes, complete 15. EXPECTED SUBMISSION DATE)

~ NO SUBMISSION DATE

!ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On April 13, 2019, the operating crew placed the key lock switch for Main Steam Process Radiation Monitor (PRM) 1705-20 to the INOP position and restored the Mechanical Vacuum (MV) pump to ready state. Subsequent research into the INOP position for the PRM 1705-20 switch revealed that this action does not introduce a channel trip signal. Not placing the PRM in a trip condition with the MV pump restored to ready state, is a violation of Technical Specification Action Statement 3.8.2.A.2 to place the channel or associated trip system in trip within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

There were no actual consequences to safety of the general public, nuclear safety, industrial safety, or radiological safety for this event.

This report is submitted in accordance with Title 10 Code of Federal Regulations 50.73(a)(2)(i)(B).

BACKGROUND The Mechanical Vacuum (MV) pump is provided to remove gases from the main condenser during plant startup and shutdown when steam is not available for the steam jet air ejectors.

!The MV pump isolation instrumentation initiates a trip of the MV pump and isolation of the associated isolation

~alve following events in which main steam line radiation exceeds predetermined values. Tripping and isolating

~he MV pump limits the offsite doses in the event of a control rod drop accident.

The MV pump isolation instrumentation includes sensors, relays, and switches that are necessary to cause initiation of a pump isolation. The channels include electronic equipment that compares measured input signals With pre-established setpoints. When the setpoint is exceeded, the channel output relay actuates, which then outputs an isolation signal to the MV pump isolation logic.

EVENT DESCRIPTION

On April 13, 2019, the operating crew placed the key lock switch for Main Steam (MS) Process Radiation Monitor (PAM) 1705-20 to the !NOP position and restored the MV pump to ready state. Subsequent research into the INOP position for the PAM 1705-20 switch revealed that this action does not introduce a channel trip

~ignal. Not placing the PAM in a trip condition with the MV pump restored to ready state, is a violation of rTechnical Specification (TS) Action Statement 3.8.2.A.2 to place the channel or associated trip system in trip Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The event occurred during power operation while at 100 percent reactor power. The reactor mode selector switch was in the RUN position.

CAUSE OF THE EVENT

Not placing the affected MS PAM channel in a trip condition with the MV pump restored to ready state was a human performance error.

CORRECTIVE ACTIONS

After discovering that the I NOP position for the MS PAM 1705-2D switch does not introduce a channel trip signal as expected, the MV pump was removed from ready state in accordance with TS Action Statement 3.8.2.B.1.

Any further corrective actions will be documented in the corrective action program.

Page 2 of 3 (04-2017)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY 0MB: NO. 3150-0104 EXPIRES: 3/31/2020 LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET (See NUREG-1022, R.3 for instruction and guidance for completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3/)

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

3. LEA NUMBER YEAR Pilgrim Nuclear Power Station 05000- 293 2019

SAFETY CONSEQUENCES

SEQUENTIAL NUMBER

- 003 REV NO.

- 00 The MV pump is provided to remove gases from the main condenser during plant startup and shutdown when steam is not available for the air ejectors. The event occurred during normal power operation. Therefore, the MV pump was not in service, or required. As a result, there were no actual consequences to safety of the general public, nuclear safety, industrial safety, or radiological safety for this event.

REPORTABI LITY The condition is reportable under Title 1 O Code of Federal Regulations 50.73 as a condition prohibited by TS.

PREVIOUS EVENTS There have been no events reported in the last three years related to the MV Pump.

REFERENCES CR-PNP-2019-02431 Page 3 of 3

v t e Letter Sequence Request
EPID:L-2019-LLE-0006, Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR Part 50, Appendix E (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request Acceptance Supplement Administration Questions Answers Results Approval, Approval, Approval Other:
MONTHYEAR2019-06-10 [Table View]

05000293/LER-2019-003, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump

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05000293/LER-2019-003, Condition Prohibited by Technical Specifications Involving the Mechanical Vacuum Pump

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Enclosure:

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EVENT DESCRIPTION

CAUSE OF THE EVENT

CORRECTIVE ACTIONS

SAFETY CONSEQUENCES

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