NMP1L3129, LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration

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LER 17-01-00 for Nine Mile Point Unit 1 Manual Reactor Scram Due to High Turbine Vibration
ML17044A007
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 02/08/2017
From: Kreider R
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NMP1L3129 LER 17-001-00
Download: ML17044A007 (8)
v • d • e


Text

p:i: . 7 r+7 Exelon Generation 10 CFR 50.73 NMP1L3129 February 8, 2017 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63 Docket No. 50-220

Subject:

NMP1 Licensee Event Report 2017-001, Manual Reactor SCRAM Due to High Turbine Vibration

There are no regulatory commitments contained in this letter.

Should you have any questions regarding the information in this submittal, please contact Dennis Moore, Site Regulatory Assurance Manager, at (315) 349-5219.

Respectfully, Robert E. Kreider Jr.

Plant Manager, Nine Mile Point Nuclear Station.

Exelon Generation Company, LLC REK/RSP

Enclosure:

NMP1 Licensee Event Report 2017-001, Manual Reactor SCRAM Due to High Turbine Vibration cc: NRG Regional Administrator, Region I NRG Resident Inspector NRG Project Manager

Enclosure NMP1 Licensee Event 2017-001, Manual Reactor SCRAM Due to High Turbine Vibration Nine Mile Point Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-63

NRCFORM 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

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LICENSEE EVENT REPORT (LER)

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

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 lnfocollects.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 (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control htt12://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3D number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME 2. DOCKET NUMBER .PAGE Nine Mile Point Unit 1 05000220 1 OF6
4. TITLE l\A::in11::il ~ - 1r ~l"'r::Jm nr It:> tn Hinh Tt trhim Vihr::itinn
5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED MONTH DAY YEAR YEAR ISEQUENTIAL NUMBER I REV NO.

MONTH DAY YEAR FACILITY NAME NA DOCKET NUMBER NA FACILITY NAME DOCKET NUMBER 12 10 2016 2017 - 01 00 02 08 2017 NA NA

9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: /Check all that aooly) 1 D 20.2201 (b) D 20.2203(a)(3)(i) D 50.73(a)(2)(ii)(A) D 50.73(a)(2)(viii)(A) p 20.2201 (d) D 20.2203(a)(3)(ii) D so.73(a)(2)(ii)(B) D 50.73(a)(2)(viii)(B)

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

D 20.2203(a)(2)(i) D 50.36(c)(1 )(i)(A) [8J 50.73(a)(2)(iv)(A) D 50.73(a)(2)(x)

10. POWER LEVEL D 20.2203(a)(2)(ii) 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 50.36(c)(2) D 50.73(a)(2)(v)(B) D 73.71 (a)(5) 97 D 20.2203(a)(2)(iv) D so.46(a)(3)(ii) D 50.73(a)(2)(v)(C) D 73.77(a)(1)

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)(i)

D 20.2203(a)(2)(vi) .0 50.73(a)(2)(i)(B) D 50.73(a)(2)(vii) D 73.77(a)(2)(ii)

D 50.73(a)(2)(i)(C) 00THER Specify in Abstract below or in NRC Form 366A

12. LICENSEE CONTACT FOR THIS LER ICENSEE CONTACT rELEPHONE NUMBER (Include Area Code)

Dennis Moore, Site Requlatorv Assurance Manaqer (315)349-5219

13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT MANU- REPORTABLE MANU- REPORTABLE CAUSE SYSTEM COMPONENT CAUSE SYSTEM COMPONENT FACTURER TOEPIX FACTURER TOEPIX B TA PSF GE y x EA CNTR GE ~
14. SUPPLEMENTAL REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR SUBMISSION D YES (If yes, complete 15. EXPECTED SUBMISSION DATE) [8J NO DATE NA NA NA ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines)

On December 10, 2016 at 08:48, Nine Mile Point Unit 1 performed a manual scram of the reactor due to increased vibrations on the main turbine. Following the scram, the High Pressure Coolant Injection (HPCI)

System automatically initiated. This event is reportable under 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b )(3)(iv)(A) as any event or condition that resulted in a manual or automatic actuation of any of the systems listed in 10 CFR 50.72(b)(3)(iv)(B).

During performance of a load drop to 95% power in support of Turbine Stop Valve Testing, main turbine bearing vibrations rose on several bearings. The Unit 1 Reactor was scrammed and the main turbine was secured when main bearing #1 reached procedural limits. The root cause of the event was a steam leak from a threaded pipe/cap connection that was not seal welded when originally supplied from the manufacturer. The connection

!has now been seal welded.

A combination of tight tolerance in conjunction with the location of the steam leak resulted in the vibrations when power level was changed.

rrhe event described in this LER is documented in the plant's corrective action program.

NRG FORM 366A (06-2016)

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

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.

f~</f.* LICENSEE EVENT REPORT (LER) Send comments regarding burden estimate to the FOIA, Privacy and Information Collections

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"* ..... ,; CONTINUATION SHEET Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.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 (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control htto://www.nrc.gov/readinq-rm/doc-collections/nureqs/staff/sr1022/r3{J number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME 2. DOCKET NUMBER 3. LER NUMBER YEAR I SEQUENTIAL I REV Nine Mile Point Unit 1 05000220 NUMBER NO.

2017 001 - 00 NARRATIVE

r. DESCRIPTION OF EVENT A. PRE-EVENT PLANT CONDITIONS:

Prior to the event, Nine Mile Point Unit 1 (NMPl) was operating at 100% with Operations performing a load drop to 95% to support turbine stop valve testing and control rod pattern adjustment.

B. Event:

On December 10, 2016 at 08:48, Nine Mile Point Unit 1 performed a manual scram of the reactor due to increased vibrations on the main turbine. This was performed during a load drop to 95% reactor power to facilitate turbine stop valve testing and rod line adjustments. At 95% reactor power operations noted rising vibrations on the main turbine bearings. The reactor was manually scrammed and the main turbine was secured as the observed vibrations reached procedural limits. Following the scram, as designed, HPCI initiated on low Reactor Pressure Vessel (RPV) water level due to the initial RPV level shrink. HPCI was secured following recovery of RPV water level above the low level scram setpoint of 53 inches.

There was no impact on Nine Mile Point Unit 2 (NMP2) from this event.

Operations performed the ENS notification (#52425) required by 10 CFR 50.72(b)(2)(iv)(B) and 10 CFR 50.72(b)(3)(iv)(A) for the manual reactor scram and for the expected HPCI initiation due to the Main Turbine Trip. This notification met the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> reporting requirements. This LER is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(iv)(A).

C. INOPERABLE STRUCTURES, COMPONENTS, OR SYSTEMS THAT CONTRIBUTED TO THE EVENT:

None NRG FORM 366A (06-2016)

Page 2 of 6

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

~~~. LICENSEE EVENT REPORT (LER)

Estimated burden per response to comply with this mandatory collection request: BO hours.

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

  • \:*.....*il=f Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail CONTINUATION SHEET to lnfocollects.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 (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3D number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.
1. FACILITYNAME 2. DOCKET NUMBER 3. LER NUMBER YEAR I SEQUENTIAL I REV Nine Mile Point Unit 1 05000220 NUMBER NO.

2017 001 - 00 D. DATES AND APPROXIMATE TIMES OF MAJOR OCCURRENCES:

The times below all occurred on December 10, 2016.

08:00- Operations commences lo.ad drop from 100% to 95% to facilitate turbine stop valve testing and perform a control rod pattern adjustment.

08: 10 - The elevated vibrations are first observed and Operations talce action in an effort to mitigate vibrations by returning the plant to pre-transient conditions.

08:48:04 - Vibration levels approach procedurally limited thresholds and operations performs a manual scram of the reactor and manually trip the turbine.

08:48:09 - HPCI actuation signal received on RPV Low Level.

08:48: 14 - Expected generator lock-out is received and initiates the fast transfer of Power Board 11 and 12. Power Board 11 fast transfers as expected; however, Power Board 12 fails to fast transfer.

Power Board 12 is re-energized 16 minutes later at 09:04 08:48: 14 -HCPI 11 Train initiates, level is restored above 53 inches (RPV Low Level Setpoint) and initiation signal reset less than 1 minute after at 08:49.

E. OTHER SYSTEMS OR SECONDARY FUNCTIONS AFFECTED:

Power Board 12 failed to fast transfer following the turbine trip due to high resistance on feeder breaker (R122) auxiliary contacts. This resulted in HPCI 12 train not starting following the manual trip of the main turbine. The failure to fast transfer also resulted in the loss of associated, non-safety related, downstream loads on Power Board 12. Power Board 12 was re-energized 16 minutes later at 09:04.

F. METHOD OF DISCOVERY:

This change in condition was immediately recognized by Operations during the load drop to 95%

based on the close monitoring of plant conditions and adherence to station procedures.

NRG FORM 366A (06-2016) Page 3 of 6

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

Estimated burden per response to comply with this mandatory collection request: BO hours.

/"', Reported lessons learned are incorporated into the licensing process and fed back to industry.

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LICENSEE EVENT REPORT {LER) Send comments regarding burden estimate to the FOIA, Privacy and Information Collections il

\. ..... *' CONTINUATION SHEET Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.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 (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3L) number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITYNAME 2. DOCKET NUMBER 3. LER NUMBER YEAR I SEQUENTIAL I REV Nine Mile Point Unit 1 05000220 NUMBER NO.

2017 .001 -00 G. MAJOROPERATORACTION:

Based on the monitoring of plant conditions and in accordance with station procedures Operators performed the following; manually scramed the reactor, manually tripped the main turbine, and energized Power Board 12 at 09:04 following the failure to fast transfer.

H. SAFETY SYSTEM RESPONSES:

All safety systems responded as expected. The HPCI 11 Train initiated. HPCI is a flow control mode of the normal feed water system and is not an emergency core cooling system. At Nine Mile Point Unit 1, a HPCI system actuation signal on low reactor pressure vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI 12 Train did.not start due to Power Board 12 failing to fast transfer. Operations energized Power Board 12 at 09:04 IL CAUSE OF THE EVENT:

The root cause of the event was a steam leak from a threaded pipe/cap connection that was not seal welded when originally supplied from the manufacturer. During the performance of the load drop the pre-existing steam leak and the dynamic conditions within that area created a condition in which internal clearances were reduced resulting in an internal rub on the HP Turbine. This, in turn, resulted in increased vibrations to the limits prescribed in the operating procedure.

NRG FORM 366A (06*2016) Page 4 of 6

NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMS: NO. 3150-0104 EXPIRES: 10/31/2018 (06-2016)

.~¥~. LICENSEE EVENT REPORT (LER)

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

~J

~ ......; CONTINUATION SHEET Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to lnfocollects.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 (See NUREG-1022, R.3 for instruction and guidance for completing this form means used to impose an information collection does not display a currently valid OMB control http://www.nrc.gov/readinq-rm/doc-collections/nureqs/staff/sr1022/r30 number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME 2. DOCKET NUMBER 3. LEA NUMBER SEQUENTIAL REV Nine Mile Point Unit 1 05000220 YEAR I NUMBER I NO.

2017 001 -00 III. ANALYSIS OF THE EVENT:

This event was reported under 10 CFR 50.72 (b)(2)(iv)(B) for the manual scram and 10 CFR 50.72(b)(3)(iv)(A) as any event or condition that resulted in a manual or automatic actuation of any of the systems listed in 10 CFR 50.72(b)(3)(iv)(B) due to the High Pressure Cooling Injection (HPCI) actuating during this event. The HPCI 11 Train initiated and performed as designed. HPCI is flow a control mode of the normal feedwater system and is not an emergency core cooling system. At Nine Mile Point Unit 1, a HPCI system *actuation signal on low reactor pressure vessel (RPV) level is normally received following a reactor scram, due to level shrink. HPCI 12 Train did not start due to Power Board 12 failing to fast transfer; operations energized Power Board 12 at 09:04. There was no actual nuclear safety consequences associated with this event and all other safety systems and balance of plant equipment operated as expected.

IV. CORRECTIVE ACTIONS:

A. ACTION TAKEN TO RETURN AFFECTED SYSTEMS TO PRE-EVENT NORMAL STATUS:

HCPI initiation signal was reset, Power board 12 was restored.

B. ACTION TAKEN OR PLANNED TO PREVENT RECURRENCE:

1. Leaking pipe/cap was seal welded. The remaining connections were inspected and verified tight.
2. Remaining pipe/cap connections will be seal welded during the next refueling outage.
v. ADDITIONAL INFORMATION:

A. FAILED COMPONENTS:

Threaded pipe/cap connection in HP Turbine area Power Board 12, Feeder Breaker R122 Auxiliary Contacts NRC FORM 366A (06-2016) Page 5 of 6

.. NRC FORM 366A (06-2016)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 Estimated burden per response to comply with this mandatory collection request: BO hours.

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LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET 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

(\4 *' to lnfocollects.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 (See NUREG-1022, R.3 for instruction and guidance for completing this fomi means used to impose an information collection does not display a currently valid OMB control httQ://www.nrc.gov/reading-mi/doc-collections/nuregs/staff/sr10221r3D number, the NRG may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME 2. DOCKET NUMBER 3. LER NUMBER SEQUENTIAL REV Nine Mile Point Uni.t 1 05000220 YEAR I NUMBER I NO.

2017 001 -00 B. PREVIOUS LERS ON SIMILAR EVENTS:

None C. THE ENERGY INDUSTRY IDENT1FICATION SYSTEM (EIIS) COMPONENT FUNCTION IDENT1FIER AND SYSTEM NAME OF EACH COMPONENT OR SYSTEM REFERRED TO IN THIS LER:

Component IEEE 803 IEEE 805 High Pressure Coolant Injection System --- SJ Main Turbine TRB JJ Power Board 12 JX EA PB 12 Breaker R122 Aux. Contacts CNTR EA Reactor Vessel RPV AD Threaded Pipe/Cap Connection PSF TA D. SPECIAL COMMENTS:

None NRG FORM 366A (06-2016) Page 6 of 6

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