05000416/LER-2016-008, Regarding Entry Into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable

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Regarding Entry Into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable
ML16301A152
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 10/27/2016
From: Nadeau J
Entergy Operations
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2016/00055 LER 16-008-00
Download: ML16301A152 (4)
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LER-2016-008, Regarding Entry Into Mode of Applicability with the Alternate Decay Heat Removal System 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)(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)
4162016008R00 - NRC Website
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text

~

~Entergy GNRO-2016/00055 October 27, 2016 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Entergy Operations, Inc.

P. O. Box 756 Port Gibson, MS 39150 James Nadeau Manager, Regulatory Assurance Grand Gulf Nuclear Station Tel. (601) 437-2103

SUBJECT:

Dear Sir or Madam:

Licensee Event Report LER 2016-008-00, Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 Attached is Licensee Event Report LER 2016-008-00, Entry into Mode of Applicability with the Alternate Decay Heat Removal System Inoperable. This report is being submitted in accordance with Title 10 Code of Federal Regulations 50.73(a)(2)(i)(B).

This letter contains no new commitments.

If you have any questions or require additional information, please contact James Nadeau at 601-437-2103.

Sincerely, JJN/ram Attachment Licensee Event Report (LER) 2016-008-00 cc: see next page

NRC FORM 366 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 />.

/.....,.,

LICENSEE EVENT REPORT (LER)

Reported lessons learned are incorporated into the licensing process and fed back to industry.

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d, i Send comments regarding burden estimate to the

FOIA, Privacy and Information Collections

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(SeePage 2forrequired number ofdigits/characters foreachblock)

Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or bye-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory (See NUREG-1022, R.3 for instruction and guidance for completing this form 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 http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3(J number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

3. PAGE Grand Gulf Nuclear Station Unit 1 05000416 10F3
4. TITLE Entrv into Mode of Aoolicabilitv with the Alternate Decav Heat Removal SYstem Inoperable
5. EVENT DATE
6. LER NUMBER
7. REPORT DATE
8. OTHER FACILITIES INVOLVED YEAR ISEQUENTIALI REV FACILITY NAME DOCKET NUMBER MONTH DAY YEAR NUMBER NO.

MONTH DAY YEAR N/A 05000N/A FACILITY NAME DOCKET NUMBER 09 09 2016 2016 008 00 10 27 2016 N/A 05000N/A 9.OPERATlNGMODE 11.THISREPORTISSUBMITTED PURSUANTTO THE REQUIREMENTSOF 10CFR§: (Checkall that apply)

MODE4 o 20.2201 (b) o 20.2203(a)(3)(i) o 50.73(a)(2)(ii)(A) o 50.73(a)(2)(viii)(A) o 20.2201 (d) o 20.2203(a)(3)(ii) o 50.73(a)(2)(ii)(B) o 50.73(a)(2)(viii)(B) o 20.2203(a)(1) o 20.2203(a)(4) o 50.73(a)(2)(iii) o 50.73(a)(2)(ix)(A) o 20.2203(a)(2)(i) o 50.36(c)(1 )(i)(A) o 50.73(a)(2)(iv)(A) o 50.73(a)(2)(x)

10. POWERLEVEL o 20.2203(a)(2)(ii) o 50.36(c)(1 )(ii)(A) o 50.73(a)(2)(v)(A) o 73.71 (a)(4) o 20.2203(a)(2)(iii) o 50.36(c)(2) o 50.73(a)(2)(v)(B) o 73.71 (a)(5) 0%

o 20.2203(a)(2)(iv) o 50.46(a)(3)(ii) o 50.73(a)(2)(v)(C) o 73.77(a)(1) o 20.2203(a)(2)(v) o 50.73(a)(2)(i)(A) o 50.73(a)(2)(v)(D) o 73.77(a)(2)(i) o 20.2203(a)(2)(vi)

~ 50.73(a)(2)(i)(B) o 50.73(a)(2)(vii) o 73.77(a)(2)(ii) o 50.73(a)(2)(i)(C) o OTHER Specify inAbstract below orinNRC Form 366A

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

James Nadeau I Manager, Regulatory Assurance (601) 437-2103 13.COMPLETEONE UNE FOR EACH COMPONENTFAILUREDESCRIBEDINTHISREPORT

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE

CAUSE

SYSTEM COMPONENT MANU-REPORTABLE FACTURER TO EPIX FACTURER TO EPIX X

N/A N/A N/A Y

N/A N/A N/A N/A N/A

14. SUPPLEMENTAL REPORT EXPECTED
15. EXPECTED MONTH DAY YEAR

~ YES (Ifyes, complete 15. EXPECTED SUBMISSIONDATE)

D NO SUBMISSION 03 03 2017 DATE ABSTRACT(Limitto 1400spaces, i.e., approximately 15single-spaced typewritten lines)

Entergy manually shutdown the Grand Gulf Nuclear Station (GGNS) reactor on September 8,2016, at approximately 1104 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.20072e-4 months <br />, to replace Residual Heat Removal (RHR) Pump lA' after it failed its technical specification surveillance. The reactor entered MODE 4, Cold Shutdown, at approximately 0509 hours0.00589 days <br />0.141 hours <br />8.416005e-4 weeks <br />1.936745e-4 months <br /> on September 9,2016. Residual Heat Removal Train IB' was placed in shutdown cooling mode (SOC) to maintain Reactor coolant temperature 110 degrees Fahrenheit (F) to 120 F on September 9, 2016 at 0332. At the time of entry into MODE 4, and throughout the time period the lA' RHR pump was inoperable, the Alternate Decay Heat Removal (ADHR) System was not available because the ADHR heat exchangers tube-side cooling water system had been clearance-tagged CLOSED to support cleaning of the heat exchanger tubes since

~ugust 10,2016. This condition was not identified until September 23,2016, after the lA' RHR train was returned to OPERABLE status. The direct cause of this event appears to be the lack of adequate information validation and verification by station personnel. Entergy personnel verified both RHR trains were operable and available on September 23,2016, r.,.vhen the ADHR Heat Exchangers were identified as clearance-tagged CLOSED. The cause of the event remains under investigation and this licensee event report will be supplemented upon completion of the causal evaluation.

PLANT CONDITIONS PRIOR TO THE EVENT MODE4

'A' RHR Pump inoperable

~~r-

'B' RHR Pump in service providing shutdown cooling Alternate Decay Heat Removal System inoperable 2016

  • 008
  • 00

DESCRIPTION

Entergy manually shutdown the Grand Gulf Nuclear Station (GGNS) reactor on September 8,2016, at approximately 1104 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.20072e-4 months <br />, to replace Residual Heat Removal (RHR) [BO] Pump 'A' after it failed its technical specification surveillance. The reactor entered MODE 4, Cold Shutdown, at approximately 0509 hours0.00589 days <br />0.141 hours <br />8.416005e-4 weeks <br />1.936745e-4 months <br /> on September 9, 2016. Residual Heat Removal Train 'B' was placed in shutdown cooling mode (SDC) to maintain Reactor coolant temperature 110 degrees Fahrenheit (F) to 120 F. At approximately 1742 hours0.0202 days <br />0.484 hours <br />0.00288 weeks <br />6.62831e-4 months <br /> on September 9,2016, The Alternate Decay Heat Removal (ADHR) [BO] System was placed into standby.

Grand Gulf Nuclear Station Technical Specification (TS) 3.4.10, Residual heat Removal (RHR) Shutdown Cooling System - Cold Shutdown, requires two trains of RHR to be OPERABLE. Condition A, One or two RHR shutdown cooling subsystems inoperable requires the verification of an alternate method of decay heat removal is available for each inoperable RHR shutdown cooling subsystem. This action is required to be completed within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter during the mode of applicability.

At the time of entry into MODE 4, and throughout the time period the 'A' RHR pump was inoperable, the ADHR System was not available because the ADHR heat exchangers tube-side cooling water system had been clearance-tagged closed to support cleaning of the heat exchanger tubes since August 10, 2016.

This condition was not identified until September 23, 2016, after the 'A' RHR train was returned to OPERABLE status.

Alternate Decay Heat Removal Background Information:

The ADHR System provides an alternate method of reactor decay heat removal during cold shutdown and refueling conditions. It is designed for use during MODEs 4 and 5 to provide decay heat removal when maintenance is being performed on RHR shutdown cooling loops or associated support systems. An alternative method of decay heat removal must be demonstrated for each required RHR SDC loop that is inoperable. The cause of the event is under investigation and this licensee event report will be supplemented upon completion of the causal evaluation. The direct cause of this event appears to be the lack The ADHR System is an auxiliary cooling loop included as part of the RHR System with separate pumps, heat exchangers, and controls. The ADHR System is completely isolated mechanically and electrically from connected plant systems during MODEs 1,2, and 3. The functional design basis for the ADHR System is to maintain Reactor coolant temperatures below TS limits during cold shutdown and refueling operations, accomplishing this task by operating in either a Reactor to Reactor cooling mode or Spent Fuel Pool to Reactor cooling mode.

The ADHR pumps and heat exchangers are located in RHR 'C' Pump Room. Cooling water for the ADHR heat exchangers is supplied by the Plant Service Water (PSW) System.Page 2 of 3

U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB: NO. 3150-0104(06-2016)

LICENSEE EVENT REPORT (LER)

CONTINUATION SHEET (SeeNUREG-1 022, R.3for instruction and guidancefor completing this form http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1022/r3D EXPIRES: 10/31/2018 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 bye-mail to Infocoliects.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. " a means used to impose an information collection does not display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person is not required to respond to, the information collection.

1. FACILITY NAME Grand Gulf Nuclear Station Unit 1
2. DOCKET NUMBER 05000-416 YEAR I
3. LERNUMBER SEQUENTIAL I

REV NUMBER NO.

2016

- 008
- 00 Two identical ADHR pumps provide the needed head to pump water at a maximum combined flow of 3600 gpm when operated in parallel.

Two ADHR heat exchangers, also located in the RHR "C" Pump Room are operated in a parallel arrangement to provide the required decay heat removal. Each heat exchanger is a horizontally mounted, 50% capacity, two-pass, U-tube type heat exchanger with a single-pass shell. Plant Service Water passes through the tubes, while the water being cooled passes through the shell.

Plant Service Water provides the cooling source to the ADHR System heat exchangers and the ADHR System Air Conditioning Unit. A loss of PSW would prevent the ADHR System from performing its intended function.

REPORTABILITY

CAUSE The cause of the event is under investigation and this licensee event report (LER) will be supplemented upon completion of the causal evaluation. The direct cause of this event appears to be the lack of adequate information validation and verification by station personnel.

CORRECTIVE ACTIONS

Entergy personnel verified both RHR trains were operable and available on September 23, 2016, when the ADHR Heat Exchangers were identified as clearance-tagged CLOSED.

Entergy established a causal evaluation to determine the cause and to establish corrective actions as appropriate. This LER will be supplemented upon completion of this causal evaluation.

SAFETY SIGNIFICANCE

There were no actual nuclear safety consequences or radiological consequences during the event. The

'B' RHR train remained OPERABLE and in service, maintaining shutdown cooling throughout the duration of the event.

PREVIOUS SIMILAR EVENTS

LER 2013-004-00, Operation Prohibited By Technical Specifications Due To Inadvertent Bypass of Reactor Steam Dome High Pressure Interlock For Residual Heat Removal System Isolation LER 2013-005-00, Reactor Pressure Vessel Steam Pressure Less Than 0 PSIG During Six Plant Startups Resulting In A Technical Specification 3.4.11 RCS Pressure And Temperature (PFF) Limits Violation LER 2013-005-01, Reactor Pressure Vessel Steam Pressure Less Than 0 PSIG During Six Plant Startups Resulting In A Technical Specification 3.4.11 RCS Pressure And Temperature (PFF) Limits Violation LER 2015-003-00, Technical Specification Surveillance On Primary Containment Isolation Valves Entergy has reviewed the above identified licensee event reports and has concluded that the causes and corrective actions associated with these licensee event reports could not have prevented the occurrence of the event documented in this licensee event report.Page 3 of 3

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