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Glen Allen, VA 23060
Glen Allen, VA 23060
-6711
-6711 SUBJECT: MILLSTONE POWER STATION UNIT 1  
 
SUBJECT: MILLSTONE POWER STATION UNIT 1  
- SAFE STORAGE INSPECTION REPORT NO. 05000245/201 8 00 1
- SAFE STORAGE INSPECTION REPORT NO. 05000245/201 8 00 1



Revision as of 04:30, 16 May 2019

Safe Storage Inspection Report No. 05000245/2018001
ML18192A441
Person / Time
Site: Millstone Dominion icon.png
Issue date: 07/11/2018
From: Powell R J
Decommissioning Branch I
To: Stoddard D
Dominion Energy
References
IR 2018001
Download: ML18192A441 (10)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 2100 RENAISSANCE BLVD., SUITE 100 KING OF PRUSSIA, PA 19406

-2713 July 11, 2018 Docket No.

05000245License No.

DPR-21 Mr. Daniel President and Chief Nuclear Officer Dominion Energy, Inc. Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, VA 23060

-6711 SUBJECT: MILLSTONE POWER STATION UNIT 1

- SAFE STORAGE INSPECTION REPORT NO. 05000245/201 8 00 1

Dear Mr. Stoddard:

On June 11 - 1 4, 201 8 , the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Millstone Power Station Unit 1 (MS

-1). The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and the conditions of your license. The inspection consisted of observations by the inspector, interviews with personnel, and a review of procedures and records. The results of the inspection were discussed with Michael O'Connor , Director - Nuclear Safety & Licensing, and other members of your organization on June 1 4, 201 8, at the conclusion of the inspection. The enclosed report presents the results of this inspection. No findings of safety significance were identified.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure(s), and your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRC document system (ADAMS), accessible from the NRC website at http://www.nrc.gov/reading

-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.

Current NRC regulations and guidance are included on the NRC's website at www.nrc.gov; select Radioactive Waste; Decommissioning of Nuclear Facilities; then Regulations, Guidance and Communications. The current Enforcement Policy is included on the NRC's website at www.nrc.gov; select About NRC, Organizations & Functions; Office of Enforcement; Enforcement documents; then Enforcement Policy (Under 'Related Information'). You may also obtain these documents by contacting the Government Printing Office (GPO) toll

-free at 1-866-512-1800. The GPO is open from 8:00 a.m. to 5:30 p.m. EST, Monday through Friday (except Federal holidays). No reply to this letter is required. Please contact Katherine Warner at 610-337-5389 if you have any questions regarding this matter.

Sincerely,

/RA/ Raymond J. Powell, Chief Decommissioning, ISFSI, and Reactor HP Branch Division of Nuclear Materials Safety Enclosure: Inspection Report No. 05000245/201 8 00 1 cc: w/encl: Distribution via ListServ

EXECUTIVE SUMMARY

Dominion Energy, Inc. Millstone Power Station Unit 1

NRC Inspection Report No. 05000245/

201 8 00 1 A n announced safety inspection was conducted on June 11 - 1 4, 201 8 at MS-1. The inspector reviewed MS

-1's activities related to the safe storage of radioactive material, including site operations, engineering, maintenance, plant support activities, management oversight, and corrective action program (CAP) implementation. The inspection consisted of observations by the inspector, interviews with Dominion personnel, a review of procedures and records, and plant walk-downs. There are currently no ongoing decommissioning activities being conducted at MS

-1. The NRC's program for overseeing the safe operation of a shut-down nuclear power reactor is described in Inspection Manual Chapter (IMC) 2561, "Decommissioning Power Reactor Inspection Program." Based on the results of this inspection, no findings of safety significance were identified.

1 Inspection Report No. 05000245/201 800 1

REPORT DETAILS

1.0 Background MS-1 went into commercial operation on December 28, 1970

, and permanently ceased operations on July 17, 1998. Subsequently, the fuel was permanently removed from the reactor vessel and is currently stored in the spent fuel pool (SFP). MS-1 is in safe storage (SAFSTOR) and Dominion plans to actively decommission MS

-1 in parallel with the decommissioning of the operational units after they have been permanently shut down. Operations and radiation protection/chemistry personnel from Millstone Unit

-2 (MS-2) provide routin e support functions to MS

-1.

The NRC's program for overseeing the safe operation of a shut

-down nuclear power reactor is described in IMC 2561.

2.0 SAFSTOR Performance and Status Review

a. Inspection Scope

(Inspection Procedures 36801, 37801, 40801, 60801 , 62801, 64704 , 71801, 83750, 84750, 86750) A n announced safety inspection was conducted on June 11 - 14, 201 8. The inspection consisted of observations by the inspector, interviews with Dominion personnel, a review of procedures and records, and plant walk

-downs. The inspector reviewed the SAFSTOR program as outlined in the defueled safety analysis report , and Technical Specifications (TS) and assess ed the adequacy of management oversight of SAFSTOR responsibilities for the MS

-1 facility. Specifically, the inspector reviewed the decommissioning management and staff organization and Dominion's implementation of SAFSTOR activities related to safe storage of radioactive material. The inspector also conducted a walk-down to assess the material condition of the MS

-1 facility (reactor building, the fuel

-handling floor, building exterior, condenser bay, and drywell

) and discussed any design changes or modifications since the previous inspection.

The inspector reviewed MS

-1's program for the safe wet storage of spent fuel. The inspector performed walk

-downs of the SFP and associated support systems to assess material condition, configuration control, and system operation.

The inspector observed activities associated with Boron Arial Density Gauge Evaluating Racks (BADGER) Testing. The inspector reviewed activities, components, and documentation associated with the following SAFSTOR programs:

occupational exposure, fire protection, radioactive effluent control, site radiological environmental monitoring program (REMP), maintenance and surveillance, and decommissioning organization and staffing. The inspector reviewed radiological survey reports, radioactive liquid effluent release permits, the annual REMP report, the annual effluent release report, condition reports, and MS-1 firefighting strategies and procedures

. The inspector reviewed Dominion fleet audit reports and CAP documents associated with MS-1 to determine if issues were being appropriately identified, assessed and reviewed and that corrective actions were being appropriately implemented.

Inspection Report No. 05000245/201800

b. Observations and Findings

The inspector confirmed that the SAFSTOR program was being effectively implemented. The inspector verified that the maintenance and surveillance program for systems and components had been conducted in accordance with the TS requirements and established procedures. T he inspector also confirmed that no dismantlement or decommissioning activities were performe d since the previous inspection.

The inspector determined that MS

-1 was safely storing spent fuel in wet storage.

The inspector noted that the design change to the MS-1 central monitoring station has been completed since the last inspection.

The inspector noted that the upgrade included alarms for exterior temperature indications for decay heat removal components.

BADGER Testing involves using a neutron source and an array of neutron sensitive instruments to determine the reactivity "effectiveness" of the MS

-1 SFP carborundum fuel racks.

The inspector observed activities associated with BADGER testing including pre-job briefs, troubleshooting, assembly, and testing. The inspector noted that MS

-1 tested 39 panels and will perform this test every 5 years in accordance with guidance from NEI 16

-03. As previously indicated, MS

-2 operations support operations at MS

-1. The inspector reviewed MS

-1's firefighting strategies and noted that the fire brigade staffed from MS

-2 and Millstone Unit 3's operations would respond in the event of a fire at MS-1. Fire drills are routinely performed at MS

-1 and staff are familiarized with MS

-1 during training. The inspector noted that MS

-2 health physics support operations at MS

-1 by performing surveys, providing radiation protection coverage for work, and providing RP briefings as necessary.

The annual radiological effluent and the annual REMP reports demonstrated that all calculated doses were below regulatory dose criteria of 10 Code of Federal Regulations 50, Appendix I

. The inspector noted that Dominion had one shipment of Class A dry active waste and one shipment of limited quantity material shipped for offsite disposal from MS-1 since the last inspection.

The inspector discussed shipping requirements and processes with Millstone Power Station staff.

Findings or issues identified from audits, plant equipment operator's rounds, and staff observations were entered into the CAP. Dominion effectively addressed identified issues, implemented corrective actions, and tracked them to closure. Condition reports and corrective actions appeared to be prioritized and evaluated commensurate with their safety significance.

c. Conclusions

Based on the results of this inspection, no findings of safety significance were identified.

Inspection Report No. 05000245/201800 3.0

Exit Meeting Summary

On June 14, 201 8 , the inspector presented the inspection results to Michael O'Connor, Director - Nuclear Safety & Licensing, and other members of Dominion's staff.

The inspector confirmed that no copies of proprietary information were used during this inspection and none were removed from the site.

Inspection Report No. 05000245/

201800 1 PARTIAL LIST OF PERSONS CONTACTED Licensee J. Armstrong Fire Protection Program Engineer W. Brown Licensing Technical Lead C. Dix Health Physics Supervisor Site M. Goolsb e y Unit 2 Superintendent Nuclear Unit 2 Operations B. Graber Radioactive Analysis Group Supervisor J. Nelson Health Physicist T. Schleicher Nuclear Core Design Supervisor G. Sturgeon Operations Nuclear Specialist MS

-1 M. Wood Radioactive Material Control Supervisor M. Wynn Acting RP and Chemistry Manager P. Vernacchio NETCO Engineer ITEMS OPEN, CLOSED, AND DISCUSSED None LIST OF

DOCUMENTS REVIEWED

2017 Radioactive Effluent Release Report and Off

-Site Dose Calculation Manual

(REMODCM), May 1, 2018

2017 Annual Radiological Environmental Operating Report, May 1, 201 8 Audit 17-04: Fire Protection and SPS Refueling, July 20, 2017

Defueled Safety Analysis Report

ETE-NAF-2018-0047, Review of NEI 16

-03 Guidance in Preparation for the 2018 Millstone Unit

Spent Fuel Pool BADGER Carborundum Areal Density Measurements

Liquid Discharge Permit, L

-EFF1-20171205-601-B, December 4, 2017

Liquid Discharge Permit, L

-EFF1-20180410-191-B, April 10, 2018

RP-AA-300 Micro ALARA Plan BADGER (Blackness Testing and Support Activities Unit 1, May

21, 2018 Millstone Nuclear Power Station Unit 1 , Spent Fuel Pool Island Vent Filters Sample

, February 27, 2017 Millstone Unit 1 Exposure Report, January 3, 2018

Millstone Unit 1 Exposure Report, April 2, 2018

Millstone Unit 1 Defueled Technical Requirements Manual

Millstone Power Station Unit 1 Permanently Defueled Technical Specifications (TS)

MS-1 Operational Issues Tracking Report

MS-1 Radiation Surveys 201

Package Characterization Report, C20312, October

3, 2018 Package Characterization Report, C21630 , October 10, 201 8 Radiation Work Permit (RWP) 1170007

- Low Risk Areas in RCA

- Self Briefing, Revision 0

RWP 1170008 - NRC, Revision 1

SP 1054A, Spent Fuel Rack Surveillance Program

- Boron Carbide Plate, Revision 005

Special Engineering Procedure 28099

-000-01, Procedure for Assembly and Testing of the

Boron-10 Areal Density Meter at Millstone Power Station, Revisio

n 0 Worker Qualification Status, NU

-MPSU1CFH - Millstone Unit 1 Certified Fuel Handler (CFH)

Inspection Report No. 05000245/

2018001 Work Orders:

53102445515

53102996223

53103054328

53103124688

203160248

Condition Reports:

1067839 1069125 1069130 1076366 1079068 1079069 1080284 1080368 1081457 1082035 1082070 1082542 1082544 1083609 1084397 1084599 1086632 1087203 1090510 1091163 1091175 1091176 1091181 1091184 1091266 1091411 1091486 1091488 1091491 1092019 1093319 1099410 1099537 1099561 1099662 LIST OF ACRONYMS USED

BADGER Boron Arial Density Gauge Evaluating Racks

CAP Corrective Action Program

Dominion Dominion Energy, Inc. IMC Inspection Manual Chapter

MS-1 Millstone Power Station Unit 1

MS-2 Millstone Power Station Unit 2

NRC U.S. Nuclear Regulatory Commission

REMP Radiological Environmental Monitoring Program

SAFSTOR Safe Storage

SFP Spent Fuel Pool

TS Technical Specification