IR 05000387/2017001

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Integrated Inspection Report 05000387/2017001 and 05000388/2017001
ML17130A896
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 05/09/2017
From: Daniel Schroeder
Reactor Projects Region 1 Branch 4
To: Rausch T
Susquehanna
Schroeder D
References
IR 2017001
Download: ML17130A896 (30)


Text

{{#Wiki_filter:[Type here] UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BLVD.

KING OF PRUSSIA, PA 19406-2713 May 9, 2017 Mr. Timothy President and Chief Nuclear Officer Susquehanna Nuclear, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603 SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION - INTEGRATED INSPECTION REPORT 05000387/2017001 AND 05000388/2017001

Dear Mr. Rausch:

On March 31, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at Susquehanna Steam Electric Station (SSES), Units 1 and 2. On April 7, 2017, the NRC inspectors discussed the results of this inspection with you and other members of your staff.

The results of this inspection are documented in the enclosed report.

NRC inspectors documented one finding of very low safety significance (Green) in this report.

This finding involved a violation of NRC requirements. The NRC is treating this violation as a non-cited violation (NCV) consistent with Section 2.3.2.a of the Enforcement Policy.

If you contest the violation or significance of the NCV, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement; and the NRC Resident Inspector at Susquehanna. In addition, if you disagree with a cross-cutting aspect assignment or a finding not associated with a regulatory requirement in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the U. S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC, 20555-0001; with copies to the Regional Administrator, Region I, and the NRC Resident Inspector at Susquehanna. This letter, its enclosure, and your response, (if any), will be made available for public inspection and copying at http://www.nrc.gov/reading-rm/adams.html and the NRCs Public Document Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.

Sincerely, /RA/ Daniel L. Schroeder, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket Nos. 50-387 and 50-388 License Nos. NPF-14 and NPF-22

Enclosure:

Inspection Report 05000387/2017001 and 05000388/2017001 w/Attachment: Supplementary Information

REGION I== Docket Nos.: 50-387 and 50-388 License Nos.: NPF-14 and NPF-22 Report No.: 05000387/2017001 and 05000388/2017001 Licensee: Susquehanna Nuclear, LLC (Susquehanna) Facility: Susquehanna Steam Electric Station, Units 1 and 2 Location: Berwick, Pennsylvania Dates: January 1, 2017 through March 31, 2017 Inspectors: L. Micewski, Senior Resident Inspector J. Greives, Senior Resident Inspector T. Daun, Resident Inspector T. OHara, Reactor Inspector J. Furia, Senior Health Physicist Approved By: Daniel L. Schroeder, Chief Reactor Projects Branch 4 Division of Reactor Projects Enclosure

SUMMARY

IR 05000387/2017001 and 05000388/2017001; January 1, 2017 through March 31, 2017;

Susquehanna Steam Electric Station Units 1 and 2; Follow-Up of Events and Notices of Enforcement Discretion.

This report covered a three-month period of inspection by resident inspectors and announced baseline inspections performed by regional inspectors. The inspectors identified one non-cited violation (NCV), which was of very low safety significance (Green). The significance of most findings are indicated by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using Inspection Manual Chapter (IMC) 0609, Significance Determination Process, dated April 29, 2015. Cross-cutting aspects are determined using IMC 0310, Aspects Within Cross-Cutting Areas, dated December 4, 2014. All violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement Policy, dated November 1, 2016.

The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.

Cornerstone: Barrier Integrity

Green.

A self-revealing finding of very low safety significance (Green) and associated NCV of TS 5.4.1, Procedures, was identified for failure to implement procedures that resulted in a secondary containment fan trip and associated loss of safety function. Susquehannas immediate corrective actions included restoring the secondary containment system to an operable configuration, and entering the issue into their corrective action program (CAP).

Inspectors determined that the finding was more than minor because it was associated with the Human Performance attribute (Routine OPS/Maintenance Performance) of the Barrier Integrity cornerstone and affected the cornerstone objective of providing reasonable assurance that physical design barriers (Secondary Containment) protect the public from radionuclide releases caused by accidents or events. The failure to adequately implement procedures for operation and maintenance of the secondary containment resulted in the inoperability of Zone 3 secondary containment and an associated loss of safety function. In accordance with IMC 0609.04, Initial Characterization of Findings, dated October 7, 2016, and Exhibit 3 of IMC 0609, Appendix A, The Significance Determination Process for Findings At-Power, dated June 19, 2012, the inspectors determined that this finding was of very low safety significance (Green) because the performance deficiency only impacted the radiological barrier function of secondary containment. This finding had a cross-cutting aspect in the area of Human Performance, Teamwork because individuals and work groups did not communicate and coordinate their activities within and across organizational boundaries to ensure nuclear safety was maintained. Specifically, personnel did not conduct a re-brief of the team after the plan deviated from what was originally briefed, and the team did not adequately respond to challenges from workers in the field about whether it was appropriate to commence load center restoration with work still in progress.

   [H.4] (Section 4OA3)

REPORT DETAILS

Summary of Plant Status

Unit 1 began the inspection period at 100 percent power. On February 24, 2017, operators reduced power to approximately 72 percent for a planned control rod sequence exchange.

Following the exchange, operators returned the unit to 100 percent on February 25, 2017.

The unit remained at 100 percent power for the remainder of the inspection period.

Unit 2 began the inspection period at 100 percent power. On January 20, 2017, operators reduced power to approximately 82 percent, performed rod pattern adjustments and returned the unit to 100 percent on January 21, 2017. On January 28, 2017, power was reduced to 85 percent for rod pattern adjustments and returned to 100 percent the same day. On January 31, 2017, operators lowered power and commenced end-of-cycle coast down for the remainder of the cycle. On March 3, 2017, operators commenced reducing power from 87 percent for a planned refueling outage. Unit 2 reached Mode 4 on March 4, 2017 and remained shut down for the remainder of the inspection period.

REACTOR SAFETY

Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity

1R01 Adverse Weather Protection

.1 Readiness for Impending Adverse Weather Conditions

a. Inspection Scope

The inspectors reviewed Susquehannas preparations for a winter weather advisory for an impending winter storm on February 8, 2017. The inspectors reviewed the implementation of adverse weather preparation procedures before the onset of and during this adverse weather condition. The inspectors walked down the emergency diesel generator (EDG) system and emergency service water to ensure system availability. The inspectors verified that operator actions defined in Susquehannas adverse weather procedure maintained the readiness of essential systems. The inspectors discussed readiness and staff availability for adverse weather response with operations and work control personnel.

b. Findings

No findings were identified. ==1R04 Equipment Alignment

.1 Partial System Walkdowns

==

a. Inspection Scope

The inspectors performed partial walkdowns of the following systems:

  • Unit Common, B control structure chiller during A control structure chiller system outage window (SOW) on January 6, 2017;
  • Unit Common, E EDG while substituted for A EDG during A EDG SOW on January 18, 2017;
  • Unit 2, high pressure coolant injection (HPCI) during reactor core isolation cooling (RCIC) SOW on January 24, 2017;
  • Unit 2, spent fuel pool cooling while shutdown cooling was secured for residual heat removal (RHR) common work window on March 23, 2017 The inspectors selected these systems based on their risk-significance relative to the reactor safety cornerstones at the time they were inspected. The inspectors reviewed applicable operating procedures, system diagrams, the Updated Final Safety Analysis Report (UFSAR), technical specifications (TSs), work orders, condition reports (CRs),and the impact of ongoing work activities on redundant trains of equipment in order to identify conditions that could have impacted the systems performance of its intended safety functions. The inspectors also performed field walkdowns of accessible portions of the systems to verify system components and support equipment were aligned correctly and were operable. The inspectors examined the material condition of the components and observed operating parameters of equipment to verify that there were no deficiencies. The inspectors also reviewed whether Susquehanna staff had properly identified equipment issues and entered them into the CAP for resolution with the appropriate significance characterization.

b. Findings

No findings were identified. ==1R05 Fire Protection

.1 Resident Inspector Quarterly Walkdowns