IR 05000387/2010502

IR 05000387-10-502 & 05000388-10-502, on 10/04/2010-10/08/2010, Susquehanna Steam Electric Station, Units 1 and 2, Exercise Evaluation; Emergency Action Level and Emergency Plan Changes; Emergency Preparedness Performance Indicators

ML103200304
Person / Time
Site:	Susquehanna
Issue date:	11/16/2010
From:	James Trapp Plant Support Branch 1
To:	Rausch T Susquehanna
References
IR-10-502
Download: ML103200304 (11)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION I

475 ALLENOALE ROAD

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION-NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE-INSPECTION REPORT NOS.

05000387/2010502 AND 05000388/2010502

Dear Mr. Rausch:

On October 8, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the October 5, 2010, evaluated emergency preparedness exercise at your Susquehanna Steam Electric Station. The enclosed inspection report documents the inspection results, which were discussed on October 8,2010, you and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

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

In accordance with 10 CFR 2.390 of the NRC's"Rules of Practice:' a copy of this letter and its enclosure and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room).

Sincerely, James A. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety Docket Nos: 50-387, 50-388 License Nos: NPF-14, NPF-22

Enclosure:

NRC Inspection Report Nos. 05000387/2010502 and 05000388/2010502

Mr. Timothy Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd - NUCSB3 Berwick, PA 18603-0467 SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION - NRC EVALUATED EMERGENCY PREPAREDNESS EXERCISE - INSPECTION REPORT NOS.

05000387/2010502 AND 05000388/2010502

Dear Mr. Rausch:

On October 8, 2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection of the October 5, 2010, evaluated emergency preparedness exercise at your Susquehanna Steam Electric Station. The enclosed inspection report documents the inspection results, which were discussed on October 8, 2010, with you and other members of your staff.

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

In a

REGION I==

Docket Nos: 50-387, 50-388 License Nos: NPF-14, NPF-22 Report Nos: 05000387/2010502 and 05000388/2010502 Licensee: PPL Susquehanna, LLC Facility: Susquehanna Steam Electric Station, Units 1 and 2 Location: Berwick, Pennsylvania Dates: October 4-8, 2010 Inspectors: S. Barr, Sr. Emergency Preparedness Inspector, DRS, Region I (Lead)

• P. Finney, Susquehanna Senior Resident Inspector, DRS, Region I J. Grieves, Susquehanna Resident Inspector, DRP, Region I R. Rolph, Health Physicist, DRS, Region'

C. Crisden, Emergency Preparedness Inspector, DRS, Region I A. Dugandzic, Reactor Inspector, DRS, Region I Approved By: James A. Trapp, Chief Plant Support Branch 1 Division of Reactor Safety

SUMMARY OF FINDINGS

IR 05000387/2010502, 05000388/2010502; 10/4/2010-10108/2010; Susquehanna Steam

Electric Station, Units 1 and 2; EXercise Evaluation; Emergency Action Level and Emergency Plan Changes; Emergency Preparedness Performance Indicators.

This was an announced inspection conducted by four region-based inspectors and two resident inspectors. No findings were identified. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649. "Reactor Oversight Process," Revision 4. dated December 2006.

NRC-Identified and Self-Revealing Findings

None.

B. Licensee-Identified Findings None.

ii

REPORT DETAILS

REACTOR SAFETY

Cornerstone: Emergency Preparedness (EP)

1EP1 Exercise Evaluation (71114.01-1 Sample)

a. Inspection Scope

Prior to the October 5, 2010, emergency preparedness exercise, the NRC inspectors conducted an in-office review of the exercise objectives and scenario, which PPL Susquehanna, LLC, had submitted to the NRC, to determine if the exercise would test major elements of the Susquehanna Steam Electric Station Emergency Plan as required by 10 CFR 50.47(b)(14). This overall exercise inspection activity represented the completion of one sample on a biennial cycle.

The exercise evaluation consisted of the following review and assessment:

• The adequacy of PPL's performance in the biennial full-participation exercise regarding the implementation of the risk-significant planning standards (RSPS)described in 10 CFR 50.47{b)(4), (5), (9), and (10), which are: emergency classification; offsite notification; radiological assessment; and protective action recommendations, respectively.

• The overall adequacy of PPL's emergency response facilities with regard to NUREG-0696. "Functional Criteria for Emergency Response Facilities," and Emergency Plan commitments. The facilities assessed were the Control Room Simulator, Technical Support Center (TSC), Emergency Operations Facility (EOF),and Joint Information Center (JIC).

• A review of other performance areas, such as: the emergency response organization's (ERO's) recognition of abnormal plant conditions; command and control; intra- and inter-facility communications; prioritization of mitigating activities; utilization of repair and field monitoring teams; interface with offsite agencies; staffing and procedure adequacy; and the overall implementation of the emergency plan and its implementing procedures.

• A review of past performance issues from the last NRC Susquehanna exercise inspection report and PPL's EP drill reports, to determine the effectiveness of licensee corrective actions as demonstrated during the October 5th exercise and to ensure compliance with 10 CFR 50.47(b)(14).

• The licensee's post-exercise critiques, to evaluate PPL's self-assessment of its ERO performance during the October 5th exercise and to ensure compliance with 10 CFR 50, Appendix E, Section IV.F.2.g.

The inspectors reviewed the documents listed in the attachment to this report.

",

b. Findings

No findings were identified.

1EP4 Emergency Action Level (EAl) and Emergency Plan Changes (71114.04 - 1 Sample)

a. Inspection Scope

Since the last NRC inspection of this program area, PPL implemented various changes to the Susquehanna Steam Electric Station Emergency Plan and implementing procedures. PPL had determined that in accordance with 10 CFR 50.54(q), any change made to the Plan had resulted in no decrease in effectiveness of the Plan, and that the revised Plan continued to meet the requirements of 10 CFR 50.47(b) and Appendix E to 10 CFR 50. The inspectors reviewed all EAL changes made since June 2009, and conducted a sampling review of other Emergency Plan changes, including changes to lower-tier emergency plan implementing procedures, to evaluate for any potential decreases in effectiveness of the Emergency Plan. However, this review was not documented in a Safety Evaluation Report and does not constitute formal NRC approval of the changes. Therefore, these changes remain subject to future NRC inspection in their entirety.

b. Findings

No findings were identified.

OTHER ACTIVITIES (OA)

40A1 Performance Indicator (PI) Verification (7'1151 - 3 Samples)

a. Inspection Scope

The inspectors reviewed data for the Susquehanna EP Pis, which are:

(1) Drill and Exercise Performance (DEP);

(2) Emergency Response Organization (ERO) Drill Participation; and,

(3) Alert and Notification System (ANS) Reliability. The last EP inspection at Susquehanna was conducted in the second quarter of 2009, so the inspectors reviewed supporting documentation from EP drills and tests from the second calendar quarter of 2009 through the third quarter of 2010, to verify the accuracy of the reported PI data. The review of these Pis was conducted in accordance with NRC Inspection Procedure 71151, using the acceptance criteria documented in NEI 99-02, "Regulatory Assessment Performance Indicator Guidelines," Revision 6.

This inspection activity represented the completion of three samples on an annual cycle.

b. Findings

No findings were identified.

40A6 Meetings, Including Exit On October 8,2010, the inspectors presented the results of this inspection with Mr. T. Rausch, Senior Vice President and Chief Nuclear Officer, and other members of the Susquehanna staff. No proprietary information was provided to the inspectors during this inspection.

A-'I ATTACHMENT

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee Personnel

T. Rausch, Senior Vice President and Chief Nuclear Officer

S. Davis, Manager, Nuclear Emergency Planning

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

None.