ML13044A599
| ML13044A599 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/13/2013 |
| From: | Mel Gray Reactor Projects Region 1 Branch 4 |
| To: | Rausch T Susquehanna |
| GRAY, MEL | |
| References | |
| IR-12-005 | |
| Download: ML13044A599 (72) | |
See also: IR 05000387/2012005
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION I
2100 RENAISSANCE BOULEVARD, SUITE 100
KING OF PRUSSIA, PENNSYLVANIA 19406-2713
February 13, 2013
Mr. Timothy S. Rausch
Senior Vice President and Chief Nuclear Officer
769 Salem Boulevard, NUCSB3
Berwick, PA 18603
SUBJECT: SUSQUEHANNA STEAM ELECTRIC STATION - NRC INTEGRATED
INSPECTION REPORT 05000387/2012005 AND 05000388/2012005
Dear Mr. Rausch:
On December 31, 2012, the U. S. Nuclear Regulatory Commission (NRC) completed an
inspection at your Susquehanna Steam Electric Station (SSES) Units 1 and 2. The enclosed
inspection report (IR) presents the inspection results, which were discussed on January 25,
2013, with you and other members of your staff.
This inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed
personnel.
This report documents two NRC identified findings and one self-revealing finding of very low
safety significance (Green). Additionally, NRC inspectors identified two traditional enforcement
Severity Level IV violations. These findings were determined to involve violations of NRC
requirements. However, because of the very low safety significance and because all the
violations are entered into your correction action program (CAP), the NRC is treating the
findings as a non-cited violations (NCVs) consistent with Section 2.3.2 of the NRCs
Enforcement Policy. If you contest any NCV in this report, you should provide a response
within 30 days of the date of this IR, with the basis for your denial, to the Nuclear Regulatory
Commission, ATTN.: Document Control Desk, Washington, D.C. 20555-0001; with copies to
the Regional Administrator Region I; the Director, Office of Enforcement, U. St. Nuclear
Regulatory Commission, Washington, D.C. 20555-0001; and the NRC Resident Inspector at the
Susquehanna Steam Electric Station. In addition, if you disagree with the cross-cutting aspect
of any finding in this report, you should provide a response within 30 days of the date of this IR,
with the basis for your disagreement, to the Regional Administrator, Region I, and the NRC
Resident Inspectors at the SSES.
T. Rausch 2
In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, 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
NRCs 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,
/RA/
Mel Gray, Chief
Reactor Projects Branch 4
Division of Reactor Projects
Docket Nos. 50-387; 50-388
Enclosures: Inspection Report 05000387/2012005 and 05000388/2012005
w/Attachment: Supplemental Information
cc w/encl: Distribution via ListServ
Non-Sensitive Publicly Available
SUNSI Review
Sensitive Non-Publicly Available
OFFICE RI/DRP RI/DRP RI/DRP
NAME PFinney/AAR for ARosebrook/AAR MGray/MG
DATE 02/ 12 /13 02/12 /13 02/ 13 /13
1
U.S NUCLEAR REGULATORY COMMISSION
REGION I
Docket No: 50-387, 50-388
Report No: 05000387/2012005 and 05000388/2012005
Licensee: PPL Susquehanna, LLC (PPL)
Facility: Susquehanna Steam Electric Station, Units 1 and 2
Location: Berwick, Pennsylvania
Dates: October 1, 2012 through December 31, 2012
Inspectors: P. Finney, Senior Resident Inspector
J. Greives, Resident Inspector
R. Edwards, Acting Resident Inspector
A. Rosebrook, Senior Project Engineer
J. Richmond, Senior Reactor Inspector
J. Furia, Senior Health Physicist
J. Caruso, Senior Operations Engineer
A. Bolger, Reactor Engineer
R. Rolph, Health Physicist
C. Lally, Operations Engineer
Approved By: Mel Gray, Chief
Reactor Projects Branch 4
Division of Reactor Projects
Enclosure
2
TABLE OF CONTENTS
SUMMARY OF FINDINGS ........................................................................................................... 3
REPORT DETAILS ....................................................................................................................... 6
1. REACTOR SAFETY ................................................................................................................. 6
1R01 Adverse Weather Protection ................................................................................... 6
1R04 Equipment Alignment ............................................................................................... 7
1R05 Fire Protection .......................................................................................................... 8
1R11 Licensed Operator Requalification Program ......................................................... 10
1R12 Maintenance Effectiveness ................................................................................... 11
1R13 Maintenance Risk Assessments and Emergent Work Control .............................. 16
1R15 Operability Determinations and Functionality Assessments .................................. 17
1R19 Post-Maintenance Testing ..................................................................................... 18
1R20 Refueling and Other Outage Activities .................................................................. 18
1R22 Surveillance Testing .............................................................................................. 20
1EP6 Drill Evaluation ...................................................................................................... 20
2. RADIATION SAFETY ............................................................................................................. 23
2RS6 Radioactive Gaseous and Liquid Effluent Treatment ............................................ 23
2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage,
and Transportation ................................................................................................ 28
4. OTHER ACTIVITIES .............................................................................................................. 30
4OA1 Performance Indicator Verification ......................................................................... 30
4OA2 Problem Identification and Resolution ................................................................... 32
4OA3 Follow-up of Events and Notices of Enforcement Discretion ................................ 47
4OA5 Other Activities ....................................................................................................... 51
4OA6 Meetings, Including Exit ......................................................................................... 54
4OA7 Licensee-Identified Violations ................................................................................. 54
ATTACHMENT: SUPPLEMENTAL INFORMATION.................................................................. 54
SUPPLEMENTAL INFORMATION ........................................................................................... A-1
KEY POINTS OF CONTACT .................................................................................................... A-1
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED ........................................................ A-2
LIST OF DOCUMENTS REVIEWED ....................................................................................... A-3
LIST OF ACRONYMS ............................................................................................................. A-13
Enclosure
3
SUMMARY OF FINDINGS
IR 05000387/2012005, 05000388/2012005 10/01/2012 - 12/31/2012; Susquehanna Steam
Electric Station, Units 1 and 2; Maintenance Effectiveness, Drill Evaluation, Problem
Identification and Resolution, Follow-up of Events and Notices of Enforcement Discretion.
The report covered a three-month period of inspection by resident inspectors and announced
inspections performed by regional inspectors. Inspectors identified two Severity Level IV non-
cited violations (NCVs) and three NCVs of very low safety significance (Green). The
significance of most findings is 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 (SDP), dated June 2, 2011. Cross-cutting aspects are determined
using IMC 0310, Components Within Cross-Cutting Areas, dated October 28, 2011. All
violations of NRC requirements are dispositioned in accordance with the NRCs Enforcement
Policy, dated June 7, 2012. The NRCs program for overseeing the safe operation of
commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process,
Revision 4.
Cornerstone: Initiating Events
Green. A self-revealing Green NCV of 10 CFR 50 Appendix B, Criteria III, Design Control,
was identified related to a leak on the Unit 1 A reactor recirculation pump suction line
decontamination flange weld. Specifically, PPL personnel used an incorrect value for stress
intensification factor in the vibration analysis in 2004 to support an extended power uprate
(EPU). When the correct stress intensification factor was applied, American Society of
Mechanical Engineers (ASME) OM-3 code limits for endurance and fatigue stress were
exceeded. The weld failure resulted in pressure boundary leakage in excess of TS 3.4.4
limits from approximately June 16 through 19, 2012. PPL staff entered the problem in the
PPL corrective action program (CAP) as CR 1589390, repaired and modified the flange line,
and revised the calculation.
The inspectors reviewed the performance deficiency using NRC IMC 0612, Appendix B,
Issue Screening, and determined to be more than minor because it affected the Initiating
Events cornerstone attribute of design control. The issue adversely affected the associated
cornerstone objective of limiting the likelihood of those events that upset plant stability and
challenge critical safety functions during shutdown as well as power operations. The finding
was evaluated using Section A of IMC 609, Appendix A, Exhibit 1, Initiating Events
Screening Questions. Since the finding result could not have reasonably exceeded the
leak rate for a small loss of coolant accident (LOCA) and did not likely affect other systems
used to mitigate a LOCA resulting in a total loss of their function (e.g., inter-facing system
LOCA), the finding screened to very low safety significance (Green). This finding was
determined to not be indicative of current performance because the deficiency occurred in
2004 and procedures and training are in place that would have precluded the issue.
Therefore, no cross-cutting aspect is assigned. (Section 4OA2)
Enclosure
4
Cornerstone: Mitigating Systems
Green. Inspectors identified a Green NCV of 10 CFR 50.65(a)(2) for PPL staff not
demonstrating that the performance of the Unit 2 125 volt direct-current (VDC) system was
being effectively controlled through appropriate preventive maintenance. Specifically, PPL
did not properly classify a functional failure of the Unit 2 125 VDC system on November 23,
2011 as maintenance preventable until prompted by questions from the inspectors.
Consequently, PPL staff declared the functional failure as maintenance preventable,
determined a maintenance rule performance criteria was exceeded and moved the Unit 2
125 VDC system from a(2) to (a)(1) status in order to establish goals and monitoring as
required by 10 CFR 50.65. PPL staff entered this issue in their CAP as CRs 1496655 and
1643158.
This finding was more than minor because it was associated with the Equipment
Performance attribute of the Mitigating System cornerstone, and adversely affected the
cornerstone objective of ensuring the availability, reliability and capability of systems that
respond to initiating events to prevent undesirable consequences. Additionally, this finding
was similar to example 7.d of IMC 0612, Appendix E. Using Section A of Exhibit 2 of NRC
IMC 0609 Appendix A, The Significance Determination Process (SDP) for Findings At-
Power, inspectors determined this finding was of very low safety significance (Green)
because the finding did not represent an actual loss of function of one or more non-TS trains
of equipment designated as high safety-significant in accordance with PPLs maintenance
rule program for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The inspectors determined that this finding had a
cross-cutting aspect in the area of Problem Identification and Resolution (PI&R), CAP,
because PPL staff did not thoroughly evaluate the Unit 2 125 VDC system functional failure
such that the resolution addressed the cause to include proper classification. The inspectors
determined that PPL staff not thoroughly evaluating the maintenance preventable aspects of
a functional failure was due to the CAP process evaluation not fully addressing the cause
such that appropriate classification under the maintenance rule could be made P.1(c)
(Section 1R12).
Cornerstone: Emergency Preparedness
Green. Inspectors identified a Green NCV associated with emergency preparedness
planning standard 10 CFR 50.47(b)(14) and the requirements of Section lV.F.2.g of
10 CFR 50, Appendix E. Specifically, PPL personnel did not identify an Emergency
Response Organization (ERO) performance weakness associated with an untimely
notification of an emergency declaration during their critique following the full-scale
emergency preparedness (EP) drill. In the case of ERO performance, simulator equipment
issues prevented the ability of drill controllers to satisfactorily evaluate performance of the
ERO and PPL staff did not identify that all off-site response organizations (OROs)
were not notified within fifteen minutes. The critique deficiency was entered into PPLs CAP
as CR 1648380.
The finding is more than minor because it is associated with the ERO attribute of the
Emergency Preparedness cornerstone and affected the cornerstone objective to ensure that
PPL staff are capable of implementing adequate measures to protect the health and safety
of the public in the event of a radiological emergency. The inspectors assessed the issue,
related to the failure to make a timely notification to the OROs, using NRC IMC 0609
Appendix B, Emergency Preparedness Significance Determination Process. PPL's drill
critique not identifying the untimely notification met the NRC's definition of a weakness in a
Enclosure
5
full-scale drill. However, because of the unique nature of the equipment failures associated
with the notification of the first ORO, inspectors determined that the failure to critique the drill
weakness only constituted a degradation of the planning standard (PS) function. Therefore
the finding is characterized as very low safety significance (Green). The finding is related
to the cross-cutting area of PI&R, CAP, in that PPL staff did not identify a risk significant
planning standard (RSPS) performance issue completely, accurately, and in a timely
manner commensurate with the safety significance. Specifically, during the critique of the
full-scale drill conducted on October 14, 2012, PPL staff did not recognize and critique that
an RSPS was not met and did not place this issue into the CAP until prompted by
inspectors. P.1(a) (Section 1EP6)
Cornerstone: Miscellaneous
Severity Level IV. Inspectors identified a SL IV NCV of 10 CFR 50.73 (a)(2)(vii) for PPLs
failure to submit a licensee event report (LER) of a common cause inoperability of two
independent trains of reactor protection system (RPS) electrical power monitoring
associated with several Unit 1 RPS breakers on May 8, 2012. PPL staff entered the issue
into the CAP as CR 1663785 and took action to issue the required LER.
This finding was evaluated using the traditional enforcement process because the failure to
accurately report events has the potential to impact or impede the regulatory process. The
finding was determined to be a Severity Level IV violation based on example 6.9.d.9 of the
NRC Enforcement Policy. This example states that a licensee failing to make a report
required by 10 CFR 50.72 or 10 CFR 50.73 is an example of a Severity Level IV violation.
Because this violation involves the traditional enforcement process and does not have an
underlying technical violation that would be considered more-than-minor, inspectors did not
assign a cross-cutting aspect to this violation in accordance with IMC 0612, Appendix B.
(Section 1R12)
Severity Level IV. The inspectors identified a SL IV NCV of 10 CFR 50.72(b)(3)(iv)(A) and
(B) when PPL operators did not report a valid actuation of the Unit 2 RPS on November 9,
2012 within eight hours of occurrence as required. The concern was entered into PPLs
CAP as CR 1643096 and an Emergency Notification System (ENS) report was submitted
restoring compliance.
This finding was evaluated using the traditional enforcement process because the failure to
accurately report events has the potential to impact or impede the regulatory process. The
finding was determined to be a Severity Level IV violation based on example 6.9.d.9 of the
NRC Enforcement Policy. This example states that a licensee failing to make a report
required by 10 CFR 50.72 or 10 CFR 50.73 is an example of a Severity Level IV violation.
Because this violation involves the traditional enforcement process and does not have an
underlying technical violation that would be considered more-than-minor, inspectors did not
assign a cross-cutting aspect to this violation in accordance with IMC 0612, Appendix B.
(Section 4OA3)
Enclosure
6
REPORT DETAILS
Summary of Plant Status
Unit 1 began the inspection period at or near 100 percent power. On October 2, 2012,
operators reduced Unit 1 to 85 percent power to address potential problems with some low
pressure (LP) turbine blades consistent with their adverse condition monitoring plan (ACMP).
On October 6, Unit 1 was further reduced to 65 percent power in accordance with the ACMP.
On October 8, the ACMP supported a Unit 1 power increase to 75 percent. Unit 1 was shut
down from 75 percent power on October 19 and reached Mode 4 the following day in support of
a maintenance outage for the LP turbine blades. A reactor startup commenced on November 6,
and Unit 1 reached 100 percent power on November 12. Operators reduced Unit 1 power to 70
percent power on December 7, for a control rod sequence exchange and scram time testing.
Unit 1 returned to 100 percent power on December 9. On December 14, operators reduced
Unit 1 power to approximately 79 percent power in response to entry into TS 3.0.3, for problems
with both control room chilling units. After restoring a control room chiller, operators restored
Unit 1 to 100 percent later that day and remained at 100 percent for the remainder of the
inspection period.
Unit 2 began the inspection period at or near 100 percent power. On October 2, operators
reduced Unit 2 to 85 percent power to address potential problems with some low pressure (LP)
turbine blades consistent with their ACMP. On October 6, Unit 2 was further reduced to 65
percent power in accordance with the ACMP to mitigate potential degradation of LP turbine
blades in accordance with the ACMP. On October 8, the ACMP supported a Unit 2 power
increase to 75 percent. On November 9, operators manually scrammed Unit 2 due to a failure of
the integrated control system (ICS). Unit 2 remained shutdown for a maintenance outage on LP
turbine blades and reached Mode 4 on November 11. On November 18, operators commenced
a Unit 2 reactor startup. On November 19, operators placed the Unit 2 main turbine on the grid,
but commenced a reactor shutdown due to an electro-hydraulic control (EHC) fluid leak on a
main turbine bypass valve. Unit 2 reached Mode 4 on November 21. Operators commenced a
Unit 2 reactor startup on November 25, and reached approximately 10 percent power when
another EHC leak was identified. Operators shutdown Unit 2 and reached Mode 4 on November
26. Operators commenced a Unit 2 reactor startup on November 28, and reached 100 percent
power on December 3. On December 14, operators reduced Unit 2 to approximately 79 percent
power in response to entry into TS 3.0.3 for problems with both control room chilling units. After
restoring a control room chiller, operators restored Unit 2 to 100 percent later that day. On
December 16, an automatic reactor scram occurred during testing of the main turbine control
valves and Unit 2 entered Mode 3. On December 18, operators commenced a Unit 2 reactor
startup. On December 19, Unit 2 automatically scrammed at approximately 18 percent power
during a feedwater system mode shift. Operators commenced a Unit 2 reactor startup on
December 26, and reached approximately 90 percent power at the end of the inspection period.
1. REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection (71111.01 - 2 samples)
.1 Readiness for Imminent Adverse Weather Conditions
Enclosure
7
a. Inspection Scope
The inspectors reviewed PPLs preparations in advance of and during warnings and
advisories issued by the National Weather Service. The inspectors performed
walkdowns of areas that could be potentially impacted by the weather conditions,
such as the emergency and station blackout (SBO) diesel generators (DGs), station
transformers, and switchyards, and verified that station personnel secured loose
materials staged for outside work prior to the forecasted weather. The inspectors
verified that PPL staff monitored the approach of adverse weather according to
applicable procedures and took appropriate actions as required. The inspectors
reviewed the Updated Final Safety Analysis Report (UFSAR), Technical Specifications
(TSs) control room logs, and the CAP to determine what temperatures or other seasonal
weather could challenge these systems, and to ensure PPL personnel had adequately
prepared for these challenges. The inspectors reviewed station procedures, including
PPLs seasonal weather preparation procedure and applicable operating procedures.
Documents reviewed for each section of this IR are listed in the Attachment.
Common, preparations for Hurricane Sandy
b. Findings
No findings were identified.
.2 Readiness for Seasonal Extreme Weather Conditions
a. Inspection Scope
The inspectors performed a review of PPLs readiness for the onset of seasonal low
temperatures. The review focused on the condensate system and the Engineering
Safeguards Service Water (ESSW) pump house. The inspectors reviewed the UFSAR,
TSs, control room logs, and the CAP to determine what temperatures or other seasonal
weather could challenge these systems, and to ensure PPL personnel had adequately
prepared for these challenges. The inspectors reviewed station procedures, including
PPLs seasonal weather preparation procedure and applicable operating procedures.
The inspectors performed walkdowns of the selected systems to ensure station
personnel identified issues that could challenge the operability of the systems during
cold weather conditions. Documents reviewed for each section of this IR are listed in
the Attachment.
Common, winter preparations
b. Findings
No findings were identified.
1R04 Equipment Alignment
.1 Partial System Walkdowns (71111.04Q - 3 samples)
a. Inspection Scope
Enclosure
8
The inspectors performed partial walkdowns of the following systems:
Unit 2, Division II residual heat removal (RHR) during C emergency diesel
generator (EDG) inoperability
Common, 13.8 kilovolts (kV) offsite power during startup transformer T20 outage
Common, B emergency service water (ESW)
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 UFSAR, TSs, work orders
(WOs), CRs, and the impact of ongoing work activities on redundant trains of equipment
in order to identify conditions that could have impacted system performance of their
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 PPL 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.
.2 Full System Walkdown (71111.04S - 1 sample)
a. Inspection Scope
On November 20, 2012, the inspectors performed a complete system walkdown of
accessible portions of the common A EDG to verify the existing equipment lineup was
correct. The inspectors reviewed operating procedures, surveillance tests, drawings,
equipment line-up check-off lists, and the UFSAR to verify the system was aligned to
perform its required safety functions. The inspectors also reviewed electrical power
availability, component lubrication, equipment cooling, and operability of support
systems. The inspectors performed field walkdowns of accessible portions of the
systems to verify system components and support equipment were aligned correctly
and operable. The inspectors examined the material condition of the components and
observed operating parameters of equipment to verify that there were no deficiencies.
Additionally, the inspectors reviewed a sample of related CRs and WOs to ensure PPL
appropriately evaluated and resolved any deficiencies.
b. Findings
No findings were identified.
1R05 Fire Protection
.1 Resident Inspector Quarterly Walkdowns (71111.05Q - 5 samples)
a. Inspection Scope
Enclosure
9
The inspectors conducted tours of the areas listed below to assess the material
condition and operational status of fire protection features. The inspectors verified
that PPL controlled combustible materials and ignition sources in accordance with
administrative procedures. The inspectors verified that fire protection and suppression
equipment was available for use as specified in the area pre-fire plan, and passive fire
barriers were maintained in good material condition. The inspectors also verified that
station personnel implemented compensatory measures for out of service, degraded, or
inoperable fire protection equipment, as applicable, in accordance with procedures.
Unit 1, lower relay room (Fire Zone 0-24D) on December 12, 2012
Unit 1, lower cable spreading room, (Fire Zone 0-25E) on December 12, 2012
Unit 2, heat exchanger and pump access area (Fire Zone 2-3A) on October 23, 2012
Unit 2, containment access area (Fire Zone 1-4A-N, S, W) on November 9, 2012
Unit 2, high pressure coolant injection (HPCI) and reactor core isolation cooling
(RCIC) pump rooms (Fire Zones 2-1C, 2-1D) on December 17, 2012
b. Findings
No findings were identified.
.2 Fire Protection - Drill Observation (71111.05A - 1 sample)
a. Inspection Scope
The inspectors observed unannounced fire drills conducted on September 17 and
October 17, 2012, which involved fires in the Unit 1 EHC room and Unit 1 Remote
Shutdown room. The inspectors evaluated the readiness of the plant fire brigade to
fight fires. The inspectors verified that PPL personnel identified deficiencies, openly
discussed them in a self-critical manner at debriefs, and took appropriate corrective
actions as required. The inspectors evaluated specific attributes as follows:
Proper wearing of turnout gear and self-contained breathing apparatus (SCBA)
Proper use and layout of fire hoses
Employment of appropriate fire-fighting techniques
Sufficient fire-fighting equipment brought to the scene
Effectiveness of command and control
Search for victims and propagation of the fire into other plant areas
Smoke removal operations
Utilization of pre-planned strategies
Adherence to the pre-planned drill scenario
Drill objectives met
The inspectors also evaluated the fire brigades actions to determine whether these
actions were in accordance with PPLs fire-fighting strategies.
b. Findings
No findings were identified.
Enclosure
10
1R11 Licensed Operator Requalification Program (71111.11 - 4 samples)
.1 Quarterly Review of Licensed Operator Requalification Testing and Training
a. Inspection Scope
The inspectors observed licensed operator requalification examinations on October 10,
2012. The inspectors evaluated operator performance during the simulated event and
verified completion of risk significant operator actions, including the use of abnormal and
emergency operating procedures (EOPs). The inspectors assessed the clarity and
effectiveness of communications, implementation of actions in response to alarms and
degrading plant conditions, and the oversight and direction provided by the control room
supervisor. The inspectors verified the accuracy and timeliness of the emergency
classification made by the shift manager and the TS action statements entered by the
shift technical advisor. Additionally, the inspectors assessed the ability of the crew and
training staff to identify and document crew performance problems.
b. Findings
No findings of significance were identified.
.2 Quarterly Review of Licensed Operator Performance in the Main Control Room
a. Inspection Scope
The inspectors observed operator performance in the main control room during the
evolutions listed below. The inspectors observed infrequently performed test or
evolution briefings, pre-shift briefings, and reactivity control briefings to verify that the
briefings met the criteria specified in PPLs Operations Section Expectations Handbook
and PPLs Administrative Procedure OP-AD-004, Operations Standards for Error and
Event Prevention, Revision 25. Additionally, the inspectors observed test performance
to verify that procedure use, crew communications, and coordination of activities
between work groups similarly met established expectations and standards.
Unit 1, reactor shutdown for a maintenance outage on October 20, 2012 and
subsequent startup on November 6, 2012
Unit 2, operator response to reactor pressure vessel stratification on November 10,
2012
b. Findings
No findings were identified.
.3 Annual Review of Pass/Fail Results for Licensed Operator Requalification Exams
a. Inspection Scope
On December 6, 2012, NRC region-based inspectors conducted an in-office review of
results of PPL-administered annual operating tests and comprehensive written
examinations for 2012. The inspection assessed whether pass rates were consistent
Enclosure
11
with the guidance of NRC IMC 0609, Appendix I, Operator Requalification Human
Performance SDP. The inspectors verified that:
Crew pass rates were greater than 80 percent. (Pass rate was 100 percent)
Individual pass rates on the written examination were greater than 80 percent.
(Pass rate was 95.1 percent)
Individual pass rates on the job performance measures of the operating examination
were greater than 80 percent. (Pass rate was 100 percent)
Individual pass rates on the dynamic simulator test were greater than 80 percent.
(Pass rate was 93.4 percent)
Overall pass rate among individuals for all portions of the examination was greater
than or equal to 80 percent. (Overall pass rate was 90.2 percent)
b. Findings
No findings were identified.
1R12 Maintenance Effectiveness (71111.12 - 5 samples)
a. Inspection Scope
The inspectors reviewed the samples listed below to assess the effectiveness of
maintenance activities on structures, systems and components (SSCs) performance
and reliability. The inspectors reviewed system health reports, CAP documents,
maintenance WOs, and maintenance rule basis documents to ensure that PPL was
identifying and properly evaluating performance problems within the scope of the
maintenance rule. For each sample selected, the inspectors verified that the SSC was
properly scoped into the maintenance rule in accordance with 10 CFR 50.65 and verified
that the (a)(2) performance criteria established by PPLs staff was reasonable. As
applicable, for SSCs classified as (a)(1), the inspectors assessed the adequacy of goals
and corrective actions to return these SSCs to (a)(2). Additionally, the inspectors
ensured that PPLs staff was identifying and addressing common cause failures that
occurred within and across maintenance rule system boundaries.
Unit 1, RPS electrical power monitoring assembly failures on May 8, 2012
Unit 1, nuclear instrumentation (NI) equipment challenges during maintenance
shutdown from October 20 through November 6, 2012
Unit 2, rod position information system (RPIS) relay card failures on July 25,
August 8, and August 9, 2012
Common, ESW pinhole leaks on November 26 and November 28, 2012
Unit 2, RCIC inverter trip while placing 125V DC system in equalize charge on
November 23, 2011
b. Findings
.1 Introduction. Inspectors identified a Green NCV of 10 CFR 50.65(a)(2) for PPL staff not
demonstrating the performance of the Unit 2 125 VDC system was being effectively
controlled through appropriate preventive maintenance. Specifically, PPL staff did not
properly classify a functional failure of the Unit 2 125 VDC system on November 23,
2011 as maintenance preventable until prompted by questions from the inspectors.
Enclosure
12
Consequently, PPL staff declared the functional failure as maintenance preventable,
determined that a maintenance rule performance criteria was exceeded and moved the
Unit 2 125 VDC system from a(2) to (a)(1) status to establish goals and monitoring as
required by 10 CFR 50.65.
Description. On November 23, 2011, PPL operators placed the Unit 2 D 125 VDC
system battery charger to equalize as a standard maintenance practice after adding
water to a battery to maintain adequate electrolyte level. Immediately after placing the
battery charger in equalize, the main control room received alarms related to the Unit 2
RCIC system. In accordance with the alarm response procedure, PPL operators
confirmed that the RCIC inverter was de-energized. With the RCIC inverter de-
energized, there was no control power to the RCIC flow controller, and PPL operators
declared the RCIC system inoperable and unavailable. PPL staff further investigated
and determined that the D battery charger equalize voltage was not within the criteria
of 138 to 141 volts, as discussed in OP-202-001, 125V DC System, Section 2.4.
Subsequently, the D battery charger was placed to float and the RCIC inverter
immediately reset. PPL staff determined that the RCIC inverter tripped on the high
voltage setpoint during equalize charging of the D battery charger. RCIC was
unavailable for a total of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 16 minutes prior to the automatic reset of the
inverter.
On March 28, 2012, PPL Engineering completed the ACE (CR 1496655), which
concluded that the November 23, 2011 issue was a maintenance rule function failure
(MRFF) of the 125 VDC system. This function is defined in the Maintenance Rule Basis
Document as the ability to energize channel A of the class 1E 125 VDC system. The
ACE also determined that the MRFF was not a maintenance preventable functional
failure (MPFF) because adequate tasks were already in place to identify and correct
setpoint drift of the RCIC inverter high voltage trip setpoint via a biennial calibration. On
October 25, 2012, PPLs Maintenance Rule Expert Panel (MREP) reviewed the Unit 2
125 VDC system functional failure and agreed with the MRFF and MPFF determinations
in the ACE.
The inspectors performed a review of the MRFF issue, including the ACE, the Expert
Panel meeting minutes, procedures NDAP-QA-0413, Maintenance Rule Program, and
OP-202-001, 125V DC System, Unit 2 RCIC inverter calibration data history, and
discussed the issue with PPL engineers and the Maintenance Rule Coordinator. PPL
staff had determined that an apparent cause of the Unit 2 RCIC inverter high voltage trip
was attributed to inadequate design margin between the operating range of the battery
chargers and the shutdown setpoint of the RCIC inverters. The ACE indicated that when
the charger is switched from float to equalize, the sudden change in potential to the
battery causes an initial voltage overshoot by the charger. The ACE also indicated that
the RCIC system Topaz-style inverters have exhibited up to a three-volt setpoint drift
decrease in the high voltage trip setpoint during routine as-found calibration testing. The
inspector review of historical as-found calibration data for a sample of PPLs Topaz-style
inverters found up to a six-volt setpoint decreasing drift. The inspectors determined that
PPLs operating experience review for Topaz-style inverter trips as a result of placing
batter chargers in equalize was appropriate, and noted that several examples were
identified, including past examples at Susquehanna. Corrective action item number 4 of
the ACE, which addressed the apparent cause, performed a change to the 125 VDC
system procedure to perform a quarter-turn decreasing voltage adjustment of the battery
charger equalizing potentiometer just prior to taking the switch from float to equalize.
Enclosure
13
The inspectors noted that NDAP-QA-0413, Maintenance Rule Program, step 7.4.2.b,
contains specific guidance that MRFFs due to incorrect maintenance procedures are
Ultimately, the inspectors determined that the ACEs apparent cause incorrectly
described the failure as inadequate design margin with respect to the operating voltage
range of the battery chargers. Despite this, the inspectors concluded that the corrective
actions were appropriate. Specifically, revising the system procedural steps for placing
the battery on an equalizing charge, during a maintenance activity, ensured the
equipment was maintained and operated within the low design margin. The inspectors
determined that had the apparent cause been more accurately described, the evaluator
could have reasonably concluded that the MRFF was maintenance preventable, or the
MREP would have had sufficient information to challenge the MRFF classification.
The inspectors questioned PPL staff regarding the determination documented in the
ACE and confirmed by October 25, 2012 MREP, that the 125 VDC system functional
failure was not maintenance preventable. Specifically, the inspectors questioned
whether the November 23, 2011 action to place the Unit 2 D battery charger to equalize
would have been considered implementation of an incorrect maintenance procedure,
since the procedure was changed as a corrective action to address the apparent cause
of the problem. The inspectors also questioned whether PPLs staff were performing the
RCIC inverter calibration at a proper frequency to address the as-found calibration
testing examples of high voltage trip setpoint drift.
On December 13, 2012, PPL staff performed a second Maintenance Rule Expert Panel
review of the Unit 2 125 VDC system MRFF to consider the potential maintenance
preventable aspects, as identified by the inspectors. PPL staff determined that
additional changes to the 125 VDC system procedure would be appropriate, to provide
guidance on promptly switching the charger from equalize back to float to promptly
restore the RCIC inverter in the event of an inverter trip on high voltage, thereby
minimizing the duration of any adverse impact on the RCIC system. Based on the
maintenance preventable aspects associated with the Unit 2 125 VDC system steps
prior to the procedure changes, PPL staff determined that the MRFF did constitute a
MPFF. PPL staff determined that because the Unit 2 125 VDC system was scoped as a
high safety significant system under the Maintenance Rule, the system would be moved
from (a)(2) to (a)(1) per procedure NDAP-QA-0413, step 7.4.3.c. PPL staff determined
that an (a)(1) action plan would be developed under the original CR. Regarding the
examples of RCIC inverter as-found high voltage setpoint drift, PPL staff evaluated a
broad scope of historical data and determined that there was no obvious trend of low
setpoint drift. PPL staff did acknowledge that low setpoint drift could have contributed to
the MRFF and created an action to obtain the as-found data in the next two-year
calibration under WO 1434638 (ACE item 6). PPL staff entered these items in their CAP
under CRs 1496655 and 1643158.
The inspectors noted that NDAP-QA-0413, steps 4.7.4.a and step 4.8.2.a require that
MRFFs shall be presented to the Expert Panel within 60 days of the failure date. Step
7.1.4 allows for the control of extensions relative to the 60-day requirement and states
that extensions are controlled to ensure that the determination of (a)(1) classification
meets timeliness requirements. The inspectors questioned PPL staff on the
approximate 11-month gap between the November 23, 2011 MRFF and the October 25,
2012 initial expert panel review. PPL staff stated that this delay was attributed to a high
Enclosure
14
backlog of functional failures for expert panel review. See section 4OA2.2 of this
inspection report for further discussion of this adverse trend.
Additionally, inspectors noted that NDAP-QA-0413, section 7.1.3 states that CRs
involving MRFFs shall, as a minimum, be assigned the Apparent Cause evaluation type
defined in NDAP-QA-0702, Action Request and CR Process. Section 7.2.2 of NDAP-
QA-0413, which describes the requirements for processing MRFF CR evaluation reports
as it applies to the Maintenance Rule, states that the responsible system engineer shall
ensure that the CR evaluation report contains a determination of whether the failure
was/was not maintenance preventable and that this must be consistent with the
cause(s) of the failure. Based on this requirement, inspectors determined that the
ACE did not appropriately evaluate the issue to ensure the functional failure was
classified as maintenance preventable.
Analysis. The inspectors determined that PPL staff did not demonstrate performance of
the Unit 2 125 VDC system was being effectively controlled through the appropriate
preventive maintenance. Specifically, PPL staff did not properly classify a functional
failure of the Unit 2 125 VDC system as maintenance preventable, which when
appropriately classified, required establishing goals and monitoring the Unit 2 125 VDC
system in accordance with 10 CFR 50.65(a)(1). This finding was more than minor
because it was associated with the Equipment Performance attribute of the Mitigating
System cornerstone, and adversely affected the cornerstone objective of ensuring the
availability, reliability and capability of systems that response to initiating events to
prevent undesirable consequences. Additionally, this finding was similar to IMC 0612
Appendix E example 7.d. Specifically, PPL staff determined, based on inspector-
identified issues of concern, that equipment performance problems were such that
effective control of performance through appropriate preventive maintenance of the 125
VDC system under 10 CFR 50.65(a)(2) could not be demonstrated. The inspectors
evaluated this finding using Section A of Exhibit 2 of NRC IMC 0609 Appendix A, The
Significance Determination Process (SDP) for Findings At-Power, and determined this
finding was of very low safety significance (Green) because the finding did not represent
an actual loss of function of one or more non-TS trains of equipment designated as high
safety-significant in accordance with PPLs maintenance rule program for greater than
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The inspectors determined that this finding had a cross-cutting aspect in the area of
PI&R, CAP, because PPL staff did not thoroughly evaluate the Unit 2 125 VDC system
functional failure such that the resolution addressed the cause, to include proper
classification. Specifically, PPLs ACE identified and addressed 125 VDC system
procedural deficiencies. However, it did not consider the procedural deficiencies in the
MPFF determination until prompted by the inspectors questions. The inspectors
determined that PPLs failure to thoroughly evaluate the maintenance preventable
aspects of a functional failure was the result of a CAP failure to address the cause such
that appropriate classification under the maintenance rule could be made P.1(c).
Enforcement. 10 CFR 50.65(a)(1) requires, in part, that holders of an operating license
shall monitor the performance or condition of SSCs within the scope of the monitoring
programs as defined in 10 CFR 50.65(b) against licensee-established goals, in a manner
sufficient to provide reasonable assurance that such SSCs are capable of fulfilling their
intended functions. 10 CFR 50.65 (a)(2) requires, in part, that monitoring as specified in
10 CFR 50.65(a)(1) is not required where it has been demonstrated that the
performance or condition of an SSC is being effectively controlled through the perfor-
Enclosure
15
mance of appropriate preventive maintenance, such that the SSC remains capable of
performing its intended function. Contrary to the above, PPL staff did not demonstrate
that performance of the Unit 2 125 VDC system was being effectively controlled through
the performance of appropriate preventive maintenance in that an MPFF of 125 VDC
occurred on November 23, 2011. PPLs ACE determined the failure was not
maintenance preventable, a determination that was accepted at the October 25, 2012
maintenance rule expert panel meeting. This determination resulted in PPL staff not
placing the Unit 2 125 VDC system under 10 CFR 50.65(a)(1) for establishing goals and
monitoring against the goals until December 13, 2012 when the system was placed in
a(1) status. This violation is being treated as an NCV, consistent with section 2.3.2 of
the NRC Enforcement Policy because it was of very low safety significance and has
been entered into PPLs CAP under CRs 1496655 and 1643158. (NCV 05000388/
2012005-01, Failure to Demonstrate Effective Preventive Maintenance Under
50.65(a)(2))
.2 Introduction. Inspectors identified a SL IV NCV of 10 CFR 50.73 (a)(2)(vii) for PPL staff
not submitting an LER within 60 days of discovery of a common cause inoperability of
two independent trains of RPS electrical power monitoring.
Description. 10 CFR 50.73 (a)(2)(vii) requires, in part, that licensees submit an LER for
any event where a single cause or condition caused two independent trains or channels
to become inoperable in a single system designed to shut down the reactor within 60
days of discovering the event.
On May 8, 2012, three of eight RPS electrical power monitoring assemblies (EPA
breakers) did not trip open as required during TS required surveillance testing on Unit 1.
TS 3.3.8.2 requires two RPS EPA breakers to be operable for each in-service RPS
motor generator set or alternate power supply. The function of the breakers is to open
on under-voltage, over-voltage, or under-frequency conditions to prevent failures in the
safety-related RPS due to the non-safety related power supplies. Extended operation of
RPS in an under-voltage condition could result in the scram solenoids chattering and
potentially losing their pneumatic control capability, resulting in a loss of the primary
scram function. The inoperable breakers were sent to a vendor for failure analysis and
an ACE was initiated (CR 1570413).
Inspectors reviewed PPLs CAP and identified that condition report action (CRA)
1571200, which tracked the reportability follow-up determination, was closed on
September 5, 2012. PPL personnel had determined that the event was not reportable
because it did not result in a loss of safety function or condition prohibited by plant TSs.
This determination was based on completion of a past operability review (CRA 1572356)
which provided discussion that there was no evidence or past indication to support
degraded past operability prior to the point of discovery. It also discussed that, based
on which breakers were inoperable; there was no loss of safety function. Inspectors
determined that this information was sufficient and reasonable to support the condition
not being reportable as an event or condition that could have prevented fulfillment of a
safety function per 10 CFR 50.73(a)(2)(v) or as an operation or condition prohibited by
TSs per 10 CFR 50.73(a)(2)(i)(B). However, the past operability review stated that the
cause of the EPA breakers failing to trip is unknown (failed breakers have been returned
for evaluation). Based on this statement, inspectors determined that there was
insufficient evidence on September 5th to determine that the event was not reportable for
other reasons and the potential for common cause inoperability should have still been
considered.
Enclosure
16
By letter dated September 21, 2012, the vendor informed PPL staff that two of the three
breakers did not trip due to the calibration screws being out of adjustment on the under-
voltage relays (UVRs) which caused an, insufficient force balance between the torsional
spring and the plunger spring. This resulted in inadequate force being applied to trip
the breaker. Additionally, the vendor determined that, marginal calibrationover time
and cycling resulted in the UVR to lose calibration. The third breaker not tripping
could not be repeated in the laboratory and therefore its cause was indeterminate.
Inspectors reviewed the failure analysis and PPLs ACE and determined that the
condition constituted a common cause failure mode for independent trains, which
should have been reported to the NRC via an LER no later than November 20, 2012.
Analysis. The inspectors determined that PPL not reporting a common cause
inoperability of independent trains of TS required equipment was a performance
deficiency and impacted the NRCs ability to perform its regulatory function. The
finding was evaluated using the traditional enforcement process because the failure to
accurately report events has the potential to impact or impede the regulatory process.
The finding was determined to be a Severity Level IV violation based on example 6.9.d.9
of the NRC Enforcement Policy. This example states that a licensee failing to make a
report required by 10 CFR 50.72 or 10 CFR 50.73 is an example of a Severity Level IV
violation.
Because this violation involves the traditional enforcement process and does not have
an underlying technical violation that would be considered more-than-minor, inspectors
did not assign a cross-cutting aspect to this violation in accordance with IMC 0612,
Appendix B.
Enforcement. 10 CFR 50.73 (a)(2)(vii) requires, in part, that licensees submit an LER for
any event where a single cause or condition caused two independent trains or channels
to become inoperable in a single system designed to shut down the reactor within 60
days of discovering the event. Contrary to the above, PPL staff did not submit a report
within 60 days of September 21, 2012, after a failure analysis determined that two
independent trains of RPS electrical power monitoring were inoperable due to a common
cause or condition. PPL staff entered the deficiency into their CAP as CR 1663785 and
initiated action to submit the required LER. This violation is being treated as an NCV,
consistent with Section 2.3.2 of the Enforcement Policy because it was Severity Level IV
and was entered into the PPLs CAP. (NCV 05000387/2012005-02, Failure to Report
Common-Cause Inoperability of Independent Trains)
1R13 Maintenance Risk Assessments and Emergent Work Control (71111.13 - 5 samples)
a. Inspection Scope
The inspectors reviewed station evaluation and management of plant risk for the
maintenance and emergent work activities listed below to verify that PPL staff performed
the appropriate risk assessments prior to removing equipment for work. The inspectors
selected these activities based on potential risk significance relative to the reactor safety
cornerstones. As applicable for each activity, the inspectors verified that PPL personnel
performed risk assessments as required by 10 CFR 50.65(a)(4) and that the
assessments were accurate and complete. When PPL performed emergent work, the
inspectors verified that operations personnel promptly assessed and managed plant risk.
The inspectors reviewed the scope of maintenance work and discussed the results of
Enclosure
17
the assessment with the stations probabilistic risk analyst to verify plant conditions were
consistent with the risk assessment. The inspectors also reviewed the TS requirements
and inspected portions of redundant safety systems, when applicable, to verify risk
analysis assumptions were valid and applicable requirements were met.
Unit 1, yellow risk during division II RHR minimum flow valve work
Unit 2, yellow risk during the November 9, 2012 manual reactor scram
Common, risk assessment during startup transformer T20 maintenance
Common, B EDG room temperature calibration
Common, yellow risk during B ESW flow transmitter replacement
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments (71111.15 - 6 samples)
a. Inspection Scope
The inspectors reviewed operability determinations for the following degraded or non-
conforming conditions:
Unit 1, anomalous bypass valve (BPV) indications during plant shutdown
Unit 2, elevated suction pressure on RCIC
Unit 2, reactor pressure vessel (RPV) bottom head cooldown in excess of 100°
F/hour following the November 9, 2012, reactor scram and reactor vessel
stratification
Unit 2, 2A residual heat removal service water (RHRSW) pump in-service test
failure
Common, control structure (CS) boundary leak during testing
Common, compliance with TS surveillance requirement (SR) 3.4.2.1 for jet pump
operability
The inspectors selected these issues based on the risk significance of the associated
components and systems. The inspectors evaluated the technical adequacy of the
operability determinations to assess whether TS operability was properly justified and
the subject component or system remained available such that no unrecognized
increase in risk occurred. The inspectors compared the operability and design criteria in
the appropriate sections of the TSs and UFSAR to PPLs evaluations to determine
whether the components or systems were operable. Where compensatory measures
were required to maintain operability, the inspectors determined whether the measures
in place would function as intended and were properly controlled by PPL. The
inspectors determined, where appropriate, compliance with bounding limitations
associated with the evaluations.
b. Findings
No findings were identified.
Enclosure
18
1R19 Post-Maintenance Testing (71111.19 - 7 samples)
a. Inspection Scope
The inspectors reviewed the post-maintenance tests for the maintenance activities listed
below to verify that procedures and test activities ensured system operability and
functional capability. The inspectors reviewed the test procedure to verify that the
procedure adequately tested the safety functions that may have been affected by the
maintenance activity, that the acceptance criteria in the procedure was consistent with
the information in the applicable licensing basis and/or design basis documents, and that
the procedure had been properly reviewed and approved. The inspectors also
witnessed the test or reviewed test data to verify that the test results adequately
demonstrated restoration of the affected safety functions.
Unit 1, standby liquid control (SBLC) planned maintenance
Unit 1, corrective maintenance on source range monitors (SRMs) and intermediate
range monitor (IRMs)
Unit 1, 1A reactor recirculation pump (RRP) seal replacement and motor-generator
set maintenance
Unit 2, division I core spray minimum flow valve maintenance
Unit 2, drywell cooler fan breaker repair following failure to start in slow speed
Unit 2, division II RHR planned maintenance
Common, planned maintenance on startup transformer T20
b. Findings
No findings were identified.
1R20 Refueling and Other Outage Activities (71111.20 - 2 samples)
.1 Unit 1 Maintenance Outage for Low Pressure (LP) Turbine Blade Replacement
a. Inspection Scope
The inspectors reviewed the stations work schedule and outage risk plan for the Unit 1
maintenance outage, which was conducted on October 19 through November 6, 2012.
The inspectors reviewed PPLs development and implementation of outage plans and
schedules to verify that risk, industry experience, previous site-specific problems, and
defense-in-depth were considered. During the outage, the inspectors observed portions
of the shutdown and cooldown processes and monitored controls associated with the
following outage activities:
Configuration management, including maintenance of defense-in-depth
commensurate with the outage plan for the key safety functions and compliance with
the applicable technical specifications when taking equipment out of service
Implementation of clearance activities and confirmation that tags were properly hung
and that equipment was appropriately configured to safely support the associated
work or testing
Installation and configuration of reactor coolant pressure, level, and temperature
instruments to provide accurate indication and instrument error accounting
Enclosure
19
Status and configuration of electrical systems and switchyard activities to ensure that
technical specifications were met
Monitoring of decay heat removal operations
Reactor water inventory controls, including flow paths, configurations, alternative
means for inventory additions, and controls to prevent inventory loss
Activities that could affect reactivity
Maintenance of secondary containment as required by technical specifications
Fatigue management
Tracking of startup prerequisites and startup and ascension to full power operation
Identification and resolution of problems related to refueling outage activities
b. Findings
No findings were identified.
.2 Unit 2 Maintenance Outage for LP Turbine Blade Replacement
a. Inspection Scope
The inspectors reviewed the stations work schedule and outage risk plan for the Unit 2
maintenance outage, which was conducted on November 9 through November 28, 2012.
The inspectors reviewed PPLs development and implementation of outage plans and
schedules to verify that risk, industry experience, previous site-specific problems, and
defense-in-depth were considered. The outage was commenced early due to a manual
reactor scram following an integrated control system failure. During the outage, the
inspectors observed portions of the shutdown and cooldown processes and monitored
controls associated with the following outage activities:
Configuration management, including maintenance of defense-in-depth,
commensurate with the outage plan for the key safety functions and compliance with
the applicable technical specifications when taking equipment out of service
Implementation of clearance activities and confirmation that tags were properly hung
and that equipment was appropriately configured to safely support the associated
work or testing
Installation and configuration of reactor coolant pressure, level, and temperature
instruments to provide accurate indication and instrument error accounting
Status and configuration of electrical systems and switchyard activities to ensure that
technical specifications were met
Monitoring of decay heat removal operations
Reactor water inventory controls, including flow paths, configurations, alternative
means for inventory additions, and controls to prevent inventory loss
Activities that could affect reactivity
Maintenance of secondary containment as required by technical specifications
Fatigue management
Tracking of startup prerequisites and startup and ascension to full power operation
Identification and resolution of problems related to refueling outage activities
b. Findings
No findings were identified.
Enclosure
20
1R22 Surveillance Testing (71111.22 - 4 samples)
a. Inspection Scope
The inspectors observed performance of surveillance tests and/or reviewed test data of
selected risk-significant SSCs to assess whether test results satisfied TSs, the UFSAR,
and PPL procedure requirements. The inspectors verified that test acceptance criteria
were clear, tests demonstrated operational readiness and were consistent with design
documentation, test instrumentation had current calibrations and the range and accuracy
for the application, tests were performed as written, and applicable test prerequisites
were satisfied. Upon test completion, the inspectors considered whether the test results
supported that equipment was capable of performing the required safety functions. The
inspectors reviewed the following surveillance tests:
Unit 1, RCIC comprehensive flow surveillance
Unit 2, main turbine valve testing
Unit 2, fuel pool cooling (FPC) system flow test
Unit 2, quarterly calibration of RPV pressure channels for low pressure
emergency core cooling system permissive signals
b. Findings
No findings were identified.
Cornerstone: Emergency Preparedness
1EP6 Drill Evaluation (71114.06 - 1 sample)
a. Inspection Scope
The inspectors evaluated the conduct of a routine PPL emergency drill on November 13,
2012 to identify weaknesses and deficiencies in the classification, notification, and
protective action recommendation development activities. The inspectors observed
emergency response operations in the simulator to determine whether the event
classifications, notifications, and protective action recommendations were performed in
accordance with procedures. The inspectors also attended the station drill critique to
compare inspector observations with those identified by PPL staff in order to evaluate
PPLs critique and to verify whether the PPL staff was properly identifying weaknesses
and entering them into the CAP.
Common, green team full-scale drill on November 13, 2012
b. Findings
Introduction. The NRC identified a Green NCV associated with emergency
preparedness planning standard 10 CFR 50.47(b)(14) and the requirements of Section
lV.F.2.g of 10 CFR 50 Appendix E. Specifically, PPL staff did not identify a performance
weakness related to a RSPS during their critique following the full-scale EP drill.
Description. 10 CFR 50.47(b)(14) requires that periodic drills be conducted to develop
and maintain key skills, and deficiencies identified as a result of exercises or drills be
Enclosure
21
corrected.Section IV.F.2.g of 10 CFR 50 Appendix E requires that all exercises, drills,
and training that provide performance opportunities to develop, maintain, or demonstrate
key skills include a formal critique in order to identify weak or deficient areas that need
correction. Additionally, it requires that any weaknesses or deficiencies be corrected.
On November 13, 2012, inspectors observed PPLs full-scale EP drill. In accordance
with the drill scenario, the Control Room Emergency Director declared an Unusual Event
(UE) at 8:28 a.m. Inspectors observed performance of the initial notification to offsite
response organizations (OROs). The stations emergency plan specifies three OROs
that PPL has responsibility to notify: Pennsylvania Emergency Management Agency
(PEMA), Luzerne County Emergency Management Agency (LCEMA), and Columbia
County Emergency Management Agency (CCEMA). Inspectors noted two observations
of significance with respect to performance of this notification.
First, in accordance with PPL emergency planning procedure EP-PS-126, Emergency
Plan Communicator: Emergency Plan Position Specific Instruction, Revision 28, the
communicator attempted to make contact with the OROs via a bridge line, which
simultaneously dials all three OROs, and then attempted to dial the OROs individually.
These attempts were unsuccessful because the phone had no dial tone. The lead drill
controller contacted a phone technician who restored some connectivity. It was
subsequently determined that at the start of the drill, the crew manipulated the setup of
the handset and portable headset. In doing this, the operator mistakenly disconnected
the handset that was required to be used by the communicator for ORO notifications.
The phone technician resolved this issue and the communicator was able to attempt to
continue the notification process. Again, notification via the bridge was unsuccessful
and the communicator asked the lead drill controller for guidance. The drill controller
prompted the communicator to continue with the procedure and attempt to dial the
OROs individually. This attempt was successful and the communicator made initial
contact with PEMA at 8:43 a.m., fifteen minutes after the UE declaration.
Secondly, inspectors observed that not all OROs were notified within 15 minutes of the
declared UE. Specifically, though initial contact was made with PEMA at 8:43 a.m.,
initial contact was not initiated with LCEMA and CCEMA until 22 minutes and 24 minutes
after the emergency declaration, respectively.
Inspectors observed the drill critique conducted on November 14, 2012 and noted these
deficiencies were not adequately captured. Specifically, Drill Objective 1.5 for the
control room emergency plan communicator states to perform timely notifications to
offsite authoritiesuntil relieved of this duty by the TSC and was evaluated by the
drill controllers as Met. CR 1643107 was generated stating that phone problems
challenged the ability of the emergency plan communicator to make the required
15 minute notification. However, the CR also mentioned that the notification to outside
agencies was successfully initiated just within the 15-minute time limit. Additionally,
inspectors reviewed the drill and exercise performance (DEP) PI opportunities for the
drill and noted that drill controllers evaluated the DEP PI opportunity for timely
notification of the UE as successful. There was no mention in the CR or drill critique
presentation that the second and third OROs were not notified within fifteen minutes
of the declared emergency or that equipment performance or controller intervention
potentially interfered with adequate observation of ERO performance.
Enclosure
22
For the first observation, inspectors reviewed NEI 99-02, Regulatory Assessment
Performance Indicator Guideline, Revision 6, and noted that page 46 of the guidance
states for sites with multiple agencies to notify, the notification is considered to be
initiated when contact is made with the first agency to transmit the initial notification
information. However, inspectors were concerned that the level of interaction between
the drill controller and the ERO member was sufficient to prevent adequate observation
and evaluation of performance. In particular, NEI 99-02 page 47 states that if a
controller intervenes (e.g., coaching, prompting) with the performance of an individual to
make an independent and correct classification, notification, or PAR, then that DEP PI
opportunity shall be considered a failure. In this case, inspectors determined, after
consultation with regional EP specialists, that it was incorrect for the evaluators to
determine the DEP PI opportunity was successful when controller intervention was
required to resolve the equipment failures. Inspectors reviewed the nature of the
equipment failures and determined that they were unique to the simulator such that there
was reasonable assurance the same deficiency could not exist in the plant control room
during an actual emergency.
For the second observation, inspectors determined the CR and the drill critique did not
correctly document that the crew had not met regulatory requirements associated with
notification of the second and third OROs following the emergency declaration.
Specifically, 10 CFR 50.47(b)(5) requires, in part, that procedures be established for
notification by the licensee of State and local response organizations. Additionally, 10
CFR 50, Appendix E, Section IV.D.3 requires, in part, that a licensee have the capability
to notify responsible State and local governmental agencies within 15 minutes of
declaring an emergency. IMC 0609 Appendix B classifies the function of notifying
OROs as a RSPS. This RSPS is further described in PPLs emergency plan and EP
implementing procedures and the OROs are defined as PEMA, LCEMA, and CCEMA.
Since initial notification was not made with all OROs within fifteen minutes of the
declared emergency, inspectors determined that an ERO performance deficiency
existed which was not adequately assessed and critiqued. PPL staff entered the critique
weakness into their CAP as CR 1648380.
Analysis. Inspectors determined that PPL staff not identifying a drill weaknesses related
to emergency notification during their drill critique was a performance deficiency that was
reasonably within their ability to foresee and prevent. The finding is more than minor
because it is associated with the ERO performance attribute of the EP corner-stone and
affected the cornerstone objective to ensure that the licensee is capable of implementing
adequate measures to protect the health and safety of the public in the event of a
radiological emergency. Specifically, PPL staff did not effectively identify a drill
weakness associated with an RSPS and caused a missed opportunity to identify and
correct a drill-related performance weakness.
The inspectors assessed the issue using the NRC IMC 0609 Appendix B, Emergency
Preparedness Significance Determination Process. Inspectors noted two examples
provided in IMC 0609 Appendix B table 5.14-1 that were similar to the performance
deficiency. First, an example of a loss of planning standard (PS) function occurs when
the critique process fails to identify a weakness associated with an RSPS that is
determined by the NRC to be a DEP Pl opportunity failure during a full-scale drill.
Second, an example of a degradation of PS function occurs when the critique process
fails to identify a weakness associated with a RSPS that is determined by the NRC to be
a DEP Pl successful opportunity during a full-scale drill. PPL not critiquing the untimely
Enclosure
23
notification met the NRC's definition of a weakness in a full-scale drill. However,
because of the unique nature of the equipment failures associated with the notification of
the first ORO, inspectors determined that not identifying and critiquing the drill weakness
only constituted a degradation of the PS function. Therefore the finding is characterized
as very low safety significance (Green).
The finding is related to the cross-cutting area of PI&R, CAP, in that PPL did not identify
an RSPS issue completely, accurately, and in a timely manner commensurate with the
safety significance. Specifically, during the critique of the full-scale drill conducted on
October 14, 2012, PPL staff did not recognize and critique that an RSPS was not met
and did not place this issue into the CAP until prompted by the inspectors questions.
Enforcement. 10 CFR 50.54(q)(2) requires, in part, that a licensee shall follow and
maintain the effectiveness of an emergency plan that meets the requirements in
10 CFR 50, Appendix E and, for nuclear power reactor licensees, the planning standards
of 10 CFR 50.47(b). 10 CFR 50.47(b)(14) requires, in part, that periodic drills be
conducted to develop and maintain key skills, and deficiencies identified as a result of
drills be corrected. 10 CFR Part 50, Appendix E, section lV.F.2.g requires that all
training, including drills, shall provide for formal critiques in order to identify weak or
deficient areas that need correction. Additionally, it requires that any identified
weaknesses or deficiencies be corrected.
Contrary to the above, during the November 14, 2012, critique of the November 13,
2012, Susquehanna Steam Electric Station full-scale emergency drill, PPL did not
identify performance weaknesses. Specifically, PPL did not identify that timely
notification was not made with two of the OROs as required by regulatory requirements
and the SSES Emergency Plan. Additionally, PPL evaluated a performance indicator
opportunity as a success despite drill controller action precluding satisfactory
observation of ERO performance. PPL entered the drill critique deficiency into their
CAP as CR 1648380 and initiated action to correct the performance indicator deficiency.
Because this violation is of very low safety significance (Green) and PPL entered this
into their CAP, this violation is being treated as an NCV consistent with Section 2.3.2 of
the NRC Enforcement Policy. (NCV 05000387;388/2012005-03: Failure of Full-Scale
Drill Critique to Identify an RSPS Weakness)
2. RADIATION SAFETY
Cornerstone: Occupational/Public Radiation Safety (PS)
2RS6 Radioactive Gaseous and Liquid Effluent Treatment (71124.06 - 1 sample)
a. Inspection Scope
From November 5 to 9, 2012, the inspectors verified that gaseous and liquid effluent
processing systems are maintained so radiological discharges are properly reduced,
monitored, and released. The inspectors also verified the accuracy of the calculations
for effluent releases and public doses.
The inspectors used the requirements in 10 CFR Part 20; 10 CFR 50.35(a) TSs; 10 CFR
Part 50 Appendix A - Criterion 60, Control of Release of Radioactivity to the
Enclosure
24
Environment, and Criterion 64, Monitoring Radioactive Releases; 10 CFR 50
Appendix I, Numerical Guides for Design Objectives and Limiting Condition for
Operations (LCOs) to Meet the Criterion As Low as is Reasonably Achievable (ALARA)
for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor Effluents;
10 CFR 50.75(g), Reporting and Recordkeeping for Decommissioning Planning;
40 CFR Part 141, Maximum Contaminant Levels for Radionuclides; 40 CFR Part 190,
Environmental Radiation Protection Standards for Nuclear Power Operations;
Regulatory Guide (RG) 1.109, Calculation of Annual Doses to Man from Routine
Releases of Reactor Effluents; RG 1.21, Measuring, Evaluating, Reporting Radioactive
Material in Liquid and Gaseous Effluents and Solid Waste; RG 4.1, Radiological
Environmental Monitoring for Nuclear Power Plants; RG 4.15, Quality Assurance for
Radiological Monitoring Programs; NUREG-1301 or 1302, Offsite Dose Calculation
Manual (ODCM) Guidance: Standard Radiological Effluent Controls; applicable Industry
standards; and PPL procedures required by Susquehannas TSs/ODCM as criteria for
determining compliance.
Inspection Planning and Program Reviews
Event Report and Effluent Report Reviews
The inspectors reviewed the SSES Radiological Effluent Release Reports for 2010 and
2011 to determine if the reports were submitted as required by the Offsite Dose
Calculation Manual (ODCM) and TSs. The inspectors reviewed anomalous results,
unexpected trends, and abnormal releases that were identified. The inspectors
determined if these effluent results were evaluated, were entered in the CAP, and were
adequately resolved.
The inspectors identified radioactive effluent monitor operability issues reported in
the Annual Radioactive Effluent Release Reports, and reviewed these issues and
determined if the issues were entered into the CAP and were adequately resolved.
The inspectors reviewed the SSES UFSAR descriptions of the radioactive effluent
monitoring systems, treatment systems, and effluent flow paths to identify system design
features and required functions.
The inspectors reviewed changes to the SSES station ODCM made by PPL, since the
last inspection. When differences were identified, the inspectors reviewed the technical
basis or evaluations of the change and determined whether they were technically
justified and maintained effluent releases ALARA.
The inspectors reviewed documentation to determine if any non-radioactive systems that
have become contaminated were disclosed either through an event report or the ODCM.
The inspectors reviewed selected 10 CFR 50.59 evaluations and made a determination
if any newly contaminated systems had an unmonitored effluent discharge path to the
environment. The inspectors also reviewed whether it required revisions to the ODCM
to incorporate these new pathways and whether the associated effluents were reported
in accordance with RG 1.21.
Enclosure
25
Groundwater Protection Initiative (GPI) Program
The inspectors reviewed reported groundwater monitoring results and changes to PPLs
written program for identifying and controlling contaminated spills/leaks to groundwater.
Procedures, Special Reports, and Other Documents
The inspectors reviewed licensee event reports (LERs), event reports and/or special
reports related to the effluent program issued since the previous inspection to identify
any additional focus areas for the inspection based on the scope/breadth of problems
described in these reports.
The inspectors reviewed effluent program implementing procedures, including those
associated with effluent sampling, effluent monitor set-point determinations, and dose
calculations.
The inspectors reviewed copies of third party (independent) evaluation reports of the
effluent monitoring program since the last inspection to gather insights into the
effectiveness of the program.
Walkdowns and Observations
The inspectors walked down selected components of the gaseous and liquid discharge
systems to verify that equipment configuration and flow paths align with the descriptions
in the UFSAR and to assess equipment material condition. Special attention was made
to identify potential unmonitored release points, building alterations which could impact
airborne, or liquid, effluent controls, and ventilation system leakage that communicate
directly with the environment.
The inspectors reviewed effluent system material condition surveillance records, as
applicable, for equipment or areas associated with the systems selected for review that
were not readily accessible due to radiological conditions.
The inspectors walked down filtered ventilation systems to verify there are no degraded
conditions associated with high efficiency particulate air/charcoal banks, improper
alignment, or system installation issues that would impact the performance or the
effluent monitoring capability of the effluent system.
As available, the inspectors observed selected portions of the routine processing and
discharge of radioactive gaseous effluent to verify that appropriate treatment equipment
was used and the processing activities align with discharge permits.
The inspectors determined that PPL had not made any changes to their effluent release
paths.
As available, the inspectors observed selected portions of the routine processing and
discharge of liquid waste. The inspectors verified that appropriate effluent treatment
equipment is being used and that radioactive liquid waste is being processed and
discharged in accordance with procedures.
Enclosure
26
Sampling and Analyses
The inspectors selected three effluent sampling activities, and assessed whether
adequate controls have been implemented to ensure representative samples were
obtained.
The inspectors selected three effluent discharges made with inoperable effluent
radiation monitors to verify that controls are in place to ensure compensatory sampling
is performed consistent with the TSs/ODCM and that those controls are adequate to
prevent the release of unmonitored liquid and gaseous effluents.
The inspectors determined whether the facility is routinely relying on the use of
compensatory sampling in lieu of adequate system maintenance, based on the
frequency of compensatory sampling since the last inspection.
The inspectors reviewed the results of the inter-laboratory and intra-laboratory
comparison program to verify the quality of the radioactive effluent sample analyses.
The inspectors also assessed whether the intra- and inter-laboratory comparison
program includes hard-to-detect isotopes, as appropriate.
Instrumentation and Equipment
Effluent Flow Measuring Instruments
The inspectors reviewed the methodology that PPL uses to determine the effluent stack
and vent flow rates to verify that the flow rates are consistent with TSs/ODCM and
UFSAR values. The inspectors reviewed the differences between assumed and actual
stack and vent flow rates to ensure that they do not affect the calculated results of public
dose.
Air Cleaning Systems
The inspectors assessed whether surveillance test results for TS-required ventilation
effluent discharge systems meet TS acceptance criteria.
Dose Calculations
The inspectors reviewed all significant changes in reported dose values compared to the
previous radioactive effluent release report to evaluate the factors which may have
resulted in the change.
The inspectors reviewed more than three radioactive liquid and no gaseous waste
discharge permits, as no batch releases were made, to verify that the projected doses to
members of the public were accurate and based on representative samples of the
discharge path. The inspectors reviewed the analysis of continuous releases.
The inspectors evaluated the methods used to ensure that all radionuclides in the
effluent stream source term are included, within detectability standards. The review
included the current waste stream analyses to ensure hard-to-detect radionuclides are
included in the effluent releases.
Enclosure
27
The inspectors reviewed changes in PPL methodology for offsite dose calculations since
the last inspection to verify the changes are consistent with the ODCM and RG 1.109.
The inspectors reviewed meteorological dispersion and deposition factors used in the
ODCM and effluent dose calculations to ensure appropriate dispersion/deposition factors
are being used for public dose calculations.
The inspectors reviewed the latest Land Use Census to verify changes that affect public
dose pathways have been factored into the dose calculations and environmental
sampling/analysis program.
The inspectors evaluated whether the calculated doses are within 10 CFR 50, Appendix I,
Numerical Guides for Design Objectives and Limiting Condition for Operations (LCOs) to
Meet the Criterion As Low as is Reasonably Achievable (ALARA) for Radioactive
Material in Light-Water-Cooled Nuclear Power Reactor Effluents; and TS dose criteria.
The inspectors reviewed records of any abnormal gaseous or liquid tank discharges to
ensure the abnormal discharge was monitored by the discharge point effluent monitor.
Discharges made with inoperable effluent radiation monitors, or unmonitored leakages
were reviewed to ensure that an evaluation was made of the discharge to account for
the effluent release and were included in the calculated doses to the public.
Groundwater Protection Initiative (GPI) Implementation
The inspectors reviewed monitoring results of the voluntary Nuclear Energy Institute GPI
to determine if PPL has implemented the GPI as intended.
For anomalous results or missed samples, the inspectors assessed whether PPL has
identified and addressed deficiencies through its CAP.
The inspectors reviewed identified leakage or spill events and entries made into PPL's
decommissioning files. The inspectors reviewed evaluations of leaks or spills, and
reviewed the effectiveness any remediation actions. The inspectors reviewed onsite
contamination events involving contamination of groundwater and assessed whether the
source of the leak or spill was identified and isolated/terminated.
For unmonitored spills, leaks, or unexpected liquid or gaseous discharges, the
inspectors assessed whether an evaluation was performed to determine the type and
amount of radioactive material that was discharged by: assessing whether sufficient
radiological surveys were performed to evaluate the extent of the contamination and
assessing whether a survey/evaluation has been performed; and determining whether
PPL completed offsite notifications, as provided in its GPI implementing procedures.
The inspectors did not review any evaluation of discharges from onsite surface water
bodies as none currently exist at the site.
The inspectors assessed whether on-site groundwater sample results and a description
of any significant on-site leaks/spills into groundwater for each calendar year are
documented in the Annual Radioactive Effluent Release Report.
For significant, new effluent discharge points, such as significant or continuing leakage
to groundwater that continues to impact the environment, the inspectors evaluated
Enclosure
28
whether the licensees ODCM was updated to include the dose calculation method for
the new release point and the associated dose calculation methodology.
Problem Identification and Resolution
Inspectors assessed whether problems associated with the effluent monitoring and
control program were being identified by the PPL staff at an appropriate threshold and
properly addressed for resolution in the PPLs licensee CAP. In addition, the inspectors
evaluated the appropriateness of the corrective actions for a selected sample of
problems documented.
b. Findings
No findings were identified.
2RS8 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and
Transportation (71124.08 - 1 sample)
a. Inspection Scope
This area was inspected to verify the effectiveness of PPLs programs for processing,
handling, storage, and transportation of radioactive material. The inspectors used the
requirements of 10 CFR Parts 20, 61, and 71, and 10 CFR Part 50, Appendix A, -
Criterion 63, Monitoring Fuel and Waste Storage, and PPL procedures required by the
TSs/Process Control Program (PCP) as criteria for determining compliance.
The inspectors reviewed the solid radioactive waste system description in the FSAR,
the PCP, and the recent radiological effluent release report for information on the types,
amounts, and processing of radioactive waste disposed.
The inspectors reviewed the scope of quality assurance (QA) audits performed for this
area since the last inspection. The inspectors reviewed the results of the audits
performed since the last inspection of this program and evaluated the adequacy of
PPLs corrective actions for issues identified during those audits.
The inspectors observed areas where containers of radioactive waste were stored, and
verified that the containers were labeled in accordance with 10 CFR 20.1904, Labeling
Containers, or controlled in accordance with 10 CFR 20.1905, Exemptions to Labeling
Requirements, as appropriate.
The inspectors verified that the radioactive materials storage areas were controlled
and posted in accordance with the requirements of 10 CFR Part 20, Standards for
Protection Against Radiation. For materials stored or used in the controlled or
unrestricted areas, the inspectors verified that they were secured against unauthorized
removal and controlled in accordance with 10 CFR 20.1801, Security of Stored
Material, and 10 CFR 20.1802, Control of Material not in Storage, as appropriate.
The inspectors verified that PPL had established a process for monitoring the impact of
long-term storage (e.g., buildup of any gases produced by waste decomposition,
chemical reactions, container deformation, loss of container integrity, or re-release of
free-flowing water) sufficient to identify potential unmonitored, unplanned releases, or
Enclosure
29
nonconformance with waste disposal requirements. The inspectors verified that there
were no signs of swelling, leakage, or deformation.
The inspectors walked down accessible portions of liquid and solid radioactive waste
processing systems to verify and assess that the current system configuration and
operation agree with the descriptions in the FSAR, offsite dose calculation manual,
and PCP.
The inspectors identified radioactive waste processing equipment that was not
operational and/or was abandoned in place, and verified that PPL had established
administrative and/or physical controls to ensure that the equipment would not contribute
to an unmonitored release path and/or affect operating systems or be a source of
unnecessary personnel exposure. The inspectors verified that PPL had reviewed the
safety significance of systems and equipment abandoned in place in accordance with
10 CFR 50.59, Changes, Tests, and Experiments.
The inspectors reviewed the adequacy of any changes made to the radioactive waste
processing systems since the last inspection. The inspectors verified that changes from
what was described in the FSAR were reviewed and documented in accordance with
10 CFR 50.59, as appropriate.
The inspectors identified processes for transferring radioactive waste resin and/or sludge
discharges into shipping/disposal containers. The inspectors verified that the waste
stream mixing, sampling procedures, and methodology for waste concentration
averaging were consistent with the PCP, and provided representative samples of the
waste product for the purposes of waste classification as described in 10 CFR 61.55,
Waste Classification.
For those systems that provide tank recirculation, the inspectors verified that the tank
recirculation procedure provided sufficient mixing.
The inspectors verified that the licensees PCP correctly described the current methods
and procedures for dewatering waste.
The inspectors identified radioactive waste streams, and verified that PPLs radio-
chemical sample analysis results were sufficient to support radioactive waste
characterization as required by 10 CFR Part 61, Licensing Requirements for Land
Disposal of Radioactive Waste. The inspectors verified that PPLs use of scaling
factors and calculations to account for difficult-to-measure radionuclides was technically
sound and based on current 10 CFR Part 61 analyses.
For the waste streams identified above, the inspectors verified that changes to plant
operational parameters were taken into account to (1) maintain the validity of the waste
stream composition data between the annual or biennial sample analysis update, and
(2) verified that waste shipments continued to meet the requirements of 10 CFR Part 61.
The inspectors verified that PPL had established and maintained an adequate QA
program to ensure compliance with the waste classification and characterization
requirements of 10 CFR 61.55, Waste Classification and 10 CFR 61.56, Waste
Characteristics.
Enclosure
30
The inspectors reviewed the records of shipment packaging, surveying, labeling,
marking, placarding, vehicle checks, emergency instructions, disposal manifest, shipping
papers provided to the driver, and verification of shipment readiness. The inspectors
verified that the requirements of any applicable transport cask certificate of compliance
had been met. The inspectors verified that the receiving licensee was authorized to
receive the shipment packages.
The inspectors determined that the shippers were knowledgeable of the shipping
regulations and that shipping personnel demonstrated adequate skills to accomplish the
package preparation requirements for public transport with respect to PPLs response to
NRC Bulletin 79-19, Packaging of Low-Level Radioactive Waste for Transport and
Burial, and 49 CFR Part 172, Hazardous Materials Table, Special Provisions,
Hazardous Materials Communication, Emergency Response Information, Training
Requirements, and Security Plans, Subpart H, Training. The inspectors verified that
PPLs training program provided training to personnel responsible for the conduct of
radioactive waste processing and radioactive material shipment preparation activities.
The inspectors identified non-excepted package shipment records and verified that the
shipping documents indicate the proper shipper name; emergency response information
and a 24-hour contact telephone number; accurate curie content and volume of material;
and appropriate waste classification, transport index, and shipping identification number.
The inspectors verified that the shipment placarding was consistent with the information
in the shipping documentation.
The inspectors verified that problems associated with radioactive waste processing,
handling, storage, and transportation, were being identified by PPL at an appropriate
threshold, were properly characterized, and were properly addressed for resolution in
PPLs CAP. The inspectors verified the appropriateness of the corrective actions for
a selected sample of problems documented by PPL that involve radioactive waste
processing, handling, storage, and transportation. PPL generated six CRs to document
material condition deficiencies identified during this inspection.
b. Findings
No findings were identified.
4. OTHER ACTIVITIES
4OA1 Performance Indicator Verification) (71151 - 8 samples)
.1 Mitigating Systems Performance Index (MSPI) (4 samples)
a. Inspection Scope
The inspectors reviewed PPLs submittal of the MSPI for the following systems for the
following systems for the period of October 1, 2011 through September 30, 2012:
Units 1 and 2, emergency alternating current power systems (MS06)
Units 1 and 2, RHR systems (MS09)
Enclosure
31
To determine the accuracy of the performance indicator data reported during those
periods, the inspectors used definitions and guidance contained in Nuclear Energy
Institute (NEI) Document 99-02, Regulatory Assessment Performance Indicator
Guideline, Revision 6. The inspectors also reviewed PPLs operator narrative logs,
CRs, mitigating systems performance index derivation reports, event reports, and
NRC integrated IRs to validate the accuracy of the submittals.
b. Findings
No findings were identified.
.2 Radiological Effluent TS/Offsite Dose Manual (ODCM) Radiological Effluent
Occurrences (1 sample)
a. Inspection Scope
During November 5-9, 2012, the inspectors sampled PPL submittals for the radiological
effluent TS/ODCM radiological effluent occurrences PI (PR01) for the period from the 1st
quarter 2011 through 4th quarter 2011. The inspectors used PI definitions and guidance
contained in the Nuclear Energy Institute Document 99-02, Regulatory Assessment PI
Guideline, Revision 6, dated October 2009, to determine if the PI data was reported
properly during this period.
The inspectors reviewed PPLs corrective action report (AR) database and selected
individual reports generated since this indicator was last reviewed to identify any
potential occurrences such as unmonitored, uncontrolled, or improperly calculated
effluent releases that may have impacted offsite dose. The inspectors reviewed
gaseous and liquid effluent summary data and the results of associated offsite dose
calculations for selected dates between 1st quarter 2011 through 4th quarter 2011, to
determine if indicator results were accurately reported. The inspectors also reviewed
PPLs methods for quantifying gaseous and liquid effluents and determining effluent
dose.
b. Findings
No findings were identified.
.3 Emergency Preparedness (3 samples)
a. Inspection Scope
The inspectors reviewed data for the three EP Performance Indicators (PI), which are:
(1) Drill and Exercise Performance (ER01); (2) Emergency Response Organization Drill
Participation (ER02); and, (3) Alert and Notification System Reliability (ER03). The last
NRC EP inspection at Susquehanna was conducted in the fourth quarter of 2011.
Therefore, the inspectors reviewed supporting documentation from EP drills and
equipment tests from the fourth quarter of 2011 through the third quarter of 2012 to
verify the accuracy of the reported PI data. The review of the PIs was conducted in
accordance with NRC Inspection Procedure 71151. The acceptance criteria
documented in NEI 99-02, Regulatory Assessment Performance Indicator Guidelines,
Revision 6, was used as reference criteria.
Enclosure
32
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution (71152)
.1 Routine Review of Problem Identification & Resolution (PI&R) Activities
a. Inspection Scope
As required by Inspection Procedure (IP) 71152, Problem Identification and Resolution,
the inspectors routinely reviewed issues during baseline inspection activities and plant
status reviews to verify that PPL entered issues into the CAP at an appropriate
threshold, gave adequate attention to timely corrective actions, and identified and
addressed adverse trends. In order to assist with the identification of repetitive
equipment failures and specific human performance issues for follow-up, the inspectors
performed a daily screening of items entered into the CAP and periodically attended CR
screening meetings.
b. Findings
No findings were identified.
.2 Semi-Annual Trend Review (1 sample)
a. Inspection Scope
The inspectors performed a semi-annual review of site issues, as required by IP 71152,
Problem Identification and Resolution, to identify trends that might indicate the
existence of more significant safety issues. In this review, the inspectors included
repetitive or closely-related issues that may have been documented by PPL staff outside
of the CAP, such as trend reports, performance indicators, major equipment problem
lists, system health reports, maintenance rule assessments, and maintenance or CAP
backlogs. The inspectors also reviewed PPLs CAP database for the third and fourth
quarters of 2012 to assess CRs written in various subject areas (equipment problems,
human performance issues, etc.), as well as individual issues identified during the NRCs
daily CR review (Section 4OA2.1). The inspectors reviewed PPL staffs quarterly trend
reports for the first three quarters of 2012, conducted under NDAP-QA-0710, Station
Trending Program, to verify that PPL personnel were appropriately evaluating and
trending adverse conditions in accordance with applicable procedures.
b. Findings and Observations
Evaluation of Trends Related to CAP Evaluations (P.1(c)).
PPL staff has designated CAP as a gap to excellence and a subset of the metrics PPL
uses to monitor CAP progress are attributable to the P.1(c) Evaluation substantive
cross-cutting issue (SCCI). Additionally, PPL completed an evaluation (CR 1633700)
after the NRCs 2012 mid-cycle assessment letter (ML12248A066), dated September 4,
2012, continued the SCCI. The evaluation concluded there were no additional
performance gaps that have not been identified and addressed with corrective actions.
Enclosure
33
The evaluation used three performance indicators (PIs) (discussed below) to confirm
PPL staffs conclusion. The inspectors performed a review of these metrics, and other
PIs deemed by the inspectors to be pertinent to the SCCI, to determine what standards
PPL had established and whether corrective actions were identified as a result of PPLs
monitoring of their internal metrics.
Quality of CARB Reviewed CR Evaluations (SL52) - This metric measures the
quality of CARB-reviewed root cause analyses (RCAs) and ACEs and plots both
the six-month average and the monthly percent rejection rate. The metric has
been White for the duration of 2012. In September, PPL concluded that the
improving trend had stalled the past several months. In October and December,
PPL concluded that the trend was slowly and consistently improving. During
review, the inspectors questioned the rise in evaluation rejection rate from 12.5
percent in both July and August, to 25 percent in September, to 50 percent for
October and November, without a corresponding decline in overall metric
performance. PPL examined the input data to the PI and determined that the
metric was incorrect. PPL entered this issue into their CAP (CR 1657686). The
PI was revised and while the trend for rejection rate percentages changed, the
overall metric color did not change.
Effectiveness Review Results (GWE40) - This metric was Green for October
after being White since January 2012. October data showed 9 of 10
effectiveness reviews rated as being effective. PPL changed the thresholds in
June 2011 to be more challenging and the rolling average was reduced from 12
to 6 months. In response to inspector questioning of SL52 accuracy, PPL also
reviewed the data for this PI and identified that this PI was also incorrect. PPL
incorporated additional effectiveness reviews that had been unaccounted for,
including five effectiveness reviews rated as being ineffective. The incorporation
of this data caused the revised PI to be changed from Green to Yellow. PPL
entered this issue into their CAP (CR 1659032).
Repeat of Significant Events (SL90) - This PI is based on the same root cause
occurring twice in a three-year rolling period and has been White for 2012. The
PI is based, in part, on a cognitive review of root causes and is expected to be
reduced to a one-year rolling average in 2013.
CAP Engagement (SL82) - This metric, covering Performance Improvement
Review Board (PIRB), CAP Health, Management Review Committee (MRC), and
CARB meeting attendance by senior management, has been consistently Green.
Notwithstanding, PPL staffs November update documented that senior
leadership struggles during outage periods for oversight of screening, MRC,
CARB, and CAP recovery meetings. The update stated that while this metric is
monitored during outages, it does not have any bearing on establishing a
recovery plan since the metric is extremely impacted by outages. The
inspectors noted that a substantial amount of 2012 was spent in outages to
include the Unit 1 refueling and Unit 2 maintenance outages in the spring, the
Unit 1 shutdown for pressure boundary leakage in the summer, fall maintenance
outages on both Units, and two Unit 2 reactor scrams in December. Additionally,
the inspectors noted that PIRB and CAP Health were consistently above the
average and most often had a score over 200 percent while MRC, a daily
meeting, was consistently less than 100 percent. MRC engagement remained
Enclosure
34
less than the goal at 26 percent in October and 68 percent in November. PPL
staff documented that no recovery plan is necessary.
Operability Determinations - The inspectors observed that PPL does not have
metrics to monitor effectiveness of Operability Determinations. The inspectors
noted that weaknesses in Operability Determinations resulted in several NRC
findings with a P.1(c) cross cutting aspect that contributed to the SCCI and
corrective actions have been developed to address weakness in this area.
Finally, both the Biennial PI&R inspection and a fourth quarter inspection sample
identified ACEs that did not evaluate deeper than the direct cause, contrary to station
procedures. Despite this, Departmental Corrective Action Review Board (DCARB)
scores were relatively high, none of the DCARBs were cross-functional, and all five
ACEs were not reviewed by CARB. PPL subsequently identified two additional ACEs
with similar issues. PPL has implemented cross-functional DCARBs as an interim
measure that will be evaluated for effectiveness.
Review of Trend Related to Procedure Quality (H.2(c))
At the station level, PPL staff has designated procedure quality, use, and adherence as
a gap to excellence. A subset of the metrics PPL uses to monitor progress in this area is
attributable to the procedure quality (H.2.(c)) substantive cross-cutting issue. The
inspectors performed a review of the applicable metrics to determine what standards
PPL had established and whether corrective actions were identified as a result of PPLs
monitoring of their internal metrics.
Procedure Request Average Age by Priority (SL104) - This metric is based on
priority 1 and 2 requests exceeding 180 days. The metric was Red from July
through October 2012. Of the four levels of Operations Procedure Group (OPG)
priority levels, there was a rise in the number of Level 3 and Level 4 requests by
age and a drop in the monthly number of Level 2 requests by age. Of the four
levels of Maintenance Procedure Group (MPG) priority levels, there was a
general rise in the number of Level 2 requests by age and general stability
without reduction in the number of Level 3 and 4 requests by age. Recovery
plans for this metric include procedure action item burndown curves that target a
total of 590 procedure requests by June 2013 and 350 by the end of 2013. The
recovery plan for the MPG concluded that resource issues and a large number of
incoming items resulted in the high percentage of high priority items. There were
also open positions in the organization that PPL management anticipated would
assist in backlog reduction, once filled.
Incoming Procedure Change Request (SL106) - This metric is based on the total
number of change requests with a distinct mechanism that each procedure
affected by a request is counted individually. The metric has been consistently
Green with a threshold of 100 change requests.
Procedure Quality Issues Identified (SL109) - This metric was changed in June
2012 to represent both technical and quality procedure issues. The metric has
been predominantly Red based on technical quality procedure issues exceeding
60 per month. The BOP procedures were not yet prioritized and incorporated
into this PI. The Green threshold is less than or equal to 40 per month. PPL
Enclosure
35
staff generated OPG and MPG recovery plans that consist of burndown curves
through the end of 2013.
Procedure Request Total Backlog Quantity (SL110) - This metric has been Red
from June through October 2012 based on the total backlog (technical, quality,
enhancement, and editorial) exceeding 1500. PPL staffs assessment stated that
the industry average for a two-unit site is 1200 items. The BOP procedures were
not yet prioritized and incorporated into this PI.
Emerging Trend in Work Control (H.3(a))
There was one NRC finding in each of the first three quarters of 2012 in this cross-
cutting area. In response, PPL staff conducted a common-cause analysis (CCA) (CR
1616738) that was not CARB-approved by the end of the inspection period. The
inspectors had one observation regarding the corrective actions planned.
The stations lowest work levels, work lists, were partly responsible for two of the three
NCVs. The lower threshold of these work list items enabled some work activities to
initiate without appropriate management or programmatic review. Corrective actions
regarding these work lists are due greater than a year from when the initial NCV with an
H.3(a) aspect was issued.
Emerging Trend in Preparations for Adverse Weather
During a winter readiness inspection sample, the inspectors noted that the preparatory
checklist in NDAP-00-0024, Winter Operation Preparations, Revision 18, had not been
completed by November 1 of each year, as required, from 2008 through 2012 (CRs
1088314, 1198388, 1323433, 1489677, and 1638078). Additionally, the summer
operations preparation procedure, NDAP-00-0334, was not completed prior to May 15,
2012 as required (CR 1575139). Finally, in the 2012 third quarter inspection report, the
NRC issued a Green NCV regarding an inadequate procedure for high winds. The
inspectors concluded that there is an adverse trend in PPL personnel preparing for
seasonal and adverse weather conditions in a timely manner.
Emerging Trend in CAP- Problem Identification (P.1(a))
The inspectors observed an issue with respect to problems being identified and placed
into the CAP based on recent inspection results.
During implementation of Temporary Instruction (TI)-187 and TI-188, inspector obser-
vations during a walkdown of the Unit 2 HPCI room floor degradations were initially
assessed by Engineering as not warranting CAP entry. Inspectors reviewed NDAP-QA-
0702, Action Request and Condition Report Process, and determined the issues met the
station defined threshold for CR generation. Following additional discussions with PPL
staff, the items were entered in the CAP.
Three NCVs in 2012 had aspects of problem identification. The first had a cross-cutting
aspect in P.1.(a) based on personnel not entering issues into the CAP when they
discovered a lack of procedural guidance, qualification, and non-compliance with
instructions associated with the motor-operated valve program (NCV 2012002-01).
Enclosure
36
The second had a cross-cutting aspect in P.1(a) based on PPL not entering procedural
issues into the CAP during a periodic procedure review or after inspectors provided the
issues to PPL staff (NCV 2012004-01). The third had a cross-cutting aspect in P.1(a)
and is documented in this report (Section 1EP6). Based on having three findings with
the same cross-cutting aspect in a four quarter period, PPL generated CR 1664721 to
perform a CCA on the collective issues.
Inspectors identified a missed risk assessment when one division of ESW was removed
from service on an operable EDG to support testing. The issue was communicated to
the work week manager who confirmed that the item had not been included in the
stations risk assessment; however, when it was added, the overall risk to the station
remained Green. Since this issue was a minor violation of 10 CFR 50.65(a)(4), it was
required to be entered into the stations CAP by PPLs CAP procedures. The issue was
not entered into the CAP until inspectors discussed the issue with senior PPL
management.
Inspectors reviewed an ACE on TS SR 3.4.2.1 requirements that concluded that the
stations performance was not in strict compliance with the SR. No CR was generated
to ensure corrective actions were taken to restore compliance until identified by the
inspectors. PPL staff took subsequent actions to revise the ACE.
Emerging Trend in Maintenance Rule Program Implementation
The inspectors noted challenges in PPL staffs implementation of the Maintenance Rule.
Maintenance Rule Expert Panel (MREP) backlog - In August 2012, the
inspectors became aware of a 17-item backlog in MRFFs that required MREP
review and that no MREP meetings occurred from April through August 2012.
PPL staff attributed the cause to extended plant outages and limited, qualified
expert panel members. This condition had existed from July 2011 when CR
1437589 documented the same situation. Additionally, PPL staff identified that
the station routinely failed to generate actions to track MREP review of the
MRFFs. In response, PPL management took action to qualify additional MREP
members and held six MREP meetings from September to the end of 2012.
Notwithstanding, the inspectors concluded the problem has not been sufficiently
resolved. For example, there were still five MRFFs requiring MREP review that
were in excess of the 60-day procedural requirement. This included one MRFF
on an inboard D MSIV LLRT with an MREP due date ten months after
identification. Inspectors identified two additional MRFFs that both exceeded the
60 day guideline and did not have associated action item for MREP review.
Scoping - Inspectors identified that the ability to substitute the E EDG for other
EDGs was not scoped into the Maintenance Rule despite being used in EOPs
(CR 1630387).
Timeliness of 10 CFR 50.65(a)(1) classification - In the discussion of the
Maintenance Rule NCV in Section 1R12 of this report, there was approximately a
year delay for a RCIC system issue designated as a MRFF to be reviewed by the
MREP. As a result, it took over a year before the system was reclassified as
(a)(1). Additionally, in the summer of 2012, the inspectors identified that PPL
staff had not classified Unit 2 RCIC as an a(1) system despite meeting the
Enclosure
37
performance criteria in the summer of 2011 (CR 1619848). The system was
subsequently presented to MREP in September of 2012 where it was classified
as (a)(1). In both cases, the delays in the review of issues by the MREP resulted
in actions to reclassify the systems to a(1) and establishment of goals as
required by 10 CFR 50.65(a)(1) to be untimely.
Quality of MPFF determinations - This report documents an NRC-identified
violation of 10 CFR 50.65(a)(2) which occurred when a MRFF was
inappropriately classified as not maintenance preventable in Section 1R12.
Additionally, inspectors reviewed an ACE for a gasket failure in the control room
emergency outside air supply (CREOAS) system which concluded that no vendor
guidance for periodic replacement existed and determined the MRFF was not
maintenance preventable. Inspectors reviewed the vendor manual and identified
that it did in fact provide recommendations for inspection and periodic
replacement. This resulted in the issue becoming an MPFF and required a
revision to the ACE. The CREOAS system remained in a(2); therefore, the issue
was determined to be of minor safety significance.
.3 Annual Sample - 1A Reactor Recirculation Pump Suction Decontamination Flange
Weld Though-Wall Leak (1 Sample)
a. Inspection Scope
The inspectors assessed the adequacy of and associated corrective actions from the
root cause analysis (RCA) for the development of a through wall leak of the Unit 1 A
reactor recirculation pump suction decontamination flange weld VRR-B31-1-14F. The
inspectors reviewed the RCA report (CR 1589390), to determine the root cause and
contributing causes for the through wall leak, and the adequacy and status of corrective
actions.
The inspectors assessed PPL staffs problem identification threshold, cause analyses,
extent of condition reviews, compensatory actions, and the prioritization and timeliness
of corrective actions to determine whether PPL staff was appropriately identifying,
characterizing, and correcting problems associated with this issue and whether the
planned or completed corrective actions were appropriate. The inspectors compared
the actions taken to the requirements of PPLs CAP and 10 CFR 50 Appendix B. In
addition, the inspectors conducted interviews with the root cause team leader, and
other engineering and operations personnel who were familiar with the event and the
investigation.
b. Findings
Introduction. A self-revealing Green NCV of 10 CFR 50, Appendix B, Criterion III,
Design Control, was identified related to the development of a through-wall leak of
the Unit 1 A reactor recirculation pump suction line decontamination flange weld. This
through-wall leak resulted in an unexpected increase in unidentified drywell leak rate and
a shutdown of Unit 1 on June 19, 2012, in order to make repairs. Specifically, PPL
personnel used an incorrect value for stress intensification factor in the vibration analysis
in 2004 to support an extended power uprate (EPU). When the correct stress intensi-
fication factor was used, American Society of Mechanical Engineers (ASME) OM-3 code
limits for endurance and fatigue stress were exceeded. The through-wall leak resulted in
Enclosure
38
pressure boundary leakage in excess of TS 3.4.4 limits from approximately June 16 to
June 19, 2012.
Discussion. Operators commenced a reactor startup for Susquehanna Unit 1 from a
refueling outage on June 7, 2012. From plant startup until June 15, the drywell
unidentified leak rate slowly increased to 0.13 gallons per minute (gpm). On June 16,
operators observed a step increase in the unidentified leak rate from 0.13 to 0.50 gpm
was observed. Unidentified leak rate continued to trend upward over the next several
days to a maximum of 1.80 gpm. On June 18, PPL management made the decision to
conduct a controlled plant shutdown of Unit 1 due to this increasing trend in unidentified
drywell leakage and drywell pressure. On June 19, Unit 1 was shutdown and a through-
wall crack was identified on 1A reactor recirculation pump suction decontamination
flange weld, VRR-B31-1-14F. Investigation revealed that a through-wall cyclic fatigue-
driven circumferential crack measuring 3 1/8 outside diameter (OD) and 2 5/8 inside
diameter (ID), initiated from the outside diameter, was the source of the leakage. In
addition, an axial, intergranular stress corrosion and cracking (IGSCC)-driven crack was
also found. However, that crack had been arrested in the weld material and was not
through-wall.
The decontamination line is a flanged connection provided to facilitate decontamination
of the recirculation system. Connections are provided in each recirculation loop on the
suction and discharge side of the pump inboard of the pump suction and discharge
valves. These connections are arranged for attachment of temporary piping to permit
flushing and decontamination of the pump and adjacent piping. The suction line
connection was an unsupported four inch flanged line.
PPL calculated the natural frequency of this line to be 129.6 Hz and the primary
frequency of vibration is 128.5 Hz. These frequencies are in the range of vibrations
experienced at the high end of the design operating range of the reactor recirculation
pumps. At these frequencies, the decontamination flange pipe is exposed to large
bending moments and stresses in the decontamination pipe branch connection. The
primary concern is the five-times (5X) vane passing frequency developed from the
recirculation pump when operating at pump speeds greater than 1515 rpm and system
flow rates greater than 103 Mlbm/hr.
In 1995, following the Unit 1 stretch power uprate (5 percent), flow rates of up to 108
Mlbm/hr were included in the new power to flow envelope. General Electric (GE) testing
programs in June 1994 following the same power uprate on Unit 2, identified abnormal
increases in RCS system vibrations at recirculation pump speed of 1570 to 1580 rpm.
These vibrations were generated by the 5X vane pass frequency of the recirculation
pumps. This was the subject of NRC Information Notice (IN) 95-16, Vibration Caused
by Recirculation Flow in a Boiling Water Reactor. However prior to 2001, recirculation
pumps were not operated above 1480 rpm by procedure. Following a power uprate in
2001, PPLs procedures were revised to authorize flow rates of up to 104 Mlbm/hr.
The PPL RCA team discovered, in 2004, PPL had contracted an outside engineering
firm to recalculate the vibrations stresses on the RCS piping systems in preparation for
an EPU. PPL provided the weld profiles for the welds within the reactor recirculation
piping system to the contractor to perform this analysis. PPL procedure, NDAP-QA-
1208, Control of Welding, contained the PPL specifications for the weld and the
specifications for in-service inspection (ISI) of girth butt welds which required welds in
Enclosure
39
stainless steel material to be essentially flush. Weld detail P5 of NDAP-QA-1208
illustrated the specification. However, the weld profile for weld VRR-B31-1-14F was not
consistent with this specification. This weld did not meet the ASME design requirements
for a flush weld; therefore, a stress intensification factor of 1.8 vice 1.1 needed to be
applied to determine the stresses felt by the weld. However, the PPL RCA team
discovered that the contractor did not identify that the weld was not flush and used the
incorrect stress intensification factor. This resulted in an incorrect conclusion that
alternating stresses due to vibrations were within specification and ASME code fatigue
curve values at 1011 cycles were also within specification yielding an infinite life with an
input frequency of 128.5 Hz.
The decontamination lines were instrumented for post EPU testing and vibrations limits
were established based upon the 2004 piping stress calculations. In July of 2010,
measured peak acceleration exceeded the level 2 vibration limits established. However,
the action for exceeding level 2 limits was to review the measured accelerations data
and resulting stresses against the stress limits established in the 2004 calculation. As a
result PPL determined the test data to have been within limits which supported
continued operations.
Following the discovery of the through-wall leak in 2012, PPL contracted a vendor and
provided them with the 2004 weld profile and specifications and requested that they
recalculate the stresses for VRR-31-1-14F and compare the results to the data taken
during the 2010 EPU. Using the proper stress intensification factor, the vendor
determined the ASME OM-S/G-2009 Part 3 stress limit was 10,880 psi, and the stresses
measured during EPU acceptance testing were 13,674 psi (approximately 26 percent
greater than the endurance limit). Likewise, the ASME fatigue curve values at 1011
cycles was recalculated for the measured stresses which calculated an expected lifetime
of only 4.9 years at a frequency of 128.5 Hz. These results would not have justified
continued operation in 2010 and corrective actions would have had to be taken. Correct
calculations could have precluded the weld failure.
PPLs corrective actions included, modifying the length of the 1A reactor recirculation
pump suction decontamination flange to change the natural frequency of the line such
that it was no longer within the operating range of the reactor recirculation pumps, the
1B reactor recirculation was also modified. Unit 2s reactor recirculation pump suction
decontamination flanges were reviewed and their natural frequencies were found to be
above the operating range of the reactor recirculation pumps and the post EPU testing
data confirmed this. Extent of condition reviews included identifying other susceptible
components, conducting volumetric examinations of those welds, reviewing the piping
stress analysis weld data to determine if any addition welds were mischaracterized as
being flush.
The crack resulted in an unidentified leak rate of 1.8 gpm at the time the unit was
shutdown. The critical flaw size for structural integrity of the flange was calculated to be
a crack measuring 7.7 and the crack discovered was 3 1/8 long. The TS limit for
unidentified leakage is 5.0 gpm; however, a through-wall leak from a weld is considered
pressure boundary leakage and the TS limit for pressure boundary leakage is zero.
Thus, Susquehanna Unit 1 had operated in a condition prohibited by TSs. Notwith-
standing, PPLs evaluation determined that the flaw characterization was such that
complete failure could not have resulted in leakage that exceeded the leak rate for a
small break loss of coolant accident (LOCA).
Enclosure
40
Analysis. PPL not identifying weld VRR-B31-1-14F was not flush and applying the
improper stress intensification factor in accordance with the ASME code in 2004 was a
performance deficiency within PPLs ability to foresee and correct. The performance
deficiency was reviewed using IMC 0612, Appendix B, Issue Screening, and was
determined to be more than minor because it affected the Initiating Events Cornerstone
attribute of design control. The issue adversely affected the associated cornerstone
objective of limiting the likelihood of those events that upset plant stability and challenge
critical safety functions during shutdown as well as power operations. The finding was
evaluated using Section A of IMC 0609 Appendix A, Exhibit 1, Initiating Events
Screening Questions. Since the finding result could not have reasonably exceeded the
leak rate for a small LOCA and did not likely affect other systems used to mitigate a
LOCA resulting in a total loss of their function (e.g., Interfacing System LOCA), the
finding screened to very low safety significance (Green). This finding was determined to
not be indicative of current performance since the performance deficiency occurred in
2004 and procedures and training are in place that would have precluded the issue.
Thus no cross-cutting aspect is assigned.
Enforcement. 10 CFR 50 Appendix B, Criterion III, Design Control, states, in part,
measures shall be established to assure that applicable regulatory requirements and
the design basis, as defined in 10 CFR 50.2 and as specified in the license application,
for those structures, systems, and components to which this appendix applies are
correctly translated into specifications, drawings, procedures, and instructions.
Additionally, Criterion III states that design control measures shall be applied to items
such as the following: reactor physics, stress, thermal, hydraulic, and accident analyses;
compatibility of materials; accessibility for in-service inspection, maintenance, and repair;
and delineation of acceptance criteria for inspections and tests. TS 3.4.4, RCS
Operational LEAKAGE, states, in part, RCS operational LEAKAGE shall be limited
to: (a) No pressure boundary LEAKAGE; and (b) < 5 gpm unidentified LEAKAGE.
Contrary to the above from 2004 until June 19, 2012, PPL failed to accurately translate
design basis requirements to ensure Unit 1 RCS piping systems met ASME Code
requirements to pipe stress analysis calculations and acceptance criteria due to using an
incorrect stress intensification factor. The weld in question subsequently failed resulting
in pressure boundary leakage in excess of Technical Specification 3.4.4 limits from
June 16 to June 18, 2012. PPL took action to make repairs to the piping and review
other areas for extent of condition. Because of the very low safety significance of this
finding and because the finding was entered into PPLs CAP as CR 1589390, this
violation is being treated as an NCV, consistent with Section 2.3.2 of the NRC
Enforcement Policy. (NCV 05000387/2012005-04, Improper Stress Intensification
Factor Results in RCS Pressure Boundary Leak)
c. Observations
The inspectors assessed PPLs problem identification threshold, cause analyses, extent
of condition reviews, compensatory actions, and the prioritization and timeliness of
PPLs corrective actions to determine whether PPLs was appropriately identifying,
characterizing, and correcting problems associated with this issue and whether the
planned or completed corrective actions were appropriate. The inspectors compared the
actions taken to the requirements of PPLs corrective action program and 10 CFR 50,
Appendix B. The inspectors concluded that PPLs evaluations and corrective actions for
this issue were timely and appropriate. The RCA (CR 1589390, Revision 1) for the issue
identified the causes of the through-wall leak, developed appropriate extent of condition
and extent of cause reviews and the corrective actions were timely and reasonable.
Enclosure
41
.4 Annual Sample: Failure to Report Changes in Medical Conditions as Required by 10
CFR 50.74, Notification of Change in Operator or Senior Operator Status (1 sample)
a. Inspection Scope
In February 2012, PPL staff commenced a root cause investigation (CR 15167640) in
response to a series of NRC findings from 2007 to present involving required NRC
notifications not being made that affected license conditions of licensed operators. The
root cause report was issued on April 17, 2012. As a result of PPLs review, on July 20,
2012, PPL submitted ten medical updates to the NRC. Four of the ten submittals
reported permanent changes in medical conditions that were not submitted in a timely
manner as required and six others were submitted to the NRC as Information Only.
On August 28 to 29, 2012, inspectors conducted a Problem Identification and Resolution
(PI&R) inspection. Since there had been a history of unreported medical issues at
Susquehanna dating back four years, the focus of this inspection was to determine the
site process for conducting the 10 CFR 55 required biennial licensed operator medical
exams. The inspectors reviewed appropriate medical documents, PPL procedures and
conducted interviews with PPL Staff, the PPL Medical Reviewing Officer (MRO) and
other knowledgeable individuals. This inspection also evaluated PPLs actions to restore
compliance and address SLIV NOV 50-387 & 388 2011-004-01. However, due to the
additional issues discovered and discussed below, the NOV could not be closed.
b. Findings
Introduction. The inspectors identified an unresolved item (URI) related to licensed
operator medical examinations and qualifications required by 10 CFR 55.53 and 10 CFR
55.21. Specifically, over a period of approximately four years, a number of licensed
operators developed potentially disqualifying medical conditions which were not properly
evaluated by PPL in accordance with ANSI/ANS-3.4-1983, American National Standard
Medical Certification and Monitoring of Personnel Requiring Operator Licenses for
Nuclear Power Plants. In addition, during this same time frame, there were a number
of cases (i.e., both historical and current) where PPL potentially failed to notify the NRC
of a change in medical condition within 30 days as required by 10 CFR 55.25. The
inspectors concluded that there are a number of recently submitted submittals of PPL
medical status updates that will require independent evaluation by the NRCs contract
physicians before the NRC is able to determine whether the medical issues represented
disqualifying conditions and; therefore, would constitute a violation of NRC requirements.
Description. In February 2012, PPL launched a root cause evaluation (CR 15167640)
in response to a series of NRC findings from 2007 to present involving required NRC
notifications not being made that affected license conditions of licensed operators. The
root cause report was issued on April 17, 2012. As a result of this evaluation, on July
20, 2012, PPL submitted ten medical updates to the NRC. Four of the ten submittals
reported permanent changes in medical conditions that were not submitted in a timely
manner as required and six others were submitted to the NRC as Information Only.
PPL later resubmitted three of the six Information Only submittals adding conditions to
the licenses after follow-up questioning from the NRC contract doctor. Examples of
license conditions included Solo Operations is Not Authorized and Shall Submit
Medical Status Report Every 12 Months.
Enclosure
42
In addition, PPL staff initiated CR 1597808 on July 12, 2012, when PPLs interviews
conducted with the MRO and site nurse as part of a root cause corrective action (CRA
1567782) revealed they are not adequately familiar with regulatory responsibilities
contained in 10 CFR 55.23, ANSI 3.4, and the NRC Medical FAQs. During the week of
July 16, 2012, the inspectors conducted a follow-up interview with the Licensed Operator
Requalification Training (LORT) supervisor who was assigned overall responsibility for
follow-up to the root cause investigation and corrective actions. On July 17, 2012, the
inspectors asked the LORT supervisor why neither the primary root cause
(Susquehanna lacks a formal process to maintain NRC licensed operator status to
ensure appropriate notifications are made) or causal factors pointed to the inadequate
training and oversight of the MRO and examining physician or assigned corrective
actions to address these issues. On July 18, 2012, PPL revised the root cause (CRA
1600109) to include training of the MRO and nurse as a root cause and assigned
corrective actions to address this issue.
On August 16, 2012, the MRO called the NRC inspectors to discuss questions that had
been previously posed to PPL staff by the inspectors. The MRO stated that he was
assigned to his position in 2008. The MRO stated that he was not given any turnover or
training regarding ANSI 3.4 or 10 CFR 55 requirements and that he relied on the in-
house nurse for her experience and insights. Through this discussion, the inspectors
identified that licensed operator medical examinations were coordinated by the site
nurse but the examinations were actually conducted at the Berwick Hospital by another
physician.
The site nurse, the MRO of record, and the doctor that actually performed the medical
examinations at Berwick Hospital were interviewed by the inspectors to determine their
process for conducting these examinations and for notifying the NRC when a change in
medical condition requires the operators license to be conditioned. The interviews also
established their prior understanding of the ANSI standard and 10 CFR 55. As a result
of their interviews the inspectors identified the following information which was not
identified in PPLs Root Cause Analysis:
The inspectors confirmed that the MRO was not provided a turnover or training
regarding ANSI 3.4 or 10 CFR 55 but learned by on-the-job performance as
discussed in the August 16 call with NRC inspectors.
The inspectors identified that the MRO does not actually perform the operator
medical examinations and, as a rule, he does not actually meet with or examine the
licensed operators during the medical exam process. The exams were actually
performed by a physician and his staff at Berwick Hospital and then the records were
faxed back to the nurse for later review by the nurse and the MRO.
The inspectors identified that the NRC Form 396s, Certification of Medical
Examination by Facility Licensee, sent to the NRC had not been completed
accurately in the past since the physicians name that had actually performed the
medical examinations was not entered on the part A of the form as required.
The inspectors identified that, in April 2010, Susquehanna Form 4294, Licensed
Operator Medical Requirements, was incorrectly revised by the MRO (i.e., the
revisions did not accurately reflect disqualifying conditions as indicated in ANSI/ANS-
3.4-1983). This Form was given to the physician actually performing the medical
examinations at Berwick Hospital as a checklist to highlight ANSI disqualifying
medical conditions.
Enclosure
43
The inspectors identified that the doctor at Berwick Hospital, who had been
performing the physical examinations for the past twenty years, had not been trained
on either ANSI 3.4 or 10 CFR 55.
The licensed operator medical issues identified in the past four years (i.e., both current
as well as historical) appear to be associated with PPLs failure to properly train and
provide oversight for their MRO and the Berwick examining physician regarding
compliance with the requirements of ANSI/ANS-3.4-1983 and 10 CFR 55. The medical
issues identified during this time frame appear to be related to a lack of knowledge and
inadequate oversight. The inspectors noted the following guidance applies:
ANSI/ANS-3.4-1983, states in part, 3. Health Evaluation Responsibility, 3.1 General
Aspects. The primary responsibility for assuring that qualified personnel are on duty
rests with the facility operator. The health requirements set forth herein are
considered the minimum necessary to determine that the physical condition and
general health of the individual are not such as might cause operational errors
endangering public health and safety. The designated medical examiner shall be
conversant with this standard and should have a general understanding of activities
required of a nuclear reactor operator.
Susquehanna Procedure, NTP-QA-31.12, Revision 5, Preparation and Submission
of NRC Form 396 - Certification of Medical Examination by facility Licensee and
NRC Form 398 - Personal Qualifications Statement - Licensee, section 6.3.11,
states in part, The Consulting Physician reviews the results against the medical
standards set forth in ANSI/ANS 3.4 -1983completes the medical section of Form
NRC- 396 for employees seeking Initial Licensure and Six-Year License Renewal or
any change in medical condition. Consulting Physician may also request a "waiver"
or a "specifically limited approval" when an employee's general medical condition
does not meet the minimum standard, i.e., wear corrective lenses. These requests
are documented on Form NRC-396 and other medical history and pertinent medical
documentation are attached.
NRC Form 396, Certification of Medical Examination by Facility Licensee, Part A,
Medical Examination Information, provides the physicians name, license number,
and most recent biennial medical examination date for the applicant that was
examined and states in part, I certify that in reaching this determination the
guidance in the ANSI standardwas followed, and that documentation is available
for review by the NRC. In addition, page two of the Instructions for NRC FORM
396, states in part, ...the physician has the ultimate responsibility for certifying that
the medical examination was conducted in accordance with the ANSI standard and
the applicant meets the medical requirements.
The inspectors concluded that PPLs failure to properly identify potentially disqualifying
medical conditions resulted in failure to notify the NRC of these changes in medical
conditions within 30 days, and in some cases may have affected the operators ability to
comply with operator license conditions that should have been in affect while standing
watch. This was a performance deficiency within PPLs ability to foresee and correct
and should have been prevented. The NRC has issued conditioned individual operator
licensees which address the potentially disqualifying conditions for the operators.
Enclosure
44
PPL has recently submitted several PPL medical status updates for the cases in
question that will require independent evaluation by the NRCs contract physicians. The
inspectors determined that these concerns represent a URI. Completion of an
independent evaluation by the NRC contract doctors is required before the NRC is able
to determine whether medical issues represented disqualifying conditions and, therefore,
would constitute a violation of NRC requirements. (URI 05000387;388/2012005-05,
Concerns Regarding PPLs Program for Conducting Biennial Medical Exams for
Licensed Operators and Reporting Changes in Medical Conditions).
.5 Annual Sample: Instances of Inoperable Main Steam Safety Relief Valves (SRVs)
(1 sample)
a. Inspection Scope
The inspectors performed an in-depth review of PPL's evaluations and corrective actions
associated with CR 1587108, for main steam SRV test failures. Specifically, during the
2012 Unit 1 refueling outage, two out of 5 SRVs tested did not meet the setpoint criteria
of +3 to -5 percent set forth in TS 3.4.3. Both SRVs actuated at a setpoint less than the
-5 percent criteria.
The inspectors assessed PPL's problem identification threshold, problem analysis,
extent of condition reviews, compensatory actions, and the prioritization and timeliness
of PPL's corrective actions to determine whether PPL was appropriately identifying,
characterizing, and correcting problems associated with this issue and whether the
planned or completed corrective actions were appropriate. The inspectors compared the
actions taken to the requirements of PPL's CAP and 10 CFR 50 Appendix B. The
inspectors interviewed engineering and licensing personnel to assess the effectiveness
of the implemented corrective actions, the reasonableness of the planned corrective
actions, and to evaluate the extent of any ongoing SRV problems. Specific documents
reviewed are listed in the attachment to this report.
b. Findings and Observations
No findings of significance were identified.
PPL staff determined the cause of the lower actuation was attributed to valve internal
misalignment. PPL staff determined the event to be a common cause inoperability of
independent trains or channels and reportable under 10 CFR 50.73(a)(2)(vii). However,
both SRVs would have relieved pressure before exceeding +3 percent. Therefore, the
SRV safety function, described in UFSAR 5.2.2.1.1, to prevent over-pressurization of the
reactor coolant pressure boundary, was not adversely impacted. In addition, TS 3.4.3
required the safety function of 14 of the 16 SRVs to be operable. With both SRVs
outside of their allowable TS setpoint criteria, 14 SRVs still remained operable and there
was no TS violation. PPL staff coordinated with the SRV vendor to address the
misalignment issues.
The inspectors determined PPL staffs overall response to the issue was commensurate
with the safety significance and included conservative decision-making and appropriate
engineering analysis. The inspectors determined that the actions taken or planned were
reasonable to resolve the identified SRV issues.
Enclosure
45
.6 Annual Sample: Evaluation of PPLs Corrective Action Plans to Address Substantive
Cross-Cutting Issues P.1(c), Evaluation of Identified Problems, and H.2(c), Procedure
Quality.
a. Inspection Scope
The inspectors reviewed PPLs corrective actions to address substantive cross-cutting
issues P.1(c), Evaluation of Identified Problems, and H.2(c), Procedure
Quality/Procedure Use and Adherence. The inspectors evaluated PPL staffs
performance in addressing the P.1(c) and H.2(c) SCCI and corrective action plan
implementation. The standards applied to the inspection are the performance attributes
contained within NRC inspection procedure 71152, Problem Identification and
Resolution, as related to corrective action implementation and effectiveness reviews.
Documents reviewed are listed throughout the body of the report and in the Attachment.
The P.1(c) cross-cutting theme was first identified in the 2010 Annual Assessment Letter
(ML110620317), dated March 4, 2011, and remained open as documented in the 2011
End-of-cycle Assessment (ML12061A021) and 2012 Mid-cycle Assessment
(ML12248A066) letters. The H.2(c) cross-cutting theme was first identified in the 2011
Mid-cycle Assessment Letter (ML112430469), dated September 1, 2011, and remained
open as documented in the 2012 Mid-cycle Assessment Letter (ML12248A066).
b. Findings and Observations
No findings were identified.
PPL Corrective Actions Related to CAP - Evaluations (P.1(c))
PPL staff implemented corrective actions to address the P.1(c) substantive cross-cutting
issue as identified in their Performance Improvement Integrated Matrix (PIIM). This
document describes seven elements intended to improve PPLs CAP performance. The
inspectors determined that PPL made progress in implementing corrective actions with
the following observations:
In 2011, PPL staff identified a significant contributing cause to for quality issues
with corrective action program (CAP) evaluations was insufficient staff skill and
understanding of process for performing root cause, apparent cause and lower
level cause evaluations. To correct this, since 2011, PPL implemented
qualification-based CAP training to employees and supervisors responsible for
performing evaluations. The training was developed to improve evaluation
quality and enhance staff knowledge on how to perform, review, and approve
CAP evaluations. Corrective actions to improve evaluation quality are in
progress and include PPLs actions to discuss evaluation quality in leadership
and all-hands meetings, increased management participation in corrective action
review boards (CARBs), and Training Needs Analyses (1547326) to make
adjustments to evaluation training as needed.
Since May 2011, PPL instituted Departmental Corrective Action Review Boards
(DCARBs), which are intended to improve evaluation quality before the
evaluations are submitted to the stations CARB for approval. The inspectors
reviewed PPL procedure NDAP-00-0761, Departmental Corrective Action
Enclosure
46
Review Board, and determined that PPL engineering department staff did not
adhere to the procedure requirement (step 2.2.2) for sampling level 3 evaluations
at DCARB. The inspectors determined this issue was a performance deficiency
and a minor finding related to PPLs procedural requirements. However, this
issue is not a violation of NRC requirements. PPL staff entered this issue into
the CAP (1651434).
PPL staff completed an evaluation (1502875) of the quality of operability
determinations, which determined that the appropriate level of rigor was not
being consistently applied in the performance of initial operability determinations
by operations personnel. In response, PPL staff completed a training needs
analysis (1383039). Full training for senior reactor operators (SROs) on
operability determinations has not yet been completed due to the availability of
the desired training vendor. In the interim, PPL staff has provided supplemental
training on operability determinations to SROs, and instituted additional peer
checks of operability determinations. Self assessments completed since the
interim training began (1521473) have concluded there is improvement in
operability evaluation quality. The inspector also noted there were no NRC
findings related to Operability Determinations over the last two quarters.
In December 2011, PPL staff determined that from a risk perspective, many
Level 3 CR evaluations within the stations backlog did not require evaluations
but were important to include in the CAP for trending. Corrective Action Program
Coordinator - Performance Improvement Coordinators (CAPCO PICs) review
these items periodically (CAP Health Days) and have determined many of the
items could be rescreened to a lower significance level in accordance with site
procedures. PPL staff also determined that many CRs were written with
insufficient problem descriptions, which made it difficult for the evaluators and the
Management Review Committee (MRC) screening team to understand the scope
of the problem. PPL staff has rescreened many of these CRs in accordance with
site procedures. Additionally, PPL staff instituted training for evaluators and
supervisors to improve upon the problem descriptions in CRs they approve.
These actions are attributed to a reduction in backlog with over 1030 corrective
actions closed since May 2012.
PPL Corrective Actions Related to Procedure Quality (H.2(c))
PPL implemented corrective actions to address procedure quality issues as identified in
the PIIM, which is intended to improve procedure quality, usage, and adherence.
Included in these corrective actions is the establishment of a site procedure group and a
procedure upgrade project. These items were inspected by the NRC during the conduct
of the NRC 95002 supplemental inspection follow-up in November 2012. The inspection
results for the site procedure group and procedure upgrade project are documented in
NRC inspection report 05000387/2012011.
The inspector determined that PPL has made progress in creating and implementing
corrective actions to address the H.2(c) substantive cross-cutting issue; however, some
items in the plan are in their early stages. The inspector noted the following
observations:
Enclosure
47
In April 2011, PPL completed a root cause evaluation (1389530) that determined
the station had less than adequate procedures due to a failure to incorporate
best industry guidance for procedure quality. Additionally, the root cause
evaluation identified that PPL had less than adequate management oversight in
reinforcing expectations for procedure use and adherence. Training sessions
conducted in January 2012 on procedure use and adherence revealed that many
supervisors were not adhering to or were not knowledgeable of existing
procedure usage standards (verifying current revision, place-keeping, signoffs,
use of not applicable, and general adherence requirements). A four-hour
classroom-based course was created and given to over 1000 PPL employees,
which focused on establishing rules and standards for procedure use to ensure
safe, effective control of work activities.
PPL evaluated the sites progress in procedure use and adherence through
effectiveness reviews, CR trending, and the use of Observation Way (an
employee observation database). Since January 2012, PPL has completed
15 effectiveness reviews which have shown through interviews that personnel
are being more critical, are demonstrating the desired procedure use and
adherence behaviors, and are identifying procedure issues during their work
activities. CR trending data shows that a total of 1589 CRs have been issued
since January 2012 which identify procedure issues for action and evaluation.
Additionally, 581 more procedure issues have been identified in 2012 than in
2011. The CRs also indicate that the number of procedure noncompliance
events have decreased from 32 events in the 3rd quarter 2011 to 11 events in the
3rd quarter 2012.
Observation Way data indicated a difference in behaviors associated with
procedure use and adherence fundamentals. In 2012, 1019 observations were
made of individuals who demonstrated a questioning attitude and stopped a job
when unsure about a procedure issue. PPL staff has interpreted this data as
evidence that the corrective actions from the root cause evaluation (1389530)
have resulted in the station personnel identifying more issues related for
procedure quality while procedures are in use in the field, and initiating actions
to address those issues vice working around procedure issues.
The inspectors reviewed the progress of the site procedure upgrade group to improve
procedure quality and found that at the time of the inspection the station had completed
333 procedure upgrades of the 700 high priority procedures. The station currently has
more than 4000 additional procedures that are being considered for upgrade over the
next several years. Though many of these non-upgraded procedures are in use in the
field, comments in Observation Way and interviews with plant personnel indicate
employees are raising concerns about existing procedures that have quality and usage
issues. PPL has corrective actions in place to continue reviewing and upgrading the
balance of the procedures.
4OA3 Follow-up of Events and Notices of Enforcement Discretion (71153 - 6 samples)
.1 Plant Events
a. Inspection Scope
Enclosure
48
For the plant events listed below, the inspectors reviewed and/or observed plant
parameters, reviewed personnel performance, and evaluated performance of mitigating
systems. The inspectors communicated the plant events to appropriate regional
personnel, and compared the event details with criteria contained in IMC 0309,
Reactive Inspection Decision Basis for Reactors, for consideration of potential reactive
inspection activities. As applicable, the inspectors verified that PPLs operators made
appropriate emergency classification assessments and properly reported the event in
accordance with 10 CFR Parts 50.72 and 50.73. The inspectors reviewed follow-up
actions related to the events to assure that PPL staff implemented appropriate corrective
actions commensurate with their safety significance.
Unit 2, Manual reactor scram following failure of the integrated control system on
November 9, 2012
Unit 2, Automatic reactor scram during control valve testing on December 16, 2012
Unit 2, Automatic reactor scram during plant startup on December 19, 2012
b. Findings
Introduction. Inspectors identified a Severity Level IV NCV of 10 CFR 50.72(b)(3)(iv)(A)
and (B) when PPL operators did not report a valid actuation of the Unit 2 reactor
protection system (RPS) on November 9, 2012 within eight hours of occurrence as
required.
Description. On November 9, 2012 at 1:17 a.m., Unit 2 was manually scrammed
following a failure in the integrated control system (ICS) and a subsequent lowering of
reactor water level. This failure rendered the control of reactor feedwater and
recirculation pump speed ineffective. Following the scram, reactor water level lowered,
the RCIC and HPCI systems automatically initiated, reactor recirculation pumps tripped
and containment isolations occurred as designed. Operators entered the appropriate
procedures. The operators overrode HPCI to prevent its injection, and restored reactor
water level using RCIC to a band of 13 to 30 inches in accordance with station
procedures.
During the post-transient response, a reactor operator was controlling RCIC using a
wide range reactor vessel level indicator in the vicinity of the RCIC control station. As
reactor temperature and pressure decreased due to cooldown, the level indications
displayed on wide range and narrow range began to diverge due to the fact these
instruments are calibrated under hot and full pressure conditions. At 4:20 a.m., while
wide range reactor water level indicated 24, narrow range level reached approximately
15 inches, and an automatic RPS scram was generated. Investigation determined that
the low reactor water level scram switches are conservatively calibrated to 15 inches.
Operators again entered applicable procedures and completed the scram response
actions. Although no rod motion occurred due to all rods having been previously
inserted, a valid reactor scram was initiated and the system responded as required.
PPL submitted a four-hour report in accordance with 10 CFR 50.72(b)(2)((iv)(A) and (B)
at 03:03 on November 9 (EN 48496) for the original scram as required. However, the
following day the inspectors questioned whether PPL operators had made an eight-hour
report regarding the second reactor scram and associated containment isolation signals.
10 CFR 50.72 (b)(3)(iv)(A) requires an eight hour report for any valid actuation of the
RPS system unless part of a preplanned test or in accordance with a procedure (such
Enclosure
49
as reactor shutdown). The inspectors raised the concern to the PPL management and
PPL staff determined that a second report had not been made, and as a result of the
inspectors questions determined a report one was required. PPL staff subsequently
submitted the report at 4:20 p.m. on November 10, 2012 (EN 48500).
The inspectors noted that NUREG 1022 Revision 2, Event Reporting Guidelines: 10
CFR 50.72 and 50.73, clarifies that the event was reportable. Examples listed for RPS
actuation include a scram signal generated with the plant in mode 3. An ENS
notification and LER are both required because, although the systems' safety functions
had already been completed, the RPS scram and primary containment isolation signals
were valid and the actuations were not part of the planned procedure. The automatic
signals were valid because they were generated from the sensor by measurement of an
actual physical system parameter that was at its set point.
The NRC was aware of both scrams, and no regulatory decisions were impacted due to
the report for the second scram being made late.
Analysis. Not making a timely eight hour notification in accordance with 10 CFR 50.72
was a performance deficiency within PPLs ability to foresee and correct. The per-
formance deficiency was evaluated in accordance with IMC 0612, Appendix B, and
traditional enforcement was determined to apply because this was a reporting failure
and therefore had the potential to impact the regulatory process. The issue was
evaluated using the Enforcement Policy and determined to be similar to example 6.9.d.9,
a licensee fails to make a report required by 10 CFR 50.72 or 10 CFR 50.73. This is
an example of a Severity Level IV violation.
Because this violation involves the traditional enforcement process and does not have
an underlying technical violation that would be considered more-than-minor, inspectors
did not assign a cross-cutting aspect to this violation in accordance with IMC 0612,
Appendix B.
Enforcement. 10 CFR 50.72(b)(3)(iv)(A) requires, in part, that any event or condition
that results in valid actuation of any of the systems listed in paragraph (b)(3)(iv)(B) of this
section shall be reported within eight hours, except when the actuation results from and
is part of a pre-planned sequence during testing or reactor operation. 10 CFR
50.72(b)(3)(B) states, in part, The systems to which the requirements of paragraph
(b)(3)(iv)(A) of this section apply are: (1) Reactor protection system (RPS) including:
Reactor scram and reactor trip. Contrary to the above, PPL did not make a timely
notification within eight hours of a valid RPS actuation, which occurred on November 9,
2012. Because this violation was of very low safety significance, was not repetitive or
willful, and was entered into PPLs CAP (CR 1643098), this violation is being treated as
an NCV consistent with the NRC Enforcement Policy. (NCV 05000388/2012005-06,
Failure to Make a Timely Report for a Valid Actuation of RPS)
.2 (Closed) Licensee Event Report (LER) 05000387/2012-005-00: Valve Internal
Misalignment resulting in Multiple Inoperable Main Steam SRVs
a. Inspection Scope
In April 2012, during the Unit 1 outage, two main steam SRVs failed to meet the setpoint
criteria of +3 to -5 percent set forth in TS 3.4.3. Both SRVs actuated at a setpoint less
Enclosure
50
than the -5 percent criteria. The cause of the lower actuation was attributed to valve
internal misalignment. PPL determined the event to be a common cause inoperability
of independent trains or channels and reportable under 10 CFR 50.73(a)(2)(vii). Both
SRVs would have relieved pressure before exceeding +3 percent. Therefore, the SRV
safety function, described in UFSAR 5.2.2.1.1, to prevent over-pressurization of the
reactor coolant pressure boundary, was not violated. In addition, TS 3.4.3 required the
safety function of 14 of the 16 SRVs to be operable. With both SRVs outside of their
allowable TS setpoint criteria, 14 SRVs still remained operable. There were no actual
adverse consequences as a result of this event.
The inspectors reviewed this LER, including PPL's evaluations and associated corrective
actions. The inspectors did not identify any additional performance deficiencies related
to this issue. This LER is closed.
b. Findings
No findings were identified.
.3 (Closed) Licensee Event Report (LER) 05000387/2012-007-00 and LER
05000387/2012-007-01: Unplanned Shutdown due to Unidentified Drywell Leakage
a. Inspection Scope
On June 19, 2012, PPL conducted a reactor shutdown of Unit 1 and entered the drywell
to investigate the source of an increasing trend in drywell unidentified leakage. PPL
discovered that the source of the leakage was from a through-wall crack on the A
reactor recirculation loop decontamination connection. The crack was determined to
have been a fatigue-related failure due to cyclic vibration. LER 50-387/2012-007-00 was
issued on Aug 17, 2012 and LER 50-387/2012-007-01 was issued November 20, 2012
to update the original LER with the results of the RCA.
The inspectors reviewed this LER, including PPL's evaluations and associated corrective
actions. The inspectors did not identify any additional issues during the review of the
LERs. These LERs are closed.
b. Findings
A self-revealing Green NCV was identified and is discussed in section 4OA2 of this
report.
.4 (Closed) Licensee Event Report (LER) 05000388/2011-002-01: Condition Prohibited by
Technical Specification due to Unknown RCIC lnoperability
a. Inspection Scope
On June 29, 2011, during startup from a refueling outage, operations personnel
conducted the Unit 2 reactor core isolation cooling (RCIC) system quarterly flow
surveillance. During the testing, RCIC tripped on overspeed. Subsequent trouble-
shooting determined the problem to be failure of the ramp generator signal converter
(RGSC). An engineering evaluation determined that RCIC had been inoperable as a
result of the RGSC problem on June 27, 2011 when the plant exceeded 150 psig and
Enclosure
51
the RCIC LCO became applicable. This constituted a condition prohibited by plant TSs
and was reported to the NRC as LER 05000388/2011-002-00. This LER reported the
apparent cause as unexpected, random failure of the RGSC. The NRC reviewed this
LER and closed it in inspection report 05000388/2011005 with a Green NCV that
identified the failure was maintenance induced. Revision 1 to this LER was submitted in
May 2012 with results of a revised RCA.
The inspectors reviewed this LER, PPL's revised RCA, and associated corrective
actions. This LER is closed.
b. Findings
No findings were identified.
4OA5 Other Activities
.1 (Closed) NRC Temporary Instruction (TI) 2515/187 - Inspection of Near-Term Task
Force Recommendation 2.3 Flooding Walkdowns
a. Inspection Scope
Inspectors verified that the PPLs walkdown packages for 1) ESSW pump house Area 55
elevation 685 and 660, 2) EDG building Area 43 elevation 660, 3) Unit 1 Reactor
Building (RB) Area 25 elevation 645, and 4) E EDG building Area 81 elevation 656,
contained the elements as specified in NEI 12-07 Walkdown Guidance document:
The inspectors accompanied PPL staff on their walkdown of both Unit 1 RB Area 25
elevation 645 and E EDG building Area 81 elevation 656 and verified that PPL staff
confirmed the following flood protection features:
Visual inspection of the flood protection feature was performed if the flood protection
feature was relevant. External visual inspection for indications of degradation that
would prevent its credited function from being performed was performed.
Critical SSC dimensions were measured.
Available physical margin, where applicable, was determined.
Flood protection feature functionality was determined using either visual observation
or by review of other documents.
The inspectors verified that noncompliance with current licensing requirements, and
issues identified in accordance with the 10 CFR 50.54(f) letter, Item 2.g of Enclosure 4,
were entered into PPL's CAP. In addition, issues identified in response to Item 2.g that
could challenge risk significant equipment and PPLs ability to mitigate the
consequences will be subject to additional NRC evaluation.
b. Findings
No findings were identified.
.2 (Closed) NRC Temporary Instruction (TI) 2515/188 - Inspection of Near-Term Task
Force Recommendation 2.3 Seismic Walkdowns
Enclosure
52
a. Inspection Scope
The inspectors accompanied PPL on their seismic walkdowns of 1) Unit 2 Reactor
Building 645 on August 15, 2012, 2) Unit 1 Reactor Building 719 on September 25, 3)
Unit 2 Reactor Building 670 on September 26, and 4) Unit 2 Control Structure 771 on
September 21, and verified that PPL confirmed that the following seismic features
associated with the Unit 2 HPCI Steam Supply Valve (HV255F001), Unit 1 120 VAC
Instrument Distribution Panel (1Y236), Unit 2 ESS Division I 480V MCC (2B219), and
Unit 2 RHR/RCIC Relay Panel Division 2 (2C618), respectively, were free of potential
adverse seismic conditions as applicable:
Anchorage was free of bent, broken, missing or loose hardware.
Anchorage was free of corrosion that is more than mild surface oxidation.
Anchorage was free of visible cracks in the concrete near the anchors.
Anchorage configuration was consistent with plant documentation.
SSCs will not be damaged from impact by nearby equipment or structures.
Overhead equipment, distribution systems, ceiling tiles and lighting, and masonry
block walls are secure and not likely to collapse onto the equipment.
Attached lines have adequate flexibility to avoid damage.
The area appears to be free of potentially adverse seismic interactions that could
cause flooding or spray in the area.
The area appears to be free of potentially adverse seismic interactions that could
cause a fire in the area.
The area appears to be free of potentially adverse seismic interactions associated
with housekeeping practices, storage of portable equipment, and temporary
installations (e.g., scaffolding, lead shielding).
The inspectors independently performed walkdowns of the following equipment and
verified they were free of the above listed adverse seismic conditions, as applicable:
Unit 1, 1D653A, 250VDC engineering safeguard system (ESS) Division I Battery
Charger A, in the Control Structure, on November 21, 2012
Common, HD07812B, CREOAS Inboard Air Supply Damper, in the Control
Structure, on November 21, 2012
Common, 0E506B, EDG B Lube Oil Cooler, in the Diesel Generator building, on
November 21, 2012
Observations made during the walkdown that could not be determined to be acceptable
were entered into PPLs CAP for evaluation.
PPL personnel determined that there were no items that could allow the spent fuel pool
(SFP) to drain down rapidly. No items from the SFP were added to the SWEL.
b. Findings and Observations
No findings were identified.
Enclosure
53
.3 (Closed) Unresolved Item (URI) 05000387;388/2011005-05, RCIC Low Pressure
Surveillance Requirement (SR)
a. Inspection Scope
Inspectors reviewed URI 05000388/2011005-05. This URI was initiated to determine
whether PPLs implementation of TS SR 3.5.3.4 appropriately verified RCIC system
operability. Specifically, the implementing procedure, SO-250-005, 24 Month RCIC
Flow Verification, Revision 17, did not initiate RCIC with its flow controller in automatic
at reactor pressure of 150 psig and verify the RCIC pump provided rated flow within 30
seconds. This procedure tested the RCIC system in manual at 150 psig and in
automatic at rated pressure. Inspectors reviewed PPLs evaluations and operability
determinations, the UFSAR, power uprate analysis and discussed the potential issue
with Nuclear Reactor Regulation staff (NRR).
b. Findings
No findings were identified.
Based on a conference call with NRR technical staff and inspectors on October 11,
2012, inspectors determined that PPL did not establish the conditions assumed in the
accident analysis in their implementing procedure SO-250-005, 24 Month RCIC Flow
Verification, Revision 17, for the low pressure RCIC surveillance test. This
determination was based, in part, on the UFSAR and power uprate analysis which
assume that the RCIC system will start automatically. These requirements were
translated into power uprate test criteria which states that the average RCIC pump
discharge flow shall be equal to or greater than the 100% rated value within 30 seconds
from automatic initiation at any reactor pressure between 150 psig and rated.
The inspectors identified a violation of 10 CFR 50, Appendix B, Criterion XI, Test
Control, which states, in part, that a test program shall be established to assure that all
testing required to demonstrate that SSCs will perform satisfactorily in service is
identified and performed in accordance with written test procedures which incorporate
the requirements and acceptance limits contained in applicable design documents.
Contrary to this, PPL did not ensure that test conditions specified in TS SR implementing
procedures were consistent with conditions assumed in the UFSAR accident analysis
and test the RCIC system in automatic at both 150 psig and rated pressure. Inspectors
determined this violation was not more than minor based on review of PPLs operability
determination, which provided reasonable assurance of operability for the short period of
exposure that the issue covered (reactor pressure of at approximately 150 psig which
only occurs during plant startup and shutdown.) Additionally, PPL staff subsequently
revised the surveillance procedure and satisfactorily performed the low-pressure
surveillance test with the flow controller in automatic on each unit. This failure to comply
with 10 CFR 50, Appendix B, Criterion XI, constitutes a minor violation that is not subject
to enforcement action in accordance with the NRCs Enforcement Policy. This URI is
closed.
Enclosure
54
4OA6 Meetings, Including Exit
On January 25, 2013, the inspectors presented the inspection results to Mr. T. Rausch,
Chief Nuclear Officer (CNO), and other members of the PPL staff. PPL acknowledged
the findings. No proprietary information is contained in this report.
4OA7 Licensee-Identified Violations
No findings were identified.
ATTACHMENT: SUPPLEMENTAL INFORMATION
Enclosure
A-1
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee Personnel
A. Alley, Medical review Officer
T. Case, Licensing Engineer
M. Crowthers, Manager, Licensing
N. Davis, Senior Engineer, Performance Improvement
R. Edwards, Mechanical Engineer
C. Goff, Training Director
J. Goodbred, Jr., Operations Manager
K. Griffith, Licensed Operator Requalification Program Lead
J. Grisewood, Manager, Performance Improvement
D. Hackenberg, Mechanic Leader
J. Helsel, Site Vice President (Acting), Plant General Manager
F. Hickey, Senior Health Physicist, Chemistry
C. Hoffman, Manager, Nuclear Fuels
T. Iliadis, General Manager, Nuclear Operations
J. Jennings, Manager, Performance Improvement
G. Kanouse, Medical Doctor, Berwick Hospital
T. Magrone, Chemistry Technician
M. Micca, Radwaste Shipper
S. Muntzenberger, Supervisor, Mechanical Engineering
B. ORourke, Licensing Engineer
C. Parks, Site Nurse
G. Pennycoff, Chemistry Technician
J. Petrilla, III, Supervisor, Regulatory Affairs
B. Rigotti, Senior Engineer
C. Ringer, Instrument and Control (I&C) Technician - Level II
R. Rodriguez-Gilroy, Radiological Operations Supervisor
R. Thomann, Support Engineer
R. Thompson, Simulator Instructor
J. Tripoli, Manager Regulatory Affairs
J. Seroka, System Engineer, Ventilation
K. Spako, McCarls Worker
R. Stigers, Radwaste Specialist
R. Streeper, Operations Training Manager
NRC Personnel
K. Hoffman, Materials Engineer
K. Mangan, Senior Reactor Inspector
Attachment
A-2
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
05000387;388/2012005-05 URI Concerns Regarding PPLs Program for
Conducting Biennial Medical Examinations for
Licensed Operators and Reporting Changes in
Medical Conditions (Section 4OA2)
Opened/Closed
05000388/2012005-01 NCV Failure to Demonstrate Effective Preventive
Maintenance Under 50.65(a)(2) (Section 1R12)05000387/2012005-02 NCV Failure to Report Common-Cause Inoperability of
Independent Trains (Section 1R12)
05000387;388/2012005-03 NCV Failure of Full-Scale Drill Critique to Identify an
RSPS Weakness (Section 1EP6)05000387/2012005-04 NCV Improper Stress Intensification Factor Results in
RCS Pressure Boundary Leak (Section 4OA2)05000388/2012005-06 NCV Failure to Make a Timely Report for a Valid
Actuation of RPS (Section 4OA3)
Closed
05000387/2012-005-00 LER Valve Internal Misalignment resulting in Multiple
05000387/2012-007-00 LER Unplanned Shutdown due to Unidentified Drywell
Leakage
05000387/2012-007-01 LER Unplanned Shutdown due to Unidentified Drywell
Leakage
05000388/2011-002-01 LER Condition Prohibited by Technical Specification
due to Unknown RCIC lnoperability
05000387;388/2011-005- URI RCIC Low Reactor Pressure SR
05
Discussed
05000387;388/2011-004-01 NOV Failure to Report a Disqualifying Operator
Medical Condition (Section 4OA2)
Attachment
A-3
LIST OF DOCUMENTS REVIEWED
(Not Referenced in the Report)
Section 1R01: Adverse Weather Protection
Procedures:
ON-104-001, Unit 1 Response to Loss of All Offsite Power, Revision 20
ON-000-002, Natural Phenomena, Revision 28
NDAP-00-0030, Severe Weather Preparations (Winter Storm, Hurricane), Revision 3
NDAP-QA-0024, Winter Operation Preparations, Revision 18
Condition Reports:
1522033, 1634874, 1654254*, 1654346, 1653636, 1640160*, 1639176, 1638800*, 1649975,
1647930, 1644298, 1644295, 1632320, 1631176, 1635181, 1635281, 1635250,
1617475, 1619820, 1624490, 1631176, 1612958, 1606545
Work Order:
1578318
Section 1R04: Equipment Alignment
Procedures:
CL-003-0011, Common 13.8kV System, Revision 2
CL-003-0012, Startup Transformers T10 and T20 (OX103 and OX 104), Revision 4
OP-003-003, Startup Bus 20 0A104 T20 Outage and Restoration, Revision 1
CL-054-0012, Common ESW System Mechanical, Revision 19
CL-054-0014, Unit 1 ESW System Mechanical, Revision 17
OP-054-001, ESW System, Revision 35
OP-249-001, RHR System, Revision 41
SO-249-001, Monthly RHR Alignment Check, Revision 25
CL-249-0015, Unit 2 RHR System - Division II Mechanical, Revision 18
CL-249-0018, Unit 2 RHR System - Common Mechanical, Revision 12
CL-249-0014, Unit 2 RHR System - Division II Electrical, Revision 11
OP-024-001, DG, Revision 64
SO-024-001A, Monthly DG A Operability Test, Revision 12
Condition Reports (* NRC identified):
1638800*, 1644374, 1524795, 1524808, 1610241, 1355642, 1425464, 1528173
Drawings:
M-134, Sheet 1, Common P&ID A, B, C, D DG Auxiliaries, Revision 49
M-134, Sheet 2, P&ID A-D Diesel Auxiliaries - Starting Air, Revision 18
M-134, Sheet 3, P&ID A-D Diesel Auxiliaries - Starting Air, Revision 16
M-134, Sheet 4, P&ID A-D Diesel Auxiliaries - Jacket Water and Lube Oil Storage Systems,
Revision 9
Miscellaneous:
Operations Logs for Units 1 and 2, dated October 27 - 30, 2012
TM-OP-024-ST, EDG A-D, Revision 11
TM-OP-024-ST, EDGs A-D, Revision 12
Attachment
A-4
Section 1R05: Fire Protection
Procedures:
OP-234-002, RB Heating, Ventilation, and Air Conditioning (HVAC) Zones 2 and 3, Revision 44
ON-013-001, Response to Fire, Revision 33
FP-213-245, HE and Pump Access Area (Fire Zone 2-3A), Elevation 683, Revision 5
FP-113-113, Containment Access Area (I-401, I-404, I-405) Fire Zones 1-4A-N, -S, -W,
Elevation 719
FP-013,139, Unit 1 Lower Relay Room C-203 Fire Zone O-24D, Elevation 698-0, Revision 8
FP-013-150, Unit 1 Lower Cable Spreading Room C-300 Fire Zone 0-25E, Elevation 714-),
Revision 6
FP-213-239, RCIC Pump Room (II-12), Fire Zone 2-10, Elevation 6450, Revision 7
FP-213-238, HPCI Pump Room (II-11), Fire Zone 2-1C, Elevation 6450, Revision 5
Section 1R11: Licensed Operator Requalification Program
Procedures:
EO-100-102, RPV Control, Revision 8
EO-100-103, Primary Containment Control, Revision 9
EO-100-112, Rapid Depressurization, Revision 7
GO-100-002, Plant Startup, Heatup, and Power Operation, Revision 79
GO-100-005, Plant Shutdown to Hot/Cold Shutdown, Revisions 55 and 56
GO-100-004, Plant Shutdown to Minimum Power, Revision 60
Miscellaneous:
10CFR55.46, 49, 59, 55.45a(2) - a(3)
OP002-406
OP002-310
Startup Control Rod Sequence A1, Unit 1, Cycle 18
Section 1R12: Maintenance Effectiveness
Procedures:
OP-202-001, 125V DC System, Revision 19
NEPM-GA-1170, Through Wall Leakage in Class 3 Rain Water Systems, Revision 1
SI-178-201D, Weekly Functional test of Intermediate Range Monitor (IRM) Channel 1D,
Revision 6
Condition Reports:
1570413, 627323, 793337, 725347, 1571290, 1571862, 1571988, 1572356, 1571200, 1575809,
1636870, 1636945, 1083716, 725352, 1571862, 1571290, 1083716, 1468821, 1571988,
1091728, 1496655, 1498290, 1575062, 1501084, 1649605, 1646629, 1647950,
1647156, 1648135, 1646704, 1646788, 1646629, 1646792*,1646005, 1646237,
1286903, 1138347, 1636752*, 1636746, 1635356, 1634937, 1635728, 1634551,
1635356, 1632988, 1637562, 1633113, 1633341, 1633101, 1527146, 1602279,
1607032, 1607178, 1603839, 1602376, 1602373, 1607037
Work Orders:
1497855, 1497848, 1511889, 1527055, 1638746, 1577438, 1496680, 1643158, 1643161
Attachment
A-5
Miscellaneous:
Engineering Work Request (EWR) 1643161
Maintenance Rule Expert Panel Meeting Minutes, Meeting Number 2012-1025
MRFF Evaluation Summary, MRFF CR Number: 1496655/1501084, October 25, 2012 Expert
Panel
Maintenance Rule Basis Document - System 02, 125V DC, dated October 9, 2012
Maintenance Rule Basis Document - System 50, RCIC, dated October 9, 2012
ASME Code Case N-513-3, Evaluation Criteria for Temporary Acceptance of Flaws in
Moderate Energy Class 2 or 3 Piping,Section XI, Division I
M&P Laboratory Report QR-0297, dated March 9, 2006
GE SIL 496, Electrical Protection Assembly Performance, Revision 1
Maintenance Rule Basis Document, System 58, RPS
Maintenance Rule Basis Document, System 78, Nuclear Instrumentation
TM-OP-056A-ST, Reactor Manual Control System, Revision 5
Maintenance Rule Basis Document, System 56, Control Rod Manual Control
Section 1R13: Maintenance Risk Assessments and Emergent Work Control
Procedures:
NDAP-QA-0340, Protected Equipment Program, Revision 18
NDAP-QA-1902, Integrated Risk Management, Revision 9
NDAP-QA-1902, Integrated Risk Management, Revision 9
Condition Reports (* NRC-identified):
162875, 1634526*
Action Request:
1510008
Work Orders:
1468533, 1603991, 1101487, 1376695, 1440681, 1616046, 1599832
Miscellaneous:
PEPETF for 149F007B
Equipment-Out-of-Service (EOOS) Run for Unit 1, October 15, 2012
Sapphire 8 Spar Model
PEPETF for B ESW
EOOS Run for Unit 1 and Unit 2, October 17, 2012
Section 1R15: Operability Evaluations
Procedures:
NDAP-QA-0703, Operability Assessments and Requests for Enforcement Discretion,
Revision 21
NDAP-QA-0423, Station Pump and Valve Testing Program, Revision 24
SO-216-A03, Quarterly RHRSW Flow Verification Division I, Revision 6
AR-208-001, RCIC System 2C601, Revision 21
SO-250-002, Quarterly RCIC Flow Verification, Revision 43
SO-100-007, Revisions 56 and 57
SO-200-007, Revisions 55 and 56
RE-ITP-023, Revision 11
Attachment
A-6
RE-ITP-024, Revision 10
NDAP-QA-0752, Cause Analysis, Revision 16
SO-200-011, Reactor Vessel Temperature and Pressure Recording, November 11, 2012,
Revision 18
Calculations:
EC-062-0573, Study to Support the Bases Section of TS 3.4.10, Revision 1
EC-062-1072, Revised Pressure Temperature Curves for Units 1 and 2, Revision 0
EC-062-0595, Evaluation of Out of Limit Reactor Pressure Vessel (RPV) Cooldown and Heatup
Rate Occurring on February 12, 1989
Condition Reports (* NRC-identified):
1626384, 1627430, 1625663, 1632998, 1633011, 1633216, 1594228, 1594716, 1632238,
1444679, 1632488, 1549881, 1599794, 1499803, 1599447, 1514292, 1630823*,
1622882*, 1537511, 1639429*, 1639432*, 1639428*, 1639403*, 1636681, 1584097*,
1643198*
Work Orders:
154772, 1643156
Miscellaneous:
Operations Logs Assistant Operations Manager Directive 12-04
IOM 182, CS, RB, TB, and RW Building Supply and Exhaust Filters, Revision 15
TS and TSB 3.7.3, 5.5.7, 5.5.14
FSAR Chapter 6, 15, and 915
NEI 99-03, Control Room Habitability Assessment, June, 2001
PLA-3654, Response to RAI: Enforcement Action 89-042
GE SIL 430, RPV Temperature Monitoring
GE-SIL 251, Control of RPV Bottom Head Temperatures and Supplement 1
NRC IR 05000387;388/1991-18
Section 1R19: Post-Maintenance Testing
Procedures:
MT-GE-005, Westinghouse 15KV Circuit Breaker and Switchgear Inspection and Maintenance,
Revision 31
SO-153-004, October 4, 2012
MT-GM-011, Valve Packing/Live Loading/Investigation, Revision 25
NDAP-QA-0515, Control and Calibration of Plant Measuring and Test Equipment (M&TE),
Revision 8
OP-164-001, Reactor Recirculation System, Revision 64
NDAP-QA-0482, Post-Maintenance Testing, Revision 6
MT-64-013, N-7500 Reactor Recirculating Pump Seal Installation and Removal, Revision 5
SO-260-001, Quarterly LOCA Test of Drywell Area Unit Coolers/Fans, Revisions 11, 12,
and 13
SO-249-805, Quarterly RHR LOOP B Valve Exercising, Revision 12
SO-249-802, Quarterly RHR System Flow Verification, Division II, Revision 17
Attachment
A-7
Condition Reports (*NRC-identified):
1627252, 1627553, 1627632, 1627635, 1628266, 1630826, 1629644, 1629159, 1634913,
1634440, 1634485, 1638291*, 1639382*, 1630214, 1631025, 1611369, 208309,
207934, 1527004, 1640858, 1639840, 1646899*, 1643759, 1643087*
Work Orders:
1068151, 1078195, 1538898, 1595917, 1451837, 1042880, 1046251, 1597911, 1635411,
1631976, 1630834, 11630223, 1632384, 1640404, 1640974, 1605927, 1640859,
1437034, 897318, 1527017, 1635559
Drawings:
E-224, Sheet 4, Unit 2 Schematic Diagram Drywell Area Cooling Fans , Revision 20
Miscellaneous:
Field test Evaluation HV252F031A, October 9, 2012
Unit 1 Operations Logs, October 26, 2012
ASME Section XI IWA-4540 and IWA 5243, 1995 Edition with 1997 Addenda and 1998 Edition
with 2000 Addenda, ML 092740004
TS and TSB 3.6.1.5, 3.6.3.2
FSAR 9.4.5, 6.2.5
Section 1R20: Refueling and Other Outage Activities
Procedures:
GO-100-002, Plant Startup, Heatup, and Power Operation, Revision 79
GO-100-005, Plant Shutdown to Hot/Cold Shutdown, Revisions 55 and 56
GO-100-004, Plant Shutdown to Minimum Power, Revision 60
GO-200-004, Plant Shutdown to Minimum Power, Revision 58
GO-200-005, Plant Shutdown to Hot/Cold Shutdown, Revision 54
OP-249-002, RHR Shutdown Cooling, Revision 52
Condition Reports (*NRC identified):
1637660*, 1637564, 1637558*, 1633107, 1633109, 1633108, 1633256, 1633295, 1633074,
1633307, 1628763, 1628764, 1644287
Miscellaneous:
Startup Control Rod Sequence A1, Unit 1, Cycle 18
Section 1R22: Surveillance Testing
Procedures:
SE-235-301, Revision 9
Non-Destructive Examination (NDE)-Visual Examination (VT)-002, Revision 4
SI-280-301, Quarterly Calibration of Reactor Vessel Pressure Channels (Core Spray System
and LPCI Permissive) Reactor Pressure Greater Than Setting (420 psig)
SO-150-006, RCIC Comprehensive Flow Verification, Revision 10
SO-150-002, RCIC Quarterly Flow Verification, Revision 47
SO-150-004, RCIC Quarterly Flow, Valve Exercising, Revision 29
SO-293-001, Quarterly Turbine Valve Cycling, Revisions 37, 38, and 39
Attachment
A-8
Condition Reports (* NRC identified):
1629100, 1230833, 1230823, 1217911, 162470, 1620757, 1652315, 1652821
Miscellaneous:
BOP-VT-12-209, October 1, 2012
SSES Switching Order, dated December 18, 2012
Section 1EP6: Drill Evaluation
Procedure:
EP-PS-126, Emergency Plan (EP) Communicator: EP-Position Specific Instructions,
Revision 28
Condition Reports:
1641893, 1641933, 1641944, 1643229, 1641405, 1641923, 1641902, 1641881, 1641878,
1641860, 1641932, 1642144, 1642137, 1641923, 1641907, 1641860, 1649645,
1643107, 1643092, 1643184, 1641934, 1642205, 1641940
Miscellaneous:
NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 6
IN 2012-18, Failure to Properly Augment Emergency Response Organizations (ERO)
Section 2RS6: Radioactive Gaseous and Liquid Effluent Treatment
Procedures:
CH-ON-001, SPING Alarm Response, Revision 18
CH-ON-003, Chemistry Requirements for Plant Events, Revision 25
CH-RC-032, Tritium Analysis - Sample Preparation and Analysis, Revision 13
CH-RC-076, Gamma Spectral Analysis, Revision 11
CH-YS-014, SPING Data Collection and System Monitoring, Revision 15
ODCM-QA-003, Effluent Monitor Setpoints, Revision 7
ODCM-QA-008, Radiological Environmental Monitoring Program, Revision 14 and 15
NDAP-QA-1180, Radiological Effluent Monitoring and Control, Revision 7
SC-069-001, Liquid Radwaste Sampling and Pre-Release Analysis, Revision 21
SC-070-001, Standby Gas Treatment Vent Iodine and Particulate Activity, Revision 18
SC-070-002, Standby Gas Treatment Vent Iodine and Particulate Activity, Revision 16
SC-133-101, Unit-1 Turbine Building Vent Iodine and Particulate Activity, Revision 16
SC-133-102, Unit-1 Turbine Building Vent Tritium and Noble Gas Grab Sample Analysis,
Revision 13
SC-134-101, Unit-1 RB Vent Iodine and Particulate Activity, Revision 16
SC-134-102, Unit-1 RB Vent Tritium and Noble Gas Grab Sample Analysis, Revision 13
SC-233-101, Unit-2 Turbine Building Vent Iodine and Particulate Activity, Revision 16
SC-233-102, Unit-2 Turbine Building Vent Tritium and Noble Gas Grab Sample Analysis,
Revision 16
SC-234-101, Unit-2 RB Vent Iodine and Particulate Activity, Revision 16
SC-234-102, Unit-2 RB Vent Tritium and Noble Gas Grab Sample Analysis, Revision 15
Condition Reports:
1348108, 1376390, 1485588, 1491557, 1507526
Attachment
A-9
Audits, Self-Assessments, and Surveillances
QA Audit 1343694, Chemistry/ Effluents Audit Report
Updated Hydrogeologic Investigation Report, January 2011
Release Permits:
2011013, 2011028, 2011071, 2011087, 2011097, 2011141
Release Permits (with out-of-service radiation monitors)
2011003, 2011004. 2012006, 2012077, 2012076, 2012106, 2012109
Section 2RS8: Radioactive Solid Waste Processing and Radioactive Material Handling,
Storage, and Transportation
Procedures:
NDAP-QA-0646, Solid Radioactive Waste Process Control Program, Revision 12
WM-PS-150, 10CFR61 Non-Process Waste Stream Sampling, Revision 2
WM-PS-155, 10CFR61 Sample Shipping and Correlation Factor Determination, Revision 4
WM-PS-160, Radioactive Waste Curie Calculations, Revision 4
Condition Reports (* NRC identified):
1321067; 1351082; 1401530; 1447145; 1488491; 1527095; 1605044; 1508719; 1579742;
1578509; 1543806; 1629175; 1380959; 1505160; 1406109; 1504510; 1402236;
1543803; 1633075; 1633077; 1633078; 1633080; 1633089; 1633091
Miscellaneous:
Radioactive Material Shipments Nos.12-011; 12-015;12-025; 12-064;12-076
Teledyne Brown Engineering Report of Analysis for: control rod drives (CRDs); dry active waste;
condensate bead resin; liquid radwaste filter media; reactor water clean-up; condensate
filtration system backwash media; U-1 SPF clean-up; U-2 SPF clean-up
Quality Assurance Audit #1340786, dated 3/25/11, RP/Solid Radwaste Report
Walkup Assessment of Low Level Radioactive Waste Holding Facility, dated 2/16/12 & 3/2/12
PPL Audit No. 23091, February 15-16, 2011, Toxco Materials Management Center
Nuclear Utilities Procurement Issues Council (NUPIC) Audits:
- 22876, December 13-16, 2011, Studsvik Processing Facility - Erwin, LLC
- 22572; 22698; 22603; 22601; 22600, April 13-29, 2010, EnergySolutions
- 22937, January 24-27, 2011, Teledyne Brown Engineering
- 22873, November 14-18, 2011, GEL Laboratories, LLC
Training Material:
HP230, Revision 1, HAZMAT Training for Health Physics (HP) Technicians
HS053, Revision 2, HAZMAT Training for Container Handlers
EF009, Revision 2, Load Securement Training
Section 4OA1: Performance Indicator Verification
Condition Reports (* NRC identified):
1656747*, 1517915, 1357297, 1656747*
Attachment
A-10
Miscellaneous:
NEI 99-02, Regulatory Assessment PI Guideline, Revision 6
PL-NF-06-002, MSPI Basis Document, Revision 6
NDAP-QA-0737, Reactor Oversight Process (ROP) Performance Indicators, Revision 9
EP-AD-022, Nuclear Emergency Planning Performance Indicators, Revision 3
Alert and Notification System Reliability PI Data, October 2011 - September 2012
Drill and Exercise Performance PI Data, October 2011 - September 2012
Emergency Response Organization Drill Participation PI Data, October 2011 - September 2012
Section 4OA2: Identification and Resolution of Problems
Procedures:
OP-AD-010, Control of Licensed Operator License Status, Restrictions and Requirements,
Revision 6
NTP-QA-31.12, Preparation and Submission of NRC Form 396 - Certification of Medical
Examination by Facility Licensee and NRC Form 398 - Personal Qualifications
Statement - Licensee, Revision 5
ANSI/ANS-3.4-1983, American National Standard Medical Certification and Monitoring of
Personnel Requiring Operator Licenses for Nuclear Power Plants
NDAP-00-0761, Departmental Corrective Action Review Board, Revision 2
NDAP-QA-0702, Action Request and Condition Report Process, Revision 38
OP-023-001, Diesel Fuel Oil System, Revision 32
OP-023-001, Diesel Fuel Oil System, Revision 33
Condition Reports (* NRC identified):
1630609*, 1632818*, 1633719*, 1633700*, 1639335*, 1563931, 1587108, 1602093,
1602094, 1632000, 1632281, 16511165*, 1651391*, 1651419*, 1651434*, 1651844,
1651311, 1651824, 1502875, 1521513, 1602210, 1651434*, 1651844, 1651311,
1651824, 1502875, 1521513, 1602210, 1521488, 1582719 , 1549115, 1619762,
1634551, 1633700, 1406091, 1461742, 1541936, 1541933, 1601934, 1643405,
1641039, 1635196, 1446224, 1642609, 1344049, 1575787 , 1464711, 1629414,
1629416, 1547326, 1619762, 1651119, 1650638, 1650638, 1650020, 1456122,
1570413, 1557151, 1554948, 1557394, 1549033, 1538286, 1383039, 1521473,
1389530, 1653022*, 1653454*
Licensing and Design Basis Documents
Susquehanna Operating License Amendment and NRC Safety Evaluation Report (SER) to
Revise SRV Setpoint Tolerance from +/-1 percent to +/-3 percent (ML020520018), dated
March 7, 2002
Susquehanna Operating License Amendment and NRC SER to Revise SRV Setpoint Tolerance
from +/-3 percent to +3 percent, -5 percent (ML11291A137), dated November 17, 2011
TS 3.4.3 Basis, Safety/Relief Valves, Revision 4
TS 3.4.3, Safety/Relief Valves, Amendment 246
UFSAR Section 5.2.2, Overpressure Protection, Revision 64
UFSAR Section 7.7.1.12Nuclear Pressure Relief System, Revision 64
UFSAR Table 15C.0-2, Input Parameters & Initial Conditions for Transients, Unit 1 Cycle 16,
Revision 64
Calculations, Analysis, and Engineering Evaluations
Apparent Cause Evaluation (ACE) for CR 1399810, Revision 1
ACE for CR 1587108, Revision 0
Attachment
A-11
Miscellaneous:
LaSalle Operating License Amendment and NRC SER to Allow Surveillance of the Relief Mode
of SRV Operation with the Relief-Mode Actuator Uncoupled (ML013170087), dated
December 13, 2001
LER 50-387/2012-005-00, Valve Internal Misalignment Resulting in Multiple Inoperable Main
Steam SRVs, dated August 2, 2012
LER 50-388/2009-001-00, Multiple Test Failures of Main Steam SRVs, dated October 12, 2009
LER 50-388/2011-001-00, Multiple Inoperable Main Steam SRVs, dated July 1, 2011
Main Steam SRV Test Results History from 1985 to 2012
Maintenance Rule Basis Document, Unit 1 Main Steam System, dated September 12, 2012
NRC IR 05000387/2009003 AND 05000388/2009003, dated August 11, 2009
NRC IR 05000387/2010006 AND 05000388/2010006, dated March 15, 2010
NRC IR 05000387/2011005 AND 05000388/2011005, dated February 14, 2012
River Bend Operating License Amendment and NRC SER to Revise SRV Setpoint Tolerance
from +/-3 percent to +3 percent, -5 percent, and Allow Surveillance of the Relief Mode of
SRV Operation with the Relief-Mode Actuator Uncoupled (ML030450307), dated
February 13, 2003
Wyle Labs Test Records for SRVs Serial Numbers N63790-00-0019-112 and
N63790-00-0019-133, dated April 24, 2012 and February 25, 2012, Respectfully
OP002 CSI, Licensed Operator Requalification Program (Training Material), dated May 4,
2012
AD281, Justification of Interim Operation - Operability and Functionality Processes (Training
Material), dated July 23, 2012
AD264, Procedure and Work Instruction Use and Adherence, dated March 17, 2012
AD260, Procedure Writer Training, dated March 15, 2012
Procedure Quality/Procedure Use and Adherence PIIM, dated December 7, 2012
Procedure Quality/Procedure Use and Adherence PIIM, dated November 19, 2012
Station CAP PIIM, dated December 7, 2012
Station CAP PIIM, dated November 5, 2012
Station PIIM, dated September 4, 2012
Quick Hit Self-Assessment, Procedure Use and Adherence, dated September 12, 2012
Susquehanna Station Quarterly Trend Report, 3rd Quarter, 2012
Section 4OA3: Event Followup
Procedures:
EO-200-102, Reactor Vessel Level Control, Revision 8
ON-200-001, Reactor Scram, Reactor Scram Imminent, Revision 23
OP-AD-001, Operations Standards for System and Equipment Operation, Revision 49
OP-AD-327, Post Reactor Transient/Scram/Shutdown Elevation, Revision 26
OP-245-001, RFP and Lube Oil System, Revision 66
AR-204-001, RPS Division 2 2C651, Revision 32
ON-200-101, Scram, Scram Imminent, Revision 23
OP-AD-338, Reactivity Manipulations Standards and Communication Requirements,
Revision 19
GO-200-002, Plant Startup, Heatup, and Power Operation, Revision 67
SO-293-001, Quarterly Turbine Valve Cycling, Revision 37
SI-264-503, 24 Month Logic System Functional Test (LSFT) - Reactor Recirculation Pump Trip
System, Revision 11
SI-264-303, 24 Month Calibration - Reactor Vessel Low Low Level Channels (ATWS - RPT
and ARI), Revision 16
Attachment
A-12
Condition Reports:
1641025, 1643210, 1643098*, 1643098*, 1652339, 1652338, 1652507, 1652316, 1652377,
1652357, 1652391, 1652494, 1652316, 1652315, 1653679, 1653477, 1653479,
1455447, 1655159, 1654635, 1654555, 1654037, 1654158, 1653480, 1653762,
1655563, 1654991, 1654915, 1654258, 1653477, 1654235*, 1653633, 1148033,
1421109
Calculations:
EC-INST-1955, I&C Maintenance Calculation for LISB212N025D, Revision 0
EC-INST-1956, I&C Maintenance Calculation for LISB212N025D, Revision 0
Work Order:
1456387
Drawings:
E-129, Sheet 1, FW RFP Discharge and Bypass Valves, Revision 14
E-129, Sheet 2, FW RFP Discharge and Bypass Valves, Revision 9
M-2142, Sheet 1, Unit 2 P&ID Nuclear Boiler Vessel Instrumentation, Revision 48
MI-B31-275, Sheet 8, Reactor Recirculation Pump and MG Set, Revision 12
M1-B31-275, Sheet 7, Reactor Recirculation Pump and MG Set, Revision 15
Miscellaneous:
NUREG 1022, Event Reporting Guidelines: 10 CFR 50.72 and 50.73, Revision 2
EN 48496 dated November 09, 2012
EN 48500 dated November 10, 2012
Administrative Directive 12-07
TM-OP-045I-ST, Reactor Feedwater Level Control System (ICS/DCS), Revision 03
Startup Control Rod Sequence A1, Unit 2, Cycle 16
Engineering Journal, System 64, Journal ID 1316
Section 4OA5: Other Activities
Condition Reports:
1637421, 1635348, 1635279, 1635281, 1634516, 1634527, 1634536, 1634540, 1634541,
1634557, 1634560, 1634561, 1634562, 1634563, 1634544, 1634554, 1634555,
1634550, 1634559, 1632786, 1631806, 1630573, 1631474, 1630575*, 1630573,
1628346, 1627138*, 1623021, 1623016, 1601043, 1599743, 1599747, 1599726,
1599748, 1596549, 1599391, 1609708*, 1625702*, 1624965*, 1625645*, 1623008*,
1623018*, 1623022*, 1626973*, 1624965*, 1646231*, 1644480*, 16326521624541,
1613781, 1613752, 1613734, 1610459, 1609310, 1609332, 1609320, 1587132,
1618860, 1618312, 1613774, 1613798, 1613805, 1624632, 1624541, 1606132,
1644480*, 1659709
Miscellaneous:
Seismic Walkdown Checklist for: 0E506B, 1D653A, HV255F001, 2C618, 2B219, 1Y236,
HD07812B
Flooding Walkdown Record for: Unit 1 Reactor Building Penetrations on X-25-1 Sh.2
Section A-A, E EDG Building Penetrations on X-81-1 Sh.1 Section A-A
Attachment
A-13
LIST OF ACRONYMS
AC Alternating Current
ACE Apparent Cause Evaluation
ACMP Adverse Condition Monitoring Plan
ADAMS Agencywide Document and Access Management System
ALARA As Low As Is Reasonably Achievable
ANS Alert and Notification System
AR Action Report
ASME American Society of Mechanical Engineers
CAP Corrective Action Program
CAPCO-PIC Corrective Action Program Coordinator - Performance Improvement
Coordinators
CARB Corrective Action Review Board
CCA Common Cause Analysis
CCEMA Columbia County Emergency Management Agency
CFR Code of Federal Regulations
CNO Chief Nuclear Officer
CR Condition Report
CRA Condition Report Action
CRD Control Rod Drive
CREOAS Control Room Emergency Outside Air Supply
CS Control Structure
DCARB Departmental Corrective Action Review Boards
DEP Drill and Exercise Performance
DG Diesel Generator
DH Decay Heat
EAL Emergency Action Level
EDG Emergency Diesel Generator
EHC Electrohydraulic Control
ENS Emergency Notification System
EOOS Equipment Out-of-Service
EOP Emergency Operating Procedure
EPA Electrical Protective Assembly
EPU Extended Power Uprate
ERO Emergency Response Organization
ESS Engineering Safeguard System
ESW Emergency Service Water
ESSW Engineering Safeguards Service Water
EWR Engineering Work Request
FIN Finding
FPC Fuel Pool Cooling
HP Health Physics
HPCI High Pressure Coolant Injection
HVAC Heating, Ventilation and Air-Conditioning
HX Heat Exchanger
ICS Integrated Control System
I&C Instrumentation and Controls
Attachment
A-14
IN Information Notice
IMC Inspection Manual Chapter
IP Inspection Procedure
IR NRC Inspection Report
ISI Inservice Inspection
JP Jet Pump
kV Kilovolts
LCEMA Luzerne County Emergency Management Agency
LCO Limiting Condition for Operation
LER Licensee Event Report
LOCA Loss of Coolant Accident
LOOP Loss of Offsite Power
LP Low Pressure
LSFT Logic System Functional Test
MPFF Maintenance Preventable Functional Failure
MPG Maintenance Procedure Group
MRC Management Review Committee
MREP Maintenance Rule Expert Panel
MRFF Maintenance Rule Functional Failures
MRO Medical Review Officer
MSPI Mitigating Systems Performance Index
M&TE Measuring and Test Equipment
NCV Non-Cited Violation
NDAP Nuclear Department Administrative Procedure
NDE Non-Destructive Examination
NEI Nuclear Energy Institute
NI Nuclear Instrumentation
NRC Nuclear Regulatory Commission
OA Other Activities
ODCM Offsite Dose Calculation Manual
ODM Operational Decision Making
OE Operating Experience
ORO Off-site Response Organization
PARS Publicly Available Records
PEMA Pennsylvania Emergency Management Agency
PI [NRC] Performance Indicator
PI&R Problem Identification and Resolution
PIIM Performance Improvement Integrated Matrix
PIM Plant Issues Matrix
PIRB Performance Improvement Review Board
PMT Post-Maintenance Test
PS Planning Standard
QA Quality Assurance
RB Reactor Building
RCA Radiologically Controlled Area
RCA Root Cause Analysis
RCIC Reactor Core Isolation Cooling
RG [NRC] Regulatory Guide
Attachment
A-15
RHRSW Residual Heat Removal Service Water
RMA Risk Management Actions
ROP Reactor Oversight Process
RP Radiation Protection
RPIS Rod Position Information System
RSPS Risk Significant Planning Standard
SBO Station Blackout
SCBA Self-Contained Breathing Apparatus
SCCI Substantive Cross-Cutting Issue
SDP Significance Determination Process
SFP Spent Fuel Pool
SRM Source Range Neutron Monitoring
SRO Senior Reactor Operator
SSC Structures, Systems and Components
SSES Susquehanna Steam Electric Station
TI Temporary Instruction
TS Technical Specifications
T20 T20 Startup Transformer
UFSAR Updated Final Safety Analysis Report
UVR Under-Voltage Relay
VDC Volt Direct-Current
VT Visual Examination
WO Work Order
Attachment