ML17312B320: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 1: | Line 1: | ||
{{Adams | |||
| number = ML17312B320 | |||
| issue date = 11/08/2017 | |||
| title = NRC Integrated Inspection Report 05000338/2017003 and 05000339/2017003 | |||
| author name = Masters A | |||
| author affiliation = NRC/RGN-II/DRP/RPB5 | |||
| addressee name = Stoddard D | |||
| addressee affiliation = Virginia Electric & Power Co (VEPCO) | |||
| docket = 05000338, 05000339 | |||
| license number = NPF-004, NPF-007 | |||
| contact person = | |||
| document report number = IR 2017003 | |||
| document type = Inspection Report, Letter | |||
| page count = 39 | |||
}} | |||
See also: [[see also::IR 05000338/2017003]] | |||
=Text= | |||
{{#Wiki_filter:UNITED STATES | |||
NUCLEAR REGULATORY COMMISSION | |||
REGION II | |||
245 PEACHTREE CENTER AVENUE NE, SUITE 1200 | |||
ATLANTA, GEORGIA 30303-1257 | |||
November 8, 2017 | |||
Mr. Daniel G. Stoddard | |||
President and Chief Nuclear Officer | |||
Innsbrook Technical Center | |||
5000 Dominion Boulevard | |||
Glen Allen, VA 23060 | |||
SUBJECT: NORTH ANNA POWER STATION - NRC INTEGRATED INSPECTION | |||
REPORT 05000338/2017003 AND 05000339/2017003 | |||
Dear Mr. Stoddard: | |||
On September 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an | |||
inspection at your North Anna Power Station, Units 1 and 2. On October 18, 2017, the NRC | |||
inspectors discussed the results of this inspection with Mr. L. Lane and other members of your | |||
staff. Inspectors documented the results of this inspection in the enclosed inspection report. | |||
No NRC-identified or self-revealing findings were identified during this inspection. | |||
However, NRC inspectors documented one licensee-identified violation, which was determined | |||
to be of very low safety significance, in this report. The NRC is treating this violation as a | |||
non-cited violation (NCV) consistent with Section 2.3.2.a of the NRC Enforcement Policy. | |||
If you contest the violation or significance of the NCV, you should provide a response within 30 | |||
days of the date of this inspection report, with the basis for your denial, to the Nuclear | |||
Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-001; with | |||
copies to the Regional Administrator Region II; the Director, Office of Enforcement, United | |||
States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident | |||
Inspector at the North Anna Power Station. | |||
D. Stoddard 2 | |||
This letter, its enclosure, and your response (if any) will be made available for public inspection | |||
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document | |||
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for | |||
Withholding. | |||
Sincerely, | |||
/RA/ | |||
Anthony D. Masters, Chief | |||
Reactor Projects Branch 5 | |||
Division of Reactor Projects | |||
Docket Nos.: 05000338, 05000339 | |||
License Nos.: NPF-4, NPF-7 | |||
Enclosure: | |||
IR05000338/2017003 and 05000339/2017003 | |||
w/Attachment: Supplemental Information | |||
cc Distribution via ListServ | |||
ML17312B320 | |||
OFFICE RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP RII:DRS | |||
NAME S. Ninh BBishop GCroon GEatmon RCarrion RKellner | |||
DATE 11/1/2017 10/30/2027 10/31/2017 10/30/2017 10/31/2017 10/30/2017 | |||
OFFICE RII:DRS RII:DRP RIIDRP | |||
NAME JRivera WPursley AMasters | |||
DATE 10/30/17 11/1/2017 11/8/2017 | |||
U.S. NUCLEAR REGULATORY COMMISSION | |||
REGION II | |||
Docket Nos: 50-338, 50-339 | |||
License Nos: NPF-4, NPF-7 | |||
Report No: 05000338/2017003 and 05000339/2017003 | |||
Licensee: Virginia Electric and Power Company (VEPCO) | |||
Facility: North Anna Power Station, Units 1 & 2 | |||
Location: Mineral, Virginia 23117 | |||
Dates: July 1, 2017 through September 30, 2017 | |||
Inspectors: G. Croon, Senior Resident Inspector | |||
G. Eatmon, Resident Inspector | |||
R. Carrion, Senior Inspector (Sections 1R07 and 1R08) | |||
R. Kellner, Senior Health Physicist (Sections 2RS1, 2RS7, 4OA1 | |||
and 4OA7) | |||
J. Rivera, Health Physicist (Section 2RS8) | |||
W. Pursley, Health Physicist (Section 2RS6) | |||
Approved by: Anthony D. Masters, Chief | |||
Reactor Projects Branch 5 | |||
Division of Reactor Projects | |||
Enclosure | |||
SUMMARY | |||
IR 05000338/2017003, 05000339/2017003; July 1, 2017 - September 30, 2017; North Anna | |||
Power Station, Units 1 and 2. Routine Integrated Inspection Report. | |||
The report covered a three-month period of inspection by resident inspectors, one regional | |||
based inspector, and three health physicists. The significance of inspection findings are | |||
indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) | |||
0609, Significance Determination Process (SDP), dated April 29, 2015. All violations of NRC | |||
requirements are dispositioned in accordance with the NRCs Enforcement Policy dated | |||
February 4, 2015. The NRCs program for overseeing the safe operation of commercial nuclear | |||
power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6. | |||
No NRC-identified or self-revealing findings were identified. | |||
A licensee-identified violation of very low safety significance has been reviewed by the | |||
inspectors. Corrective actions taken or planned by the licensee have been entered into the | |||
licensees corrective action program. This violation and its associated corrective action tracking | |||
number are listed in Section 4OA7 of this report. | |||
REPORT DETAILS | |||
Summary of Plant Status | |||
Unit 1 began the inspection period at approximately 100 percent rated thermal power (RTP), | |||
and operated at RTP for the remainder of the inspection period. | |||
Unit 2 began the inspection period at approximately 100 percent RTP. On September 9, 2017, | |||
the unit was taken offline for a planned refueling outage. The unit remained offline for the | |||
remainder of the inspection period. | |||
REACTOR SAFETY | |||
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity | |||
1R01 Adverse Weather Protection | |||
.1 Seasonal Extreme Weather Conditions | |||
a. Inspection Scope | |||
The inspectors reviewed the licensees adverse weather preparations for hot weather | |||
operations, specified in 0-GOP-4.1, Hot Weather Operations, Rev. 36, 0-GOP-5.5, | |||
EDG Hot Weather Operation, Rev.14, and the licensees corrective action program | |||
(CAP) database for hot weather related issues. The inspectors walked down two risk- | |||
significant systems/areas listed below to verify compliance with the procedural | |||
requirements and to verify that the specified actions provided the necessary protection | |||
for the structures, systems, or components. | |||
b. Findings | |||
No findings were identified. | |||
.2 Impending Adverse Weather Conditions | |||
a. Inspection Scope | |||
The inspectors performed a site-specific weather-related inspection due to anticipated | |||
adverse weather conditions. On April 17, 2017, the inspectors reviewed the licensee | |||
response to severe storm warnings, with tornado watch, and high wind warnings of 40 | |||
miles an hour for the area. Specifically, the inspectors reviewed licensee adverse | |||
weather response procedures, including 0-AP-41, Severe Weather Conditions, | |||
Rev. 61, and site preparations including work activities that could impact the overall | |||
maintenance risk assessments. | |||
4 | |||
b. Findings | |||
No findings were identified. | |||
.3 Offsite Power and Alternate AC Power | |||
a. Inspection Scope | |||
The inspectors verified that plant features and procedures for operation and continued | |||
availability of offsite and alternative alternating current (AC) power systems were | |||
appropriate. The inspectors reviewed the licensees procedures affecting those areas, | |||
and the communications protocols between the transmission system operator and the | |||
nuclear power plant to verify that the appropriate information was exchanged when | |||
issues arose that could impact the offsite power system. The inspectors evaluated the | |||
readiness of the offsite and alternative AC power systems by reviewing the licensees | |||
procedures that address measures to monitor and maintain the availability and reliability | |||
of the offsite and alternative AC power systems. The inspectors walked down one risk- | |||
significant system/area listed below to verify compliance with the procedural | |||
requirements and to verify that the specified actions provided the necessary protection | |||
for the structures, systems, or components. | |||
b. Findings | |||
No findings were identified. | |||
1R04 Equipment Alignment | |||
Partial Walkdowns | |||
a. Inspection Scope | |||
The inspectors conducted four equipment alignment partial walkdowns, listed below, to | |||
evaluate the operability of selected redundant trains or backup systems with the other | |||
train or system inoperable or out of service. The inspectors reviewed the functional | |||
systems descriptions, UFSAR, system operating procedures, and Technical | |||
Specifications (TS) to determine correct system lineups for the current plant conditions. | |||
The inspectors performed walkdowns of the systems to verify the operability of a | |||
redundant or backup system/train or a remaining operable system/train with a high risk | |||
significance for the current plant configuration (considering out-of-service, inoperable, or | |||
degraded condition); or a risk-significant system/train that was recently realigned | |||
following an extended system outage, maintenance, modification or testing; or a risk- | |||
significant single-train system. The inspector conducted the reviews to ensure that | |||
critical components were properly aligned, and to identify any discrepancies which could | |||
affect operability of the redundant train or backup system. | |||
Documents reviewed are listed in the Attachment. | |||
* Unit 1, Quench spray system, train A | |||
* Unit 2, Quench spray system, train B | |||
* Unit 1, Recirculation spray system, train A | |||
* Unit 2, Control room ventilation system | |||
5 | |||
b. Findings | |||
No findings were identified. | |||
1R05 Fire Protection | |||
Quarterly Fire Protection Walkdowns | |||
a. Inspection Scope | |||
The inspectors conducted focused tours of the four areas listed below that are important | |||
to reactor safety to verify the licensees implementation of fire protection requirements as | |||
described in fleet procedures CM-AA-FPA-100, Fire Protection/Appendix R (Fire Safe | |||
Shutdown) Program, Rev. 10, CM-AA-FPA-101, Control of Combustible and | |||
Flammable Materials, Rev. 8, and CM-AA-FPA-102, Fire Protection and Fire Safe | |||
Shutdown Review and Preparation Process and Design Change Process, Rev. 5. The | |||
inspectors evaluated, as appropriate, conditions related to: (1) licensee control of | |||
transient combustibles and ignition sources; (2) the material condition, operational | |||
status, and operational lineup of fire protection systems, equipment, and features; and, | |||
(3) the fire barriers used to prevent fire damage or fire propagation. Documents | |||
reviewed are listed in the Attachment. | |||
* Units 1 and 2, Service water pumphouse | |||
* Unit 2, Motor generator set house | |||
* Units 1 and 2, Turbine building fire fighting strategy | |||
* Unit 2, Containment | |||
b. Findings | |||
No findings were identified. | |||
1R07 Heat Sink Performance | |||
Triennial Review of Heat Sink Performance | |||
a. Inspection Scope | |||
The inspectors selected the Unit 2 B Component Cooling Heat Exchanger (2-CC-E-1B), | |||
the Unit 2 D Recirculation Spray Heat Exchanger (2-RS-E-1D), and the Unit 1 A Control | |||
Room Chiller (1-HV-E-4A-2) based on their risk-significance in the licensees | |||
probabilistic safety analysis, and their importance to safety-related mitigating system | |||
support functions. | |||
For the two heat exchangers and a control room chiller, the inspectors reviewed the | |||
licensees inspection, maintenance, and monitoring of biotic fouling and macrofouling | |||
programs to ensure that they were adequate. The inspectors also reviewed the | |||
licensees inspection and cleaning activities to determine if they had established | |||
acceptance criteria consistent with industry standards, and the as-found results were | |||
recorded, evaluated, and appropriately dispositioned to maintain structural integrity. | |||
6 | |||
The inspectors reviewed the condition and operation of the Unit 2 B Component Cooling | |||
Heat Exchanger, the Unit 2 D Recirculation Spray Heat Exchanger, and the Unit 1 A | |||
Control Room Chiller to ensure they were consistent with design assumptions in heat | |||
transfer calculations, as described in the final safety analysis report. This included | |||
determining whether the number of plugged tubes was within pre-established limits | |||
based on capacity and heat transfer assumptions for the Unit 2 B Component Cooling | |||
Heat Exchanger, and the Unit 1 A Control Room Chiller. The inspectors also determined | |||
that the licensee had established adequate controls and operational limits to prevent | |||
heat exchanger degradation due to excessive flow-induced vibration during operation. | |||
The inspectors determined whether the performance of ultimate heat sinks (UHS), and | |||
their subcomponents such as piping, intake screens, pumps, valves, etc., was | |||
appropriately evaluated by tests or other equivalent methods, to ensure availability and | |||
accessibility to the in-plant cooling water systems. | |||
The inspectors determined whether the licensees inspection of the UHS was thorough | |||
and of sufficient detail to identify degradation of the impoundment protection, or loss of | |||
structural integrity. This included determination of whether vegetation present along the | |||
slopes was trimmed, maintained, and not adversely impacting the embankment. In | |||
addition, the inspectors determined whether the licensee ensured sufficient reservoir | |||
capacity by trending and removing debris in the UHS. | |||
The inspectors reviewed the licensees inspection of the UHS to determine if it was | |||
comprehensive and of significant depth to ensure sufficient reservoir capacity. This | |||
included the review of licensees periodic monitoring and trending of sediment buildup | |||
and heat transfer capability. In addition, the inspectors reviewed licensees periodic | |||
performance monitoring of the UHS structural integrity, to determine whether adjacent | |||
non-seismic or nonsafety-related structures could degrade, or block safety-related flow | |||
paths, during a severe weather or seismic event. The inspectors also performed | |||
walkdowns of accessible portions of the UHS supply and return piping to look for | |||
possible settlement, or movement and piping conditions that would indicate loss of | |||
structural integrity. | |||
The inspectors performed a system walkdown of the service water intake structure to | |||
determine whether the licensees assessment on structural integrity and component | |||
functionality was adequate. In addition, the inspectors determined whether service | |||
water pump bay silt accumulation was monitored, trended, and maintained at an | |||
acceptable level by the licensee, and that water level instruments were functional and | |||
routinely monitored. The inspectors also determined whether the licensees ability to | |||
ensure functionality during adverse weather conditions was adequate. | |||
The inspectors reviewed condition reports related to the heat exchangers/coolers and | |||
heat sink performance issues to determine whether the licensee had an appropriate | |||
threshold for identifying issues, and to evaluate the effectiveness of the corrective | |||
actions. | |||
These inspection activities constituted four heat sink inspection samples as defined in | |||
IP 71111.07-05. Documents reviewed are listed in the Attachment. | |||
7 | |||
b. Findings | |||
No findings were identified. | |||
1R08 Inservice Inspection Activities Unit 2 - Outage N2R25 | |||
a. Inspection Scope | |||
Non-Destructive Examination Activities and Welding Activities: From September 18, | |||
through September 22, 2017, the inspectors conducted an onsite review of the | |||
implementation of the licensees inservice inspection (ISI) program for monitoring | |||
degradation of the reactor coolant system, emergency feedwater systems, risk- | |||
significant piping and components, and containment systems in Unit 2. The inspectors | |||
activities included a review of non-destructive examinations (NDEs) to evaluate | |||
compliance with the applicable edition of the American Society of Mechanical Engineers | |||
(ASME) Boiler and Pressure Vessel Code (BPVC), Section XI (Code of Record: 2004 | |||
Edition with no Addenda; 4th Interval, 2nd Period, 3rd Outage), and to verify that | |||
indications and defects (if present) were appropriately evaluated and dispositioned in | |||
accordance with the requirements of the ASME Code, Section XI, acceptance | |||
standards. | |||
The inspectors directly observed the following NDEs mandated by the ASME Code to | |||
evaluate compliance with the ASME Code Section XI and Section V requirements, and | |||
if any indications and defects were detected, to evaluate if they were dispositioned in | |||
accordance with the ASME Code, or an NRC-approved alternative requirement. | |||
* UT of Component 12050-WMKS-0102B / 16-WFPD-423 / 40, Elbow to Nozzle | |||
* UT of Component 12050-WMKS-0102A / 16-WFPD-424 / 75, Elbow to Nozzle | |||
* PT of Component 12050-WMKS-0111AP / 6-Sl-441 / 7, Valve to Pipe weld | |||
* PT of Component 12050-WMKS-0111AQ / 6-CH-603 / 8, Valve to Pipe weld | |||
The inspectors observed some welding activities and reviewed the welding documents | |||
for the activities referenced below in order to evaluate compliance with procedures and | |||
the ASME Code. Specifically, the inspectors reviewed the respective work orders, | |||
including the weld data sheets, welding procedures, procedure qualification records, and | |||
welder performance qualification records for the referenced welds. | |||
* 02-RC-154-VALVE, Replace Valve IAW DC NA-17-00008, ASME Class 1, reviewed | |||
Work Order (WO) 59103055303 | |||
* 02-CH-MOV-2267B-VALVE, Replace Valve, ASME Class 2, reviewed | |||
WO 59102981224 | |||
* 02-CC-328-VALVE and Piping, Remove/Reinstall Valve and Piping, ASME Class 3, | |||
reviewed WO 59103105688 and observed some of the welding activities | |||
During non-destructive surface and volumetric examinations performed since the | |||
previous refueling outage, the licensee did not identify any relevant indications that were | |||
analytically evaluated and accepted for continued service. Therefore, no NRC review | |||
was completed for this inspection procedure attribute. | |||
8 | |||
Pressurized Water Reactor Vessel Upper Head Penetration Inspection Activities: For | |||
the Unit 2 vessel head, a bare metal visual examination was not required during this | |||
outage pursuant to 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 as it had | |||
been performed during the previous outage (March 2016 during refueling outage | |||
N2R24). The inspectors also noted that the licensee had requested, and the NRC had | |||
approved, Relief Request N2-I4-NDE-002, which extended the Code Case N-729-1 | |||
Item B4.40 volumetric/surface examination schedule for the reactor vessel closure head | |||
nozzles and partial penetration welds from a ten-year to a fifteen-year period because | |||
the currently installed head is constructed of alloy 690/152/52 material. This material | |||
has exhibited much higher resistance to crack growth rates than the material of the | |||
original reactor vessel upper head, i.e., alloy 600/182/82 material. (The licensee | |||
replaced the original head in January 2003 after identifying extensive cracking in the | |||
attachment welds for reactor vessel head penetrations.) Note that the requirements for | |||
Item B4.40 of Code Case N-729-1 did not change for Item B4.40 of Code Case N-729-4. | |||
The Relief Request allows the licensee to postpone the volumetric and surface | |||
examinations until spring 2022, during scheduled outage N2R28 in the fifth ten-year ISI | |||
inspection interval. These examinations were last conducted in spring 2007 during | |||
N2R18. | |||
Boric Acid Corrosion Control Inspection Activities: The inspectors reviewed the | |||
licensees boric acid corrosion control (BACC) program activities to ensure | |||
implementation with commitments made in response to NRC Generic Letter 88-05, | |||
Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary, and applicable | |||
industry guidance documents. Specifically, the inspectors performed an onsite record | |||
review of procedures and the results of the licensees containment walkdown inspections | |||
performed during the current fall refueling outage (N2R25). The inspectors also | |||
interviewed the BACC program owner, conducted an independent walkdown of | |||
containment to evaluate compliance with licensees BACC program requirements, and | |||
verified that degraded or non-conforming conditions such as boric acid leaks, were | |||
properly identified and corrected, in accordance with the licensees BACC and corrective | |||
action programs. | |||
The inspectors reviewed the condition reports (CRs) and associated corrective actions | |||
(CAs) listed in the Documents Reviewed Attachment related to boric acid leakage to | |||
evaluate if the corrective actions completed were consistent with the requirements of the | |||
ASME Code Section XI and 10 CFR Part 50, Appendix B, Criterion XVI. | |||
Identification and Resolution of Problems: The inspectors performed a review of a | |||
sample of ISI-related problems that were identified by the licensee and entered into the | |||
corrective action program as CRs. The inspectors reviewed the CRs to confirm that the | |||
licensee had appropriately described the scope of the problem, and had initiated | |||
corrective actions. The review also included the licensees consideration and | |||
assessment of operating experience events applicable to the plant. The inspectors | |||
performed this review to ensure compliance with 10CFR Part 50, Appendix B, | |||
Criterion XVI, Corrective Action, requirements. The corrective action documents | |||
reviewed by the inspectors are listed in the report Attachment. Documents reviewed are | |||
listed in the Attachment. | |||
b. Findings | |||
No findings were identified. | |||
9 | |||
1R11 Licensed Operator Requalification Program and Licensed Operator Performance | |||
.1 Resident Inspector Quarterly Review | |||
a. Inspection Scope | |||
The inspectors reviewed a licensed operator performance on August 3, 2017, during a | |||
simulator scenario. The inspectors observed the following elements of crew | |||
performance in terms of communications: (1) ability to take timely and proper actions; | |||
(2) prioritizing, interpreting, and verifying alarms; (3) correct use and implementation of | |||
procedures, including the alarm response procedures; (4) timely control board operation | |||
and manipulation, including high-risk operator actions; and (5) oversight and direction | |||
provided by the shift supervisor, including the ability to identify and implement | |||
appropriate TS actions. Documents reviewed are listed in the Attachment. | |||
b. Findings | |||
No findings were identified. | |||
.2 Quarterly Control Room Operator Performance Observations | |||
a. Inspection Scope | |||
During the inspection period, the inspectors conducted two observations of licensed | |||
reactor operators actions and activities to ensure that the activities were consistent with | |||
the licensee procedures and regulatory requirements. These observations took place | |||
during both normal and off-normal plant working hours. As part of this assessment, the | |||
inspectors observed the following elements of operator performance: (1) operator | |||
compliance and use of plant procedures including technical specifications; (2) control | |||
board/in-plant component manipulations; (3) use and interpretation of plant instruments, | |||
indicators and alarms; (4) documentation of activities; (5) management and supervision | |||
of activities; and (6) communication between crew members. | |||
The inspectors observed and assessed licensed operator performance during the | |||
following events: | |||
* 2-OP-3.7, Unit Shutdown from Mode 1 to Mode 5 for Refueling | |||
* Unit 1 during reset of U1 generator automatic voltage regulator to AUTO after | |||
experiencing oscillations. | |||
b. Findings | |||
No findings were identified. | |||
1R12 Maintenance Effectiveness | |||
a. Inspection Scope | |||
For the four equipment issues listed below, the inspectors evaluated the effectiveness of | |||
the respective licensee's preventive and corrective maintenance. The inspectors | |||
10 | |||
performed walkdowns of the accessible portions of the systems, performed in-office | |||
reviews of procedures and evaluations, and held discussions with licensee staff. The | |||
inspectors compared the licensees actions with the requirements of the Maintenance | |||
Rule (10 CFR 50.65), and licensee procedure ER-AA-MRL-10, Maintenance Rule | |||
Program, Rev. 6. Documents reviewed are listed in the Attachment. | |||
* Fuel cooling pump, 1-FC-P-1B, motor in alert range for vibration | |||
* Charging pump, 1-CH-P-1A, in alert range of vibration | |||
* 1-VG-RM-180, Gaseous Effluent Monitor Out of Service | |||
* 1-SA-P-1A, 1A service air pump trip | |||
b. Findings | |||
No findings were identified. | |||
1R13 Maintenance Risk Assessments and Emergent Work Control | |||
a. Inspection Scope | |||
The inspectors evaluated, as appropriate, the four activities listed below for the following: | |||
(1) effectiveness of the risk assessments performed before maintenance activities were | |||
conducted; (2) management of risk; (3) appropriate and necessary steps taken to plan | |||
and control the resulting emergent work activities upon identification of an unforeseen | |||
situation; and (4) adequate identification and resolution of maintenance risk | |||
assessments and emergent work problems. The inspectors reviewed these | |||
maintenance activities to verify that the licensee was in compliance with the | |||
requirements of 10 CFR 50.65 (a)(4) and the data output from the licensees safety | |||
monitor associated with the risk profile of Units 1 and 2. The inspectors reviewed the | |||
corrective action program to verify that deficiencies in risk assessments were being | |||
identified and properly resolved. Documents reviewed are listed in the Attachment. | |||
* Motor replacement of 1-FC-P-1B due to high vibration | |||
* 2B slave relay PT, 2-PT-213.2A | |||
* Appendix R Alternate Shutdown/Maintenance Rule (a)(4) Fire Risk Equipment | |||
(Technical Response Manual 7.5 for charging crosstie U1/U2) | |||
* U2 overpressure protection, 2-PT-44.4.1 | |||
b. Findings | |||
No findings were identified. | |||
1R15 Operability Determinations and Functionality Assessments | |||
Operability and Functionality Review | |||
a. Inspection Scope | |||
The inspectors reviewed five operability determinations (OD) and functionality | |||
assessments, listed below, affecting risk-significant mitigating systems, to assess, as | |||
appropriate: (1) the technical adequacy of the evaluations; (2) whether continued | |||
11 | |||
system operability was warranted; (3) whether other existing degraded conditions were | |||
considered as compensatory measures; (4) whether the compensatory measures, if | |||
involved, were in place, would work as intended, and were appropriately controlled; and | |||
(5) where continued operability was considered unjustified, the impact on TS Limiting | |||
Conditions for Operation and the risk significance in accordance with the SDP. No | |||
samples of operator work arounds (OWA) were reviewed because there were no OWAs | |||
existing for either unit during the calendar year 2016. The inspectors review included a | |||
verification that ODs were made as specified by procedure OP-AA-102, Operability | |||
Determination, Rev. 13. Documents reviewed are listed in the Attachment. | |||
* Operability Determination, CA3063143, Degraded Non-Conforming Condition of SW | |||
Traveling Screens due to Electrical Design Inadequacy Identified in CR 1074806 | |||
* CA286656, 1-CC-P-1B Oil Sample has Visible Ferrous Particles | |||
* Feedwater ultrasonic flow meter | |||
* 1-CH-P-1A operability in alert vibrations | |||
* Increased reactor coolant system leakage from U1 reactor coolant pump | |||
b. Findings | |||
No findings were identified. | |||
1R19 Post Maintenance Testing | |||
a. Inspection Scope | |||
The inspectors reviewed five post-maintenance test procedures and/or test activities, | |||
listed below, for selected risk-significant mitigating systems to assess whether: (1) the | |||
effect of testing on the plant had been adequately addressed by control room and/or | |||
engineering personnel; (2) testing was adequate for the maintenance performed; (3) | |||
acceptance criteria were clear and adequately demonstrated operational readiness | |||
consistent with design and licensing basis documents; (4) test instrumentation had | |||
current calibrations, range, and accuracy consistent with the application; (5) tests were | |||
performed as written with applicable prerequisites satisfied; (6) jumpers installed or | |||
leads lifted were properly controlled; (7) test equipment was removed following testing; | |||
and (8) equipment was returned to the status required to perform in accordance with | |||
VPAP-2003, Post Maintenance Testing Program, Rev. 14. Documents reviewed are | |||
listed in the Attachment. | |||
* Main Control Room Chiller 4B | |||
* Fire Protection Pumps - Annual Testing for 1-FP-P-2, Diesel-Driven Fire Pump, after | |||
maintenance | |||
* SR102 Shunt Breaker Spare replacement and oil leak repair | |||
* 2-RS-MR02 casing cooler chiller failure and repair | |||
* 1-RM-CNUT-193, N-16 signal converter replacement | |||
b. Findings | |||
No findings were identified. | |||
12 | |||
1R22 Surveillance Testing | |||
a. Inspection Scope | |||
For the six surveillance tests listed below, the inspectors examined the test procedures, | |||
witnessed testing, or reviewed test records and data packages, to determine whether the | |||
scope of testing adequately demonstrated that the affected equipment was functional | |||
and operable, and that the surveillance requirements of TS were met. The inspectors | |||
also determined whether the testing effectively demonstrated that the systems or | |||
components were operationally ready and capable of performing their intended safety | |||
functions. Documents reviewed are listed in the Attachment. | |||
IST Pump or Valve Test: | |||
* 1-PT-71.3Q, 1-FW-P-3B, B Motor-Driven AFW Pump and Valve Test, Revision 53 | |||
RCS Leakage: | |||
* 1-GOP-52.2A, Identifying Increased RCS Leakage, Rev 01 | |||
Containment Isolation Valve: | |||
* 2-PT-57.5A, Leak Rate Test of 2-SI-P-1A and Associated Piping and Inservice | |||
Inspection for 2-SI-6, Rev 21 | |||
* 2-PT-57.5B, Leak Rate Test of 2-SI-P-1B and Associated Piping and Inservice | |||
Inspection for 2-SI-29, Rev 21 | |||
Other Surveillance Tests: | |||
* 2-PT-17.1, Control Rod Operability, Revision 41 | |||
* 2-PT-83.12H, 2H Diesel Generator Test (Start by ESF Actuation) Followed by 24- | |||
hour Run and Hot Restart Test, Revision 29 | |||
b. Findings | |||
No findings were identified. | |||
2. RADIATION SAFETY (RS) | |||
2RS1 Radiological Hazard Assessment and Exposure Controls (Seven Inspection Samples | |||
Completed) | |||
a. Inspection Scope | |||
Hazard Assessment and Instructions to Workers: During facility tours, the inspectors | |||
directly observed radiological postings and container labeling for areas established | |||
within the radiologically controlled area (RCA) of the Unit 2 (U2) Reactor Building, Unit 1 | |||
(U1) and U2 Auxiliary Buildings, and radioactive waste (radwaste) processing and | |||
storage locations. The inspectors independently measured radiation dose rates or | |||
directly observed conduct of licensee radiation surveys for selected RCA areas. The | |||
13 | |||
inspectors reviewed survey records for several plant areas including surveys for airborne | |||
radioactivity, gamma surveys with a range of dose rate gradients, surveys for alpha- | |||
emitters and other hard-to-detect radionuclides, and pre-job surveys for upcoming tasks. | |||
The inspectors also discussed changes to plant operations that could contribute to | |||
changing radiological conditions since the last inspection. The inspectors attended pre- | |||
job briefings and reviewed Radiation Work Permit (RWP) details to assess | |||
communication of radiological control requirements and current radiological conditions to | |||
workers. | |||
Control of Radioactive Material: The inspectors observed surveys of material and | |||
personnel being released from the RCA using small article monitor, personnel | |||
contamination monitor, and portal monitor instruments. The inspectors discussed | |||
equipment sensitivity, alarm setpoints, and release program guidance with licensee staff. | |||
The inspectors also reviewed records of leak tests on selected sealed sources and | |||
discussed nationally tracked source transactions with licensee staff. | |||
Hazard Control: The inspectors evaluated access controls and barrier effectiveness for | |||
selected High Radiation Area (HRA), Locked High Radiation Area (LHRA), and Very | |||
High Radiation Area (VHRA) locations and discussed changes to procedural guidance | |||
for LHRA and VHRA controls with Radiation Protection (RP) supervisors. The | |||
inspectors reviewed implementation of controls for the storage of irradiated material | |||
within the spent fuel pool. Established radiological controls, including airborne controls | |||
and electronic dosimeter (ED) alarm setpoints, were evaluated for selected U2 Refueling | |||
Outage 25 (2R25) tasks including lncore Flux Thimble modifications, Reactor Vessel | |||
Head disassembly/assembly, and Valve Maintenance. In addition, the inspectors | |||
reviewed licensee controls for areas where dose rates could change significantly as a | |||
result of plant shutdown and refueling operations. The inspectors also reviewed the use | |||
of personnel dosimetry including extremity dosimetry and multi-badging in high dose rate | |||
gradients. | |||
Radiation Worker Performance and RP Technician Proficiency: Occupational workers | |||
adherence to selected RWPs and RP technician proficiency in providing job coverage | |||
were evaluated through direct observations and interviews with licensee staff. Jobs | |||
observed included incore flux thimble cutting, refueling, and various outage maintenance | |||
tasks in high radiation and contaminated areas. The inspectors also evaluated worker | |||
responses to dose and dose rate alarms during selected work activities. | |||
Problem Identification and Resolution: The inspectors reviewed and assessed | |||
Corrective Action Program (CAP) documents associated with radiological hazard | |||
assessment and control. The inspectors evaluated the licensees ability to identify and | |||
resolve the issues in accordance with licensee procedures. The inspectors also | |||
reviewed recent self-assessment results. | |||
Inspection Criteria: Radiation protection activities were evaluated against the | |||
requirements of Updated Final Safety Analysis Report (UFSAR) U2 Chapters 11 and 12, | |||
TS Section 5.7, 10 CFR Parts 19 and 20, and approved licensee procedures. Licensee | |||
programs for monitoring materials and personnel released from the RCA were evaluated | |||
against 10 CFR Part 20 and IE Circular 81-07, Control of Radioactively Contaminated | |||
Material. Documents reviewed are listed in the Attachment.. | |||
14 | |||
b. Findings | |||
No findings were identified. | |||
2RS6 Radioactive Gaseous and Liquid Effluent Treatment (Six Inspection Samples | |||
Completed) | |||
a. Inspection Scope: | |||
Radioactive Effluent Treatment Systems: The inspectors walked-down selected | |||
components of the gaseous and liquid radioactive waste (radwaste) processing and | |||
effluent discharge systems. To the extent practical, the inspectors observed and | |||
evaluated the material condition of in-place waste processing equipment for indications | |||
of degradation or leakage that could constitute a possible release pathway to the | |||
environment. Inspected components included radwaste processing equipment in the | |||
clarifier building, turbine building, auxiliary building and associated piping and valves. | |||
The inspectors interviewed licensee staff regarding equipment configuration and effluent | |||
monitor operation. The inspectors also walked down and reviewed surveillance test | |||
records for the A and B trains of the Emergency Core Cooling System Pump Room | |||
Exhaust Air Cleanup System (ECCS PREACS) ventilation system filters. | |||
Effluent Sampling and Discharge: The inspectors observed the collection and | |||
processing of liquid effluent samples from high capacity steam generator blowdown | |||
proportional tanks in the turbine building and from the clarifier proportional tanks in the | |||
waste disposal building and observed gaseous effluent sampling on the 291 elevation of | |||
the auxiliary building. Technician proficiency in collecting, processing, and preparing the | |||
applicable release permits was evaluated. The inspectors reviewed recent liquid and | |||
gaseous release permits including pre-release sampling results, effluent monitor alarm | |||
setpoints, and public dose calculations. For RM-111 (Clarifier Hold-Up Tank Outlet | |||
Liquid Effluent Monitor), RM-187 (Process Vent Gaseous Effluent Monitor), RM-188 | |||
(Plant Vent A Gaseous Effluent Monitor) and RM-121 (U1 Condensate Air Ejector | |||
Gaseous Effluent Monitor), the inspectors reviewed calibration and functional test | |||
records and evaluated traceability of radioactive calibration sources to National Institute | |||
of Standards and Technology (NIST) standards. The inspectors also evaluated the | |||
licensees capability to collect high-range post-accident effluent samples from these | |||
monitoring systems if applicable. The inspectors reviewed and discussed with licensee | |||
staff methodology for determining vent and stack flow rates and compared current vent | |||
flows to design values in the Offsite Dose Calculation Manual (ODCM). | |||
The inspectors reviewed the 2015 and 2016 Annual Radioactive Effluent Release | |||
Reports to evaluate reported doses to the public, review any anomalous events, and to | |||
review ODCM changes. The inspectors reviewed compensatory sampling data for time | |||
periods when selected radiation monitors were out of service. The inspectors reviewed | |||
the results of interlaboratory cross-checks for laboratory instruments used to analyze | |||
effluent samples. The inspectors also reviewed licensee effluent source term | |||
characterizations and changes to effluent release points. In addition, the inspectors | |||
evaluated recent land use census results. | |||
15 | |||
Problem Identification and Resolution: The inspectors reviewed and discussed selected | |||
CAP documents associated with gaseous and liquid effluent processing and release | |||
activities including licensee sponsored assessments. The inspectors evaluated the | |||
licensees ability to identify and resolve issues. | |||
Inspection Criteria: Radwaste system operation and effluent processing activities were | |||
evaluated against requirements and guidance documented in the following: 10 CFR Part | |||
20; 10 CFR Part 50 Appendix I; ODCM; UFSAR Chapters 9 and 11; Regulatory Guide | |||
(RG) 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and | |||
Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water- | |||
Cooled Nuclear Power Plants; RG 1.109, Calculation of Annual Doses to Man from | |||
Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 | |||
CFR Part 50 Appendix I; and TS Section 5, Administrative Requirements Documents | |||
reviewed are listed in the Attachment. | |||
b. Findings | |||
No findings were identified. | |||
2RS7 Radiological Environmental Monitoring Program (REMP) (Three Inspection Samples | |||
Completed) | |||
a. Inspection Scope | |||
REMP Implementation: The inspectors reviewed the (2015 and 2016) Annual | |||
Radiological Environmental Operating Reports and the (2015 and 2016) Annual | |||
Radioactive Effluent Release Reports. Selected environmental measurements were | |||
reviewed for consistency with licensee effluent data, evaluated for radionuclide | |||
concentration trends, and compared with detection level sensitivity requirements as | |||
described in the ODCM. The inspectors assessed the licensees response to any | |||
missed or anomalous environmental samples. The inspectors also reviewed the results | |||
of interlaboratory cross-checks for laboratory instruments used to analyze environmental | |||
samples. Any changes to the ODCM, Land Use Census, or environmental program | |||
processes were discussed with licensee staff. | |||
The inspectors observed routine collection of airborne particulate and iodine air samples | |||
and verified placement of environmental dosimeters and surface water sampling | |||
equipment at selected locations as required by the licensees ODCM. The inspectors | |||
noted the material condition of the continuous air samplers, water samplers, and | |||
environmental dosimeters. The inspectors also reviewed calibration and maintenance | |||
records for the selected the environmental sampling equipment. | |||
Meteorological Monitoring Program: The inspectors observed the physical condition of | |||
the meteorological tower and its instrumentation and discussed equipment operability | |||
and maintenance history with licensee staff. The inspectors evaluated transmission of | |||
locally generated meteorological data to other licensee groups such as emergency | |||
operations personnel and main control room operators. Calibration records for the | |||
meteorological measurements of wind speed, wind direction, and temperature were | |||
reviewed. The inspectors also reviewed meteorological measurement data recovery for | |||
2015 and 2016. | |||
16 | |||
Ground Water Protection: The inspectors reviewed the licensees continued | |||
implementation of the industrys Ground Water Protection Initiative (Nuclear Energy | |||
Institute (NEI) 07-07) and discussed any changes to the program. The inspectors | |||
discussed program guidance for dealing with spills, leaks, and unexpected discharges | |||
with licensee staff and reviewed recent monitoring well results and any voluntary | |||
communications. The inspectors also reviewed recent entries into the 10 CFR 50.75(g) | |||
decommissioning file. The inspectors reviewed and discussed the licensees program | |||
for monitoring of structures, systems, and components with the potential to release | |||
radioactive material to the environment. Potential effluent release points due to onsite | |||
surface water bodies were also evaluated. | |||
Problem Identification and Resolution: The inspectors reviewed CAP documents in the | |||
areas of radiological environmental monitoring and meteorological tower maintenance. | |||
The inspectors evaluated the licensees ability to identify and resolve the issues. The | |||
inspectors also reviewed recent self-assessment results. | |||
Inspection Criteria: The inspectors evaluated REMP implementation and meteorological | |||
monitoring against the requirements and guidance contained in: 10 CFR Part 20; | |||
Appendices E and I to 10 CFR Part 50; TS Section 5.0; Offsite Dose Calculation Manual | |||
(North Anna); UFSAR Chapter 11; RG 4.15, Quality Assurance for Radiological | |||
Monitoring Programs (Normal Operation) - Effluent Streams and the Environment; | |||
Branch Technical Position, An Acceptable Radiological Environmental Monitoring | |||
Program - 1979; Safety Guide 23 Onsite Meteorological Programs; NEI 07-07, | |||
Industry Groundwater Protection Initiative - Final Guidance Document; and approved | |||
licensee procedures Documents reviewed are listed in the Attachment. | |||
b. Findings | |||
No findings were identified. | |||
2RS8 Radiological Radioactive Solid Waste Processing and Radioactive Material Handling, | |||
Storage, and Transportation (Six Inspection Samples Completed) | |||
a. Inspection Scope | |||
Radioactive Material: The inspectors walked down indoor and outdoor areas inside the | |||
protected area as well as radioactive material storage warehouses and the steam | |||
generator storage facility outside of the protected area (PA). During the walk-downs, the | |||
inspectors observed the physical condition and labeling of storage containers and the | |||
radiological postings for satellite radioactive material storage areas. The inspectors also | |||
reviewed the licensees radwaste procedures for routine surveys and waste storage. | |||
Radioactive Waste System Walkdown, Characterization and Classification: The | |||
inspectors walked down accessible sections of the liquid and solid radwaste systems to | |||
assess material condition and conformance of equipment with system design diagrams. | |||
This included portions of the radwaste processing building. The inspectors discussed | |||
the function of radwaste components with the radwaste operator. The inspectors | |||
discussed possible changes to the radwaste processing systems with radwaste staff. | |||
The processes for the dewatering of resins, spent resin tank recirculation, resin | |||
sampling, and transfer of resins from the processing pads to the shipping casks and | |||
temporary storage casks were reviewed and discussed with resin processing contractor. | |||
17 | |||
The inspectors reviewed the 2016 Radioactive Effluent Release Report and the most | |||
recent radionuclide characterization and classification for the dry active waste and | |||
primary resin waste streams. The inspectors evaluated analyses for hard-to-detect | |||
nuclides, reviewed the use of scaling factors, and examined quality assurance | |||
comparison results between licensee waste stream characterizations and outside | |||
laboratory data. The inspectors also evaluated how changes to plant operational | |||
parameters were taken into account in waste characterization. | |||
Shipment Preparation and Records: There were no outgoing radioactive material | |||
shipments available for observation during the week of the inspection. The inspectors | |||
observed the radiological survey of an incoming limited quantity shipment. The | |||
inspectors reviewed four shipping records for consistency with licensee procedures and | |||
compliance with NRC and Department of Transportation regulations. This included | |||
review of emergency response information, waste classification, radiation survey results, | |||
information on the waste manifest, and the authorization of the receiving licensee to | |||
receive shipments. Training records for selected individuals currently qualified to ship | |||
radioactive material were reviewed for compliance with 49 CFR Part 172 Subpart H. | |||
Problem Identification and Resolution: The inspectors reviewed CAP documents in the | |||
areas of radwaste/shipping. The inspectors evaluated the licensees ability to identify | |||
and resolve the issues. The inspectors also reviewed recent self-assessment results. | |||
Inspection Criteria: Radioactive material and waste storage activities were reviewed | |||
against the requirements of 10 CFR Part 20. Radwaste processing activities and | |||
equipment configuration were reviewed for compliance with the licensees Process | |||
Control Program. Waste stream characterization analyses were reviewed against | |||
regulations detailed in 10 CFR Part 20, 10 CFR Part 61, and guidance provided in the | |||
Branch Technical Position on Waste Classification (1983). Transportation program | |||
implementation was reviewed against regulations detailed in 10 CFR Part 20, 10 CFR | |||
Part 71 (which requires licensees to comply with Department of Transportation | |||
regulations in 49 CFR Parts 107, 171-180, and 390-397), as well as the guidance | |||
provided in NUREG-1608. Training activities were assessed against 49 CFR Part 172 | |||
Subpart H. Documents reviewed are listed in the Attachment. | |||
b. Findings | |||
No findings were identified. | |||
4. OTHER ACTIVITIES | |||
4OA1 Performance Indicator (PI) Verification (Four Inspection Samples Completed) | |||
.1 Reactor Safety | |||
a. Inspection Scope | |||
The inspectors reviewed a sample of the performance indicator (PI) data, submitted by | |||
the licensee, for the Unit 1 and Unit 2 PIs listed below. The inspectors reviewed plant | |||
records compiled between June 2016 to June 2017 to verify the accuracy and | |||
completeness of the data reported for the station. The inspectors verified that the PI | |||
data complied with guidance contained in Nuclear Energy Institute 99-02, Regulatory | |||
18 | |||
Assessment Performance Indicator Guideline, and licensee procedures. The inspectors | |||
verified the accuracy of reported data that were used to calculate the value of each PI. | |||
In addition, the inspectors reviewed a sample of related corrective action documents to | |||
verify the licensee was identifying and correcting any deficiencies associated with PI | |||
data. Documents reviewed are listed in the attachment. | |||
Cornerstone: Mitigating Systems | |||
* safety system functional failure (MS05) | |||
Cornerstone: Barrier Integrity | |||
* reactor coolant system specific activity (BI01) | |||
b. Findings | |||
No findings were identified. | |||
.2 Radiation Safety | |||
a. Inspection Scope | |||
Occupational Radiation Safety Cornerstone: (OR01) The inspectors reviewed the | |||
Occupational Exposure Control Effectiveness PI results for the Occupational Radiation | |||
Safety Cornerstone from April 2016 through July 2017. For the assessment period, the | |||
inspectors reviewed ED alarm logs and CAP documents related to controls for exposure | |||
significant areas. Documents reviewed are listed in the Attachment. | |||
Public Radiation Safety Cornerstone: (PR01) The inspectors reviewed the Radiological | |||
Control Effluent Release Occurrences PI results for the Public Radiation Safety | |||
Cornerstone from April 2016 through July 2017. For the assessment period, the | |||
inspectors reviewed cumulative and projected doses to the public contained in liquid and | |||
gaseous release permits and CAP documents related to Radiological Effluent Technical | |||
Specifications/ODCM issues. The inspectors also reviewed licensee procedural | |||
guidance for collecting and documenting PI data. Documents reviewed are listed in the | |||
Attachment. | |||
b. Findings | |||
No findings were identified. | |||
4OA2 Problem Identification and Resolution | |||
.1 Review of Items Entered into the Corrective Action Program | |||
a. Inspection Scope | |||
As required by NRC Inspection Procedure 71152, Identification and Resolution of | |||
Problems, and in order to help identify repetitive equipment failures or specific human | |||
performance issues for follow-up, the inspectors performed a daily screening of items | |||
19 | |||
entered into the licensees CAP. This review was accomplished by reviewing daily CR | |||
report summaries and periodically attending daily CR Review Team meetings. | |||
b. Findings and Observations | |||
No findings were identified. | |||
.2 Semiannual Trend Review: Procedural Adherence | |||
a. Inspection Scope | |||
The inspectors performed a review regarding the licensees procedural adequacy. The | |||
inspectors, through document review and interviews with licensee, reviewed the | |||
establishment and effectiveness of a licensee program in addressing procedural | |||
adequacy in operations and maintenance activities. | |||
b. Findings and Observations | |||
No findings were identified. | |||
4OA6 Meetings, Including Exit | |||
On October 18, 2017, the resident inspectors presented the quarterly inspection results | |||
to Mr. L. Lane and other members of the staff. The licensee acknowledged the results of | |||
these inspections. The inspectors verified no proprietary information was retained by the | |||
inspectors or documented in this report. | |||
4OA7 Licensee-Identified Violations | |||
The following violation of very low safety significance (Green) was identified by the | |||
licensee and is a violation of NRC requirements which meet the criteria of the NRC | |||
Enforcement Policy, for being dispositioned as a Non-Cited Violation. | |||
TS 5.4.1 requires, that Written procedures shall be established, implemented, and | |||
maintained covering the following activities: a. The applicable procedures | |||
recommended in Regulatory Guide 1.33, Revision 2, Appendix A, | |||
February 1978. Regulatory Guide (RG) 1.33, Appendix A, identifies Access control to | |||
radiation areas, including a Radiation Work Permit (RWP) system as one of the areas | |||
requiring procedural controls. Additionally, procedure VPAP-2101, Radiation Protection | |||
Program, Revision 35, Attachment 1, RCA Work Practices, identifies what workers | |||
should know prior to entering the RCA (minimum requirements). Attachment 1 states, in | |||
part, All workers entering the RCA are required to: 1) Notify RP prior to entering the | |||
RCA. Contrary to the above requirements, on September 15, 2017, two maintenance | |||
workers entered U2 Containment, a posted High Radiation Area (HRA), while signed in | |||
on an incorrect RWP, and without checking in at the Health Physics Shift Supervisor | |||
window prior to entering containment. The workers signed in on the RWP they had used | |||
earlier in the day which did not allow entry into a HRA. The containment building had | |||
been posted as a HRA in preparation for lifting the reactor head while the workers were | |||
out of containment. HP personnel in the remote monitoring facility identified that the | |||
individuals were on an incorrect RWP, informed HP personnel in containment, and the | |||
workers exited containment prior to the head lift. This finding was of very low safety | |||
20 | |||
significance (Green) because there was no substantial potential for overexposure and | |||
the licensees ability to assess dose was not compromised. The immediate corrective | |||
actions were documented in CR 1078223. Corrective actions included a human | |||
performance review, coaching of the individuals by RP Management, and distribution of | |||
a site-wide message discussing the incident and reminding site personnel to remain | |||
aware of radiological safety. | |||
ATTACHMENT: SUPPLEMENTAL INFORMATION | |||
SUPPLEMENTAL INFORMATION | |||
KEY POINTS OF CONTACT | |||
Licensee personnel: | |||
M. Becker, Manager, Nuclear Outage and Planning | |||
R. Galbraith, ISI/NDE Supervisor | |||
A. Garcia-Santiago, Auxiliary System Programs Engineer II | |||
J. Jenkins, Manager, Nuclear Site Services | |||
R. Hanson, Manager, Nuclear Protection Services | |||
E. Hendrixson, Director, Nuclear Site Engineering | |||
L. Hilbert, Plant Manager | |||
J. Jenkins, Manager, Nuclear Maintenance | |||
L. Lane, Site Vice President | |||
K. LeBarron, Nuclear Technical Specialist III | |||
J. Leberstien, Technical Advisor, Licensing | |||
D. McGinnis, Technical Specialist II | |||
R. Page, Licensing Engineer | |||
J. Plossl, Supervisor, Nuclear Station Procedures | |||
J. Schleser, Manager, Nuclear Organizational Effectiveness | |||
R. Simmons, Manager, Radiation Protection and Chemistry | |||
J. Slattery, Manager, Nuclear Operations | |||
W. Standley, Director, Nuclear Station Safety & Licensing | |||
D. Taylor, Manager, Station Licensing | |||
B. Thompson, Manager, Nuclear Training | |||
B.J Thompson, Superintendent, Radiation Protection Technical Services | |||
M. Whalen, Technical Advisor, Licensing | |||
J. Collins - Corporate Director, Emergency Preparedness (EP) | |||
B. Miller - EP Specialist | |||
D. Plogger - EP Specialist | |||
T. Shalaski - EP Specialist | |||
N. Turner, EP Manager | |||
LIST OF ITEMS OPENED, CLOSED AND DISCUSSED | |||
Opened and Closed | |||
None | |||
Attachment | |||
LIST OF DOCUMENTS REVIEWED | |||
Section 1R04: Equipment Alignment | |||
Procedures, Guidance Documents, and Manuals | |||
1-OP-7.4A, Valve Checkoff - Quench Spray System, Revision 10. | |||
CR1041263 BACC 1-QS-P-1A at shaft seal | |||
Section 1R05: Fire Protection | |||
Procedures, Guidance Documents, and Manuals | |||
2-FS-C-1, Loss Prevention Fire Strategy, Containment - Unit 2, Revision 4 | |||
2-PT-105.4.1, Loss Prevention Periodic Test, Fire Protection - Hose Station Flow Test, | |||
Revision 3 | |||
1-FS-SW-1, Loss Prevention Fire Strategy, Service Water Pump House Units 1 and 2, | |||
Revision 2 | |||
0-PT-105.3, Loss Prevention Periodic Test, Hose House Inspection, Revision 5 | |||
CM-AA-FPA-100, Fire Protection/Appendix R (Fire Safe Shutdown) Program, Revision 13 | |||
0-PT-105.1.1, Loss Prevention Period Test, Fire Door Inspection - Turbine Building, Control | |||
Room, and Office Area, Revision 10 | |||
0-FS-TB-1, Loss Prevention Fire Strategy, Turbine Building Fire Fighting Strategy, Revision 2 | |||
2-FS-MG-1, Firefighting Strategy, Motor Generator Set House Unit 2, Dated May 28, 1992 | |||
Section 1R07: Heat Sink Performance | |||
Procedures | |||
0-AP-12, Abnormal Procedure, Loss of Service Water, Revision 40 | |||
0-EPM-2303-01, Inspection of Service Water Cathodic Protection System, Revision 12 | |||
0-EPM-2303-02, Corrosion Survey of Service Water Cathodic Protection System, Revision 0 | |||
0-OP-49.1, Operating Procedure, Service Water System Normal Operation, Revision 20 | |||
0-OP-49.6, Operating Procedure, Service Water System Throttling Alignment, Revision 24 | |||
0-PT-75.7, Engineering Periodic Test, Service Water Reservoir - Ground Water Level, | |||
Revision 7 | |||
0-PT-75.8, Engineering Periodic Test, Service Water Reservoir Loss Monitoring Procedure, | |||
Revision 5 | |||
0-PT-75.24A, Service Water MIC Leakage Inspection - Units 1 and 2, Revision 9 | |||
0-PT-75.12, Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike | |||
and Toe, Revision 7 | |||
0-PT-75.15, Engineering Periodic Test, Generic Letter 89-13 Service Water System Testing | |||
Requirements Coordination, Revision 6 | |||
0-PT-75.22, Engineering Periodic Test, Service Water System Reservoir Sludge Depth | |||
Measurement, Revision 7 | |||
0-PT-115, Engineering Periodic Test, Survey of Settlement Monitoring Points, Revision 13 | |||
1-PT-75.6, Engineering Periodic Test, Service Water System Flow Balance, Revision 24-MR1 | |||
2-PT-75.6, Engineering Periodic Test, Service Water System Flow Balance, Revision 23 | |||
ER-AA-AMP-101, Implementation of Activities Performed by License Renewal Aging | |||
Management Coordinators, Revision 7 | |||
ER-AA-BPM-10, Underground Piping and Tank Integrity Program Description, Revision 7 | |||
ER-AA-BPM-101, Underground Piping and Tank Integrity Program, Revision 10 | |||
ER-AA-HTX-10, Heat Exchanger Program, Revision 6 | |||
3 | |||
ER-NA-INS-101, Main Dam Annual Inspection, Revision 2 | |||
ER-NA-SYS-320, Generic Letter 89-13 Program, Revision 2 | |||
CH-32.939, Service Water Chemical Addition System: Operation, Revision 14 | |||
CH-32.940, Service Water System: Aqua Shade Addition, Revision 2 | |||
CHAP-0105, Auxiliary Cooling Water System Chemistry Control Program (North Anna), | |||
Revision 26 | |||
VPAP-0811, Service Water System Inspection and Maintenance Program, Revision 6 | |||
Corrective Action Documents | |||
CR 0580154, Service Water flow indication on 'B' supply header is indicating high | |||
CR 1010758, Extension shaft material for SW Spray Array MOVs (and Bypass MOVs) do not | |||
support torque requirement | |||
CR 1010761, Unable to confirm material removed from the "B" SW header | |||
CR 1010918, Through-Wall Leak in the 1B2 Spray Array Piping | |||
CR 1010927, Through-Wall Leak identified on the 2A2 Spray Array | |||
CR 1010934, 2A2 SW spray array surging | |||
CR 1010936, 2-SW-MOV-222A Internal Inspection Findings | |||
CR 1011052, Mop head fibers lodged in 2" continuous drains | |||
CR 1050193, 2-SW-354 has a MIC leak at the pipe weld | |||
CR 1071375, Weld Repairs identified on 10 Tee off of 24-WS-102-151-Q3 | |||
Work Orders (WOs) | |||
WO 59102243628, Control Room Chiller Equipment Performance Test (1-HV-E-4A) | |||
WO 59102493734, Inspection and Cleaning of 01-HV-E-4A-2-HTEXCH | |||
WO 59102498132, CC Heat Exchanger Tube Cleaning/Plugging 02-CC-E-1B HTEXCH | |||
WO 59102888926, Annual Corrosion Survey of Service Water Cathodic Protection System per | |||
0-EPM-2303-02 | |||
WO 59102999245, Eddy Current Testing of 01-RS-E-1B-HTEXCH | |||
WO 59102999267, Perform Eddy Current Testing I As-Found Tubesheet Inspection of | |||
01-RS-E-1 D-HTEXCH | |||
Other Documents Reviewed | |||
Main Dam Annual Inspection using ER-NA-INS-101, dated 10/16/14 | |||
Main Dam Annual Inspection using ER-NA-INS-101, dated 8/19/15 | |||
Main Dam Annual Inspection using ER-NA-INS-101, dated 11/3/16 | |||
Calculation 07797-US(B)-280, Containment Recirculation Heat Exchanger UAs, dated 5-3-00 | |||
Calculation ME-0530, Component Cooling Heat Exchanger Tube Plugging, dated 2/10/97 | |||
Calculation ME-0932, Evaporator and Condenser Tube Plugging Evaluation for the Main | |||
Control Room Chillers and Front Office Chillers, dated 10/16/12 | |||
Design Change NA-15-00106, Removal of Weko Pipe Seals in the A Service Water Return | |||
Header (36-WS-4-151-Q3) | |||
Design Change NA-16-00058 Removal of Weko Pipe Seals in the B Service Water Supply | |||
Header (36-WS-2-151-Q3) | |||
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7, | |||
dated 11/25/14 | |||
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7, | |||
dated 6/10/15 | |||
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7, | |||
dated 1/6/16 | |||
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7, | |||
dated 6/20/16 | |||
4 | |||
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7, | |||
dated 1/10/17 | |||
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7, | |||
dated 6/15/17 | |||
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated | |||
1/28/15 | |||
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated | |||
7/30/15 | |||
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated | |||
2/4/16 | |||
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated | |||
8/9/16 | |||
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated | |||
1/25/17 | |||
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated | |||
6/19/17 | |||
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe | |||
using 0-PT-75.12, dated 11/26/14 | |||
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe | |||
using 0-PT-75.12, dated 5/6/15 | |||
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe | |||
using 0-PT-75.12, dated 12/7/15 | |||
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe | |||
using 0-PT-75.12, dated 6/16/16 | |||
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe | |||
using 0-PT-75.12, dated 12/5/16 | |||
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe | |||
using 0-PT-75.12, dated 5/31/17 | |||
Engineering Periodic Test of Generic Letter 89-13 Service Water System Testing Requirements | |||
Coordination using 0-PT-75.15, dated 8/31/15 | |||
Engineering Periodic Test of Generic Letter 89-13 Service Water System Testing Requirements | |||
Coordination using 0-PT-75.15, dated 8/12/16 | |||
Engineering Periodic Test, Service Water System Sludge Depth Measurement using | |||
0-PT-75.22, dated 12/6/16 | |||
Engineering Periodic Test of Generic Letter 89-13 Service Water System Components using | |||
0-PT-75.15, dated 8/31/15 | |||
Engineering Periodic Test of Generic Letter 89-13 Service Water System Components using | |||
0-PT-75.15, dated 8/12/16 | |||
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated | |||
10/2/14 | |||
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated | |||
3/27/15 | |||
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated | |||
9/30/15 | |||
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated | |||
3/31/16 | |||
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated | |||
10/2/16 | |||
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated | |||
3/21/17 | |||
Engineering Periodic Test, Service Water System Flow Balance using 1-PT-75.6, dated 3/13/15 | |||
5 | |||
Engineering Periodic Test, Service Water System Flow Balance using 1-PT-75.6, dated | |||
10/11/16 | |||
Engineering Periodic Test, Service Water System Flow Balance using 2-PT-75.6, dated 9/24/14 | |||
Engineering Periodic Test, Service Water System Flow Balance using 2-PT-75.6, dated 4/6/16 | |||
Engineering Technical Evaluation ETE-NA-2012-0064, Life Cycle Management Plan - | |||
Underground Piping and Tank Integrity Program - North Anna Power Station, Revision 4 | |||
EPRI TR-108009, Balance of Plant Heat Exchanger Condition Assessment and Inspection | |||
Guide, December 1999 | |||
EPRI TR-110392, Eddy Current Testing of Service Water Heat Exchangers for Engineers | |||
Guideline, February 1999 | |||
Federal Energy Regulatory Commission (FERC) Dam Safety Inspection Report on the Service | |||
Water Reservoir Dam, submitted on May 24, 2016 | |||
Plant Health Issues List (PHIL) 3171, Obsolescence: SW System Component Obsolete (SW | |||
Travelling Screens) | |||
SDBD-NAPS-SW, System Design Basis Document for Service Water System - North Anna | |||
Power Station, Revision 19 | |||
Service Water System Health Report for 3rd Quarter 2014 | |||
Service Water System Health Report for 4th Quarter 2014 | |||
Service Water System Health Report for 1st Quarter 2015 | |||
Service Water System Health Report for 2nd Quarter 2015 | |||
Service Water System Health Report for 3rd Quarter 2015 | |||
Service Water System Health Report for 4th Quarter 2015 | |||
Service Water System Health Report for 1st Quarter 2016 | |||
Service Water System Health Report for 4th Quarter 2016 | |||
Service Water System Health Report for 1st Half 2017 | |||
Technical Report LR-2754, Service Water System Inspections, North Anna Power Station | |||
Unit 1 PT of isolation capabilities for interface valves between SW and non-safety-related or | |||
non-seismic piping using Operations Periodic Test Procedure 1-PT-57.4, dated 9/30/16 | |||
Unit 2 PT of isolation capabilities for interface valves between SW and non-safety-related or | |||
non-seismic piping using Operations Periodic Test Procedure 2-PT-57.4, dated 3/31/16 | |||
Updated Final Safety Analysis Report (FSAR) Section 9.2.1, Service Water System | |||
Water Hammer Analysis from the Service Water System Operational Performance Assessment, | |||
July 11 - July 29, 1994 (CNS Report No. 94-03- NAPS-A) | |||
Section 1R08: Inservice Inspection Activities | |||
Procedures | |||
ER-AA-NDE-PT-301, ASME Section XI Liquid Penetrant Examination Procedure, Revision 7 | |||
ER-AA-NDE-PT-301, Balance of Plant (BOP) Liquid Penetrant Examination Procedure, | |||
Revision 7 | |||
ER-AA-NDE-UT-801, Ultrasonic Examination of Ferritic Piping Welds in Accordance with ASME | |||
Section XI, Appendix VIII, Revision 7 | |||
ER-AP-BAC-10, Boric Acid Corrosion Control Program, Revision 12 | |||
ER-AP-BAC-101, Boric Acid Corrosion Control Program (BACCP) Inspections, Revision 12 | |||
ER-AP-BAC-102, Boric Acid Corrosion Control Program (BACCP) Evaluations, Revision 13 | |||
Corrective Action Documents | |||
CR 1044128, Manifold at 2-CH-MAN-2147 has moist boric acid leak | |||
CR 1044134, Excessive boric acid leak found on 2-CH-249 | |||
CR 1050623, BACC packing leak on 2-SI-MOV-2867C excessive and discolored | |||
CR 1050625, BACC actively leaking on 2-CH-250 | |||
6 | |||
CR 1054222, Excessive wet boric acid on 2-SI-RV-2857 Leak-Off Line | |||
CR 1055826, Excessive boric acid deposit on 2-CH-240 | |||
CR 1055829, Discolored boric acid deposit on 2-SI-MOV-2867D | |||
CR 1060028, Excessive dry boric acid from packing on 1-CH-316 | |||
CR 1063045, Manifold at 2-CH-MAN-2147 has moist boric acid leak | |||
CR 1064466, Excessive, discolored boric acid on 2-SI-83 | |||
CR 1064483, Moist, discolored boric acid on 2-CH-MOV-2287A | |||
CR 1077711, Excessive boric acid leakage at 2-RC-48 packing | |||
CR 1077834, Excessive boric acid found on various components | |||
CR 1077970, 2-CH-ICV-3154 excessive boric acid leak | |||
CR 1077973, 2-CH-FT-2155A excessive discolored Boric Acid | |||
CR 1078234, Discolored boric acid noted at packing of 2-CH-ICV-3019 | |||
Corrective Actions (CAs) | |||
CA3037522, Perform Boric Acid Review to Restore Full Qualification for Boric Acid Leak Found | |||
on 2-CH 249 (associated with CR1044134 | |||
CA3044983, Perform Boric Acid Review for Excessive Wet Boric Acid on 2-SI-RV-2857 Leak | |||
Off-Line (associated with CR1054222) | |||
CA3053391, Perform Boric Acid Review (02-CH-MAN-2147-VALVE) (associated with | |||
CR1063045) | |||
CA3054717, Perform Boric Acid Review for Excessive, Discolored Boric Acid on 2-SI-83 | |||
(associated with CR1064466) | |||
CA3054879, Perform Boric Acid Review: Moist, Discolored Boric Acid on 2-CH-MOV-2287A | |||
(associated with CR1064483 | |||
Welding Documentation | |||
Work Order (WO) 59103055303, Replace Valve IAW DC NA-17-00008 (02-RC-154-VALVE), | |||
ASME Class 1 | |||
Repair/Replacement Plan 2017-102 | |||
Weld Map for location 02-RC-154 | |||
Weld Material Field Control Sheet for Welds # 50, 51, and 52A | |||
Weld Data Record for Welds # 50, 51, and 52A | |||
Procedure Qualification Record 801, Revision 2 | |||
Procedure Qualification Record 830 | |||
Procedure Qualification Record 831 | |||
Liquid Penetrant Examination Report BOP-PT-17-790 of Weld 50 | |||
Liquid Penetrant Examination Report BOP-PT-17-730 of Welds 51 & 52A | |||
Welder Performance Qualification (WPQ) of J. Hamilton, J. Olson, and A. Pennington | |||
Welding Technique Sheet for Welding Technique Number 801, Revision 8 | |||
WO 59102981224, Valve (02-CH-MOV-2267B-VALVE) Replacement Due to History of Leakby, | |||
ASME Class 2 | |||
Repair/Replacement Plan 2017-019 | |||
Weld Map for location 2-CH-MOV-2267B | |||
Weld Material Field Control Sheet for Welds # 7, 8, and SW32 | |||
Welder Performance Qualification (WPQ) of J. Coleman, T. McGlothlin, and N. Sadler | |||
Welding Technique Sheet for Welding Technique Number 801, Revision 2 | |||
Welding Technique Sheet for Welding Technique Number 803, Revision 9 | |||
Welding Technique Sheet for Welding Technique Number 805, Revision 3 | |||
Welding Technique Sheet for Welding Technique Number 809, Revision 2 | |||
Welding Technique Sheet for Welding Technique Number 830 | |||
7 | |||
Welding Technique Sheet for Welding Technique Number 831 | |||
Ultrasonic Examination Report BOP-UT-17-013 of Welds 7 and SW32 | |||
Ultrasonic Examination Report BOP-UT-17-025 of Weld 8 | |||
Liquid Penetrant Examination Report BOP-PT-17-733 of Final Welds 7 and SW32 | |||
Liquid Penetrant Examination Report BOP-PT-17-771 of Final Weld 8 | |||
Liquid Penetrant Examination Report PT-17-001 of 12050-WMKS-0111AP / 6-Sl-441 / 7 | |||
Liquid Penetrant Examination Report PT-17-002 of 12050-WMKS-0111AP / 6-Sl-441 / | |||
SW32 | |||
Liquid Penetrant Examination Report PT-17-006 of 12050-WMKS-0111AQ / 6-CH-603 / 8 | |||
Radiography Report NDE-R-2017-48 of Weld Joint #7 | |||
Radiography Report NDE-R-2017-48 of Weld Joint #8 | |||
Radiography Report NDE-R-2017-48 of Weld Joint #SW32 | |||
Ultrasonic Examination Report UT-17*002 of 12050-WMKS-0111AP / 6-Sl-441 / SW32 | |||
Ultrasonic Examination Report UT-17*003 of 12050-WMKS-0111AP / 6-Sl-441 / 7 | |||
Ultrasonic Examination Report UT-17*011 of 12050-WMKS-0111AP / 6-Sl-441 / 7 | |||
Ultrasonic Examination Report UT-17*012 of 12050-WMKS-0111AP / 6-Sl-441 / SW32 | |||
WO 59103105688, Remove/Reinstall Valve (02-CC-328-VALVE) and Piping, ASME Class 3 | |||
Repair/Replacement Plan 2017-111 | |||
Weld Map for location 02-CC-328-VALVE | |||
Weld Data Record for Welds # 34 | |||
Weld Material Field Control Sheet for Welds # 34 | |||
Welding Technique Sheet for Welding Technique Number 103, Revision 8 | |||
Procedure Qualification Record 101, Revision 5 | |||
Procedure Qualification Record 102, Revision A | |||
Procedure Qualification Record 103 | |||
Procedure Qualification Record 105, Revision 4 | |||
Procedure Qualification Record 135 | |||
Welder Performance Qualification (WPQ) Records of R. Stewart, J. Olson, and A. | |||
Pennington | |||
Other Documents | |||
ASME Code Cases N-729-1 and N-729-4 | |||
Ultrasonic Examination Report UT-17-038 of 12050-WMKS-0102B / 16-WFPD-423 / 40, Elbow | |||
to Nozzle | |||
Ultrasonic Examination Report UT-17-037 of 12050-WMKS-0102A / 16-WFPD-424 / 75, Elbow | |||
to Nozzle | |||
Calibration Certificate digital thermometer, Serial Number 1079BGCY | |||
Certificate of Calibration (Certificate #172330SRAM1) for light meter, serial number OSRAM-1 | |||
Certificate of Certification for Ultra Gel II, Batch# 12J066 | |||
Certification for Magnaflux Spotcheck, SKC-S, Batch #: 16H07K | |||
Certification for Magnaflux Penetrate, SKC-S, Batch #: 16H07K | |||
Certificate of Certification, Spotcheck Penetrant, SKL-SP2, Batch# 15J02K | |||
Certificate of Certification, Spotcheck Developer, SKD-S2, Batch# 14K04K | |||
Krautkramer Transducer Certificate of Conformity for Serial Number OlCXBJ | |||
Krautkramer Transducer Certificate of Conformity for Serial Number OlCXBN | |||
NDE Personnel Certification Records for J. Block, T. Coburn, and C. Popp | |||
Relief Request N2-I4-NDE-002 | |||
Report Number L-17-012, Ultrasonic Instrument Linearity for Olympus Model EPOCH 600, | |||
Serial Number 150864802 | |||
8 | |||
Self-Assessment Report (SAR) 000486, Nuclear Welding Program Formal Fleet Self- | |||
Assessment | |||
SAR 002257, Inservice Inspection/Risk-Informed Inservice Inspection Program Formal Self- | |||
Assessment | |||
SAR 002813, Boric Acid Corrosion Control Program (BACCP) Self Assessment | |||
Section 1R11: Licensed Operator Requalification Program and Licensed Operator | |||
Performance | |||
Licensed Operator Requalification Program, Cycle 17-6, Segment 1B, Revision 5 | |||
Licensed Operator Requalification Program, Cycle 17-6, Segment 1C, Revision 4 | |||
2-OP-3.7, Unit Shutdown from Mode 1 to Mode 5 for Refueling, Revision 48 | |||
Section 1R12: Maintenance Effectiveness | |||
1-PT-97.1B, Operations Periodic Test, Spent Fuel Pit Cooling Pump (1-FC-P-1B) Test, | |||
Revision 17 | |||
Nuclear Electric Insurance Limited Loss Control Manual, January 2017 Edition | |||
North Anna Narrative Logs regarding 1-FC-P-1B dated January 1, 2017-August 2, 2017 | |||
Vibration Trend for 1-FC-P-1B from June 24, 2008 to August 2, 2017 | |||
Corrective Action Documents | |||
CR 1073731, 1-FC-P-1B Vibration Data in Alert Range | |||
Work Order | |||
WO59103007607 | |||
Section 1R13: Maintenance Risk Assessments and Emergent Work Control | |||
NUMARC 93-01, Industry Guidelines for Monitoring the Effectiveness of Maintenance at | |||
Nuclear Power Plants, Revision 4A | |||
1-Log-14, Non-Routine Surveillance Log, Initiate the following Maintenance Rule(a)(4) Fire RMA | |||
Defense-in-Depth Measures for TR 7.5 | |||
WM-AA-301, Operational Risk Assessment, Revision 14 | |||
1-AP-27, Malfunction of Spent Fuel Pit System, Revision 26 | |||
Work Order | |||
WO59103098001 | |||
WO59102932957 | |||
WO59103101877 | |||
WO59102933066 | |||
Section 1R15: Operability Determinations and Functionality Assessments | |||
OD CA 3063143 - Degraded Non-Conforming Condition of SW Traveling Screens due to | |||
Electrical Design Inadequacy Identified in CR1074806 | |||
CR1074806,Reduced Margin due to Temperature Derating of SWPH MCC Bucket | |||
Transformers/Fuses | |||
Operation Department Shift Orders for August 25, 2017 | |||
OP-AA-102, Operability Determination, Revision 15 | |||
9 | |||
1-AR-J-H6, SW Screens 1A-1B No Rotation, SW Screens Hi P, Revision 3 | |||
ME-0305, Service Water Pump NPSH, Revision 0 | |||
CR554449, 1-CC-P-1B Outboard Pump Bearing Oil Sample Discoloration | |||
CA286656, Track and document oil sample results for 1-CC-P-1B | |||
Engineering Log Entry for 7/25/2017, 1-CC-P-1B Oil Sample has Visible Ferrous Particulates | |||
Work Order | |||
WO59103098137 | |||
WO05910312409 | |||
Corrective Action Documents | |||
CR 1073832 | |||
CR 3062123 | |||
CR 1079324 | |||
CR 1000423 | |||
Section 1R19: Post Maintenance Testing | |||
Procedures, Guidance Documents, and Manuals | |||
0-PT-100.2, Fire Protection Pumps - Annual Test, Revision 26 | |||
CR1075127, Tagged 1FP-P-2 for pump replacement | |||
CR1075979, 1-FP-P-2 New Pump high vibrations on return to service | |||
1-PT-77.11B.1, Control Room Chiller 1-HV-E-4B IST Comprehensive Pump and Valve Test, | |||
Revision 12-OTO1 | |||
Work Order | |||
WO59102873252 | |||
WO59103085096 | |||
Section 1R22: Surveillance Testing | |||
Procedures, Guidance Documents, and Manual | |||
1-PT-71.3Q, 1-FW-3B, B Motor-Driven AFW Pump, and Valve Test, Revision 53 | |||
CR1073791, 2-PT-71.3Q.1 test results need engineering evaluation | |||
2-PT-17.1, Control Rod Operability, Revision 41 | |||
2-AP-1.2, Dropped Rod, Revision 18 | |||
2-AR-A-H1, Rod Bank A Lo/lo-lo Limit, Revision 1 | |||
2-AR-A-H2, Rod Bank B Lo/lo-lo Limit, Revision 1 | |||
2-AR-A-H3, Rod Bank C Lo/lo-lo Limit, Revision 3 | |||
2-AR-A-H4, Rod Bank D Lo/lo-lo Limit, Revision 3 | |||
2-PT-82.4A, 2H Diesel Generator Test (Start by ESF Actuation), Revision 75 | |||
2-PT-82.4B, 2J Diesel Generator Test (Start by ESF Actuation), Revision 72 | |||
2-PT-82.2A, 2H Diesel Generator Test (Simulated Loss of Off-Site Power), Revision 74 | |||
2-PT-82.2A, 2J Diesel Generator Test (Simulated Loss of Off-Site Power), Revision 76 | |||
2-PT-83.12H, 2H Diesel Generator Test (Start by ESF Actuation) followed by 24-hour Run and | |||
Hot Restart Test, Revision 29 | |||
2-PT-142.10A.1, Valve Inservice Inspection Associated with 2-EG-TK-2HA for 2-EB-15 Check | |||
Valve, Revision 3 | |||
2-PT-142.10A.2, Valve Inservice Inspection Associated with 2-EG-TK-2HB for 2-EB-61 Check | |||
Valve, Revision 3 | |||
Procedure 2-PT-36.7.1, Engineered Safety Features and Containment Isolation Valve | |||
10 | |||
Response Time, Rev 23 | |||
Procedure 2-PT-57.5A, Leak Rate Test of 2-SI-P-1A and Associated Piping and Inservice | |||
Inspection for 2-SI-6, Rev 21 | |||
Procedure 2-PT-57.5B, Leak Rate Test of 2-SI-P-1B and Associated Piping and Inservice | |||
Inspection for 2-SI-29, Rev 21 | |||
Procedure 2-PT-213.5J, Valve Inservice Inspection (2-QS-MOV-201B), Rev 10 | |||
Work Order | |||
WO59102098166 | |||
WO59080458701 | |||
WO59101762949 | |||
WO59060120201 | |||
Section 2RS1: Radiological Hazard Assessment and Exposure Controls | |||
Procedures, Guidance Documents, and Manuals | |||
HP-1032.080, Controlled Area and Unrestricted Area Radiological Surveys, Rev. 9 | |||
HP-1032.110, Dose Rate Trending, Rev. 1 | |||
HP-1032.131, Initial Movement of Irradiated Fuel Assemblies to and From the Reactor Vessel, | |||
Rev. 0 | |||
HP-1032.140, Guidance/Actions to Take When Licensed Material is Detected at Exposure | |||
Control, Rev. 0 | |||
HP-1032.202, Radiological Informational Posting, Rev. 0 | |||
North Anna Power Station Outage ALARA Guide, Unit Two Refueling Outage September 2017 | |||
RP-AA-101, Radiological Protection Organization and Administration, Rev. 3 | |||
RP-AA-109, Radiological Survey Program, Rev. 0 | |||
RP-AA-201, Access Controls for High and Very High Radiation Areas, Rev. 8 | |||
RP-AA-202, Radiological Posting, Rev. 10 | |||
RP-AA-222, Radiation Surveys, Rev. 3 | |||
RP-AA-223, Contamination Surveys, Rev. 4 | |||
RP-AA-224, Airborne Radioactivity Surveys, Rev. 3 | |||
RP-AA-225, Unrestricted Release of Material, Rev. 6 | |||
RP-AA-226, Alpha Monitoring, Rev. 5 | |||
RP-AA-230, Personnel Contamination Monitoring and Decontamination, Rev. 11 | |||
RP-AA-240, Discrete Radioactive Particle Control, Rev. 2 | |||
RP-AA-270, Providing HP Coverage During Work, Rev. 2 | |||
RP-AA-271, Use of Remote Monitoring, Rev. 2 | |||
RP-AA-275, Radiological Risk Assessment Process, Rev. 3 | |||
VPAP-2101, Radiation Protection Program, Rev. 35 | |||
Records and Data | |||
Air Sample Analysis: 259' A Gas Stripper, Routine Gas & Particulate, Filename: 13-Jul-17- | |||
400030 and 13-Jul-17-400031, 7/13/2017 and Filename: 10-Aug-17-400017 and 400020, | |||
8/10/2017; 259' B Gas Stripper, Routine Gas & Particulate, Filename: 13-Jul-17-400032 | |||
and 13-Jul-17-400032, 7/13/2017 and Filename: 10-Aug-17-400018 and 400019, 8/10/2017; | |||
Unit 1 Quench Spray Pump House and Main Steam, Routine Particulate, Filename: and 01- | |||
Aug-17-400028, 8/1/2017 and Filename: 05-Sep-17-400001, 9/5/2017; Hot Lab, Routine | |||
Particulate, Filename: 06-Jul-17-400003, 7/6/2017 and Filename: 03-Aug-17-400001, | |||
8/3/2017 | |||
11 | |||
List, Location of Locked High Radiation Areas (LHRAs) and Very High Radiation Areas | |||
(VHRAs) [including areas with the potential to become a LHRA during routine operations or | |||
outages], 8/29/2017 | |||
List, Non-Fuel Items Stored in the NAPS Spent Fuel Pool [based on Assembly Information | |||
Reports, Fig File: N2EOC25.fig, 8/24/2017 and 8/30/2017], 8/30/2017 | |||
List, 2017 Non-Outage RWP [including dose and dose rate alarms by task], 7/26/2017 | |||
List, 2017 Unit 2 Outage RWPs [including dose and dose rate alarms by task], 9/6/2017 | |||
Non-Outage Radiological Surveys: Decon Building 251' Spent Resin Hold-up Tank Area, | |||
1/5/2015; Aux Building, 274' VCT Cubes, 2/10/2016; U2 Containment, 216' lncore access | |||
(keyway), 4/5/2016; U1 Containment, 216' lncore access (keyway), 9/16/2016; U2 Reactor | |||
Cavity, 4/4/2017; Unit 2 Unit 1 and Unit 2 Equipment Hatch Platforms, Perform PT-60.1B | |||
and Alarm Checks, 4/16/2017; Unit 2 Personnel Hatch, Security Alarm Checks, 6/25/2017; | |||
Unit 1 Personnel Hatch, Security Alarm Checks, 6/25/2017; Demin Alley, Resin Transfer, | |||
6/28/2017; Waste Solids Area, 6/29/2017; Decon Building, 251', 6/29/2017; Aux Building, | |||
259' Gas Strippers, 7/13/2017 and 8/10/2017; Aux Building, 244' Gas Strippers, 7/13/2017 | |||
and 8/10/2017; Unit 1 Quench Spray Pump House and Main Steam 272, 8/1/2017 and | |||
9/5/2017; U1 & U2 Charging Pump Cubicles, 7/31/2017 and 9/4/2017; Health Physics | |||
Office, Count Room, and Chemistry Office/Lab, 7/6/2017 and 8/3/2017 | |||
NSTS Annual Inventory Reconciliation Report, for License Number NPF-4, Confirmation of | |||
Annual Inventory Reconciliation, 1/20/2017 | |||
Outage Radiological Surveys: U2 Reactor Cavity, Initial Cavity Dose Rate Survey, 9/10/2017; | |||
U2 Reactor Cavity, Initial Cavity Contamination Survey, 9/10/2017; U2 Containment, 241' | |||
"B" Loop Room 2-PT-46.21, 9/10/2017; U2 Containment, 231' RHR and Excess Letdown | |||
HX Platform, 9/10/2017; U2 Containment, Top of Pressurizer, 9/10/2017; U2 Reactor Head, | |||
Dose Rate and Contamination Survey, 9/11/2017; U2 Containment, Top of Pressurizer | |||
Removal of 2-RC-SV-2115B, 9/12/2017; U2 Reactor Cavity, Reactor Head Lift, 9/15/2017; | |||
U2 Containment, 241' During Head Lift & Move To Lower Containment, 9/15/2017; U2 | |||
Containment, 262' During Head Lift & Move To Lower Containment, 9/15/2017; U2 | |||
Containment, 216' Reactor Head on Head Stand in Lower Containment, 9/15/2017; U2 | |||
Containment, 291' Refuel Floor Post Head Lift, 9/15/2017; U2 Reactor Cavity, Upper | |||
Internals Lift & Move, 9/16/2017; U2 Containment, 291', 9/18/2017; U2 Reactor Cavity, | |||
Remove and Cut 11 Thimbles, 9/19/2017; U2 Containment 262' "B" Cubicle, Open & Inspect | |||
2-CH-340, 9/21/2017; | |||
Radiation Work Permit (RWP) 17-2002, Maintenance activities within the Unit 2 Circulating | |||
Water Tunnel, Rev 0 | |||
Radioactive Source Master Listing (NAPS) [radioactive source inventory], 8/21/2017 | |||
RWP 17-2201, lncore Drive unit 5 and 10 path maintenance, Rev. 0 | |||
RWP 17-2215, Valve Maintenance in Locked High Radiation Areas, Rev. 0 | |||
RWP 17-2251, Disassemble and reassemble Reactor Vessel Head, Rev. 0 | |||
RWP 17-2266, Perform DCP 15-00088, lncore Flux Thimble modifications, Rev. 0 | |||
Site-Wide Communication, U2 RFO RP Update, Radiological Postings, 9/22/2017 | |||
Spreadsheet, North Anna Power Station Radiological Survey Schedule Check Sheet [Survey | |||
Frequency], August 2017 | |||
Corrective Action Documents | |||
PI-AA-200, Corrective Action, Rev. 33 | |||
PI-AA-300, Cause Evaluation, Rev. 14 | |||
Nuclear Oversight Audit Report, Audit 16-04 RP, PCP, Chemistry & Millstone Refueling, | |||
5/26/2016 | |||
Self-Assessment, PIR Number 1019510, Exit Monitor Reliability, 4/15/2016 | |||
Self-Assessment, PIR Number 1057549, Radiological Work Control Program Review, 3/14/2017 | |||
12 | |||
Self-Assessment Results Measurement Review, PIR1019510 - Exit Monitor Reliability | |||
CR 1032511 | |||
CR 1032902 | |||
CR 1032903 | |||
CR 1034024 | |||
CR 1034627 | |||
CR 1034930 | |||
CR 1039806 | |||
CR 1043768 | |||
CR 1061774 | |||
CR 1067020 | |||
CR 1074424 | |||
CR 1078100 | |||
CR 1078223 | |||
CR 1078811 | |||
Section 2RS6: Liquid and Gaseous Effluents | |||
Procedures, Guidance Documents, and Manuals | |||
HP-3010-020, Radioactive Liquid Waste Release Permits, Rev. 5 | |||
HP-3010-021, Radioactive Liquid Waste Sampling and Analysis, Rev. 23 | |||
HP-3010-031, Radioactive Gaseous Waste Sampling and Analysis, Rev. 40 | |||
HP-3010-032, Radioactive Gaseous Waste Accountability and Dose Calculations, Rev. 15 | |||
HP-3010.040, Radiation Monitoring System Setpoint Determination, Rev. 26 | |||
VPAP-2103N, Offsite Dose Calculation Manual (North Anna), Rev. 27 | |||
0-HSP-LQC-001, Confirmatory Measurements Using Blind Samples, Rev. 0 | |||
0-PT-37.1, Radiation Monitoring Equipment Source Check, Rev. 08 | |||
Records and Data | |||
Annual Radioactive Effluent Release Report, 2015 and 2016 | |||
Certificate Detalonnage (Calibration Certificate), MGP Instruments, S/N 6012 and 6054, | |||
10/19/2000 | |||
Certificate of Conformance, Westinghouse Electric Corporation, S/N 01-315 and 01-317, | |||
05/12/1989 | |||
Certificate of Conformance, Westinghouse Electric Corporation, S/N 02-691 and 02-754, | |||
07/01/1989 | |||
Eckert & Ziegler Radiochemistry Cross Check Program for 2015, 2016 and the 1st Quarter 2017 | |||
Gaseous Release Permit# G-20170801-277-B, BRT Vent, 08/07/2017 | |||
Gaseous Release Permit# G-20170801-276-B, Aux Bldg Roof Fans, 08/07/2017 | |||
Gaseous Release Permit# G-20170801-283-C, Unit 1 CAE, 08/07/2017 | |||
Gaseous Release Permit # G-20160223-072-B, Process Vent, 02/23/2016 | |||
Liquid Release Permit # L-20170728-064-C, Clarifier, 07/28/2017 | |||
Liquid Release Permit # L-20170701-066-C, Unit 1 HCBD, 07/01/2017 | |||
Liquid Release Permit # L-20170701-067-C, Unit 2 HCBD, 07/01/2017 | |||
List, Effluent Radiation Monitors Out of Service for Greater than 24 Hours since 06/01/2015 | |||
North Anna Power Station Equipment Reliability List for System Radiation Monitoring, Updated | |||
08/26/2014 | |||
Nuclide Distribution Report, 10CFR61 Waste Stream Analyses for Multiple Waste Streams, | |||
2016 | |||
Radioactive Sealed Source Certificate and Test Report, QSA Global, S/N 8788GS, 03/13/2001 | |||
Unplanned Gaseous Release Record, ID 16-AGR-01, U2 RWST Gas Space, 01/20/2016 | |||
13 | |||
Unplanned Gaseous Release Record, ID 16-AGR-02, Process Vent Hi Hi Alarm, 02/23/2016 | |||
Work Order (WO) 5910201495932, U1 RM-178 Process Vent Normal Range, 01/23/2014 | |||
WO 59102473155, U1 SW-RM-130, Discharge Tunnel Effluent Radiation Monitor Calibration, | |||
08/05/2015 | |||
WO 59102488682, LW-RM-110 Clarifier Hold Up Tank Inlet Monitor Calibration, 06/17/2014 | |||
WO 59102721714, 0-PT-77.4A, Laboratory Analysis- 1-HV-FL-3A ECCS PREACS, completed | |||
07/09/2015 | |||
WO 59102735956, Condenser Air Ejector In-Line Radio Gas Monitor (2-SV-RM-221) Channel | |||
Calibration, 12/04/2015 | |||
WO 591029166517, Condenser Air Ejector In-Line Radio Gas Monitor (2-SV-RM-221) Channel | |||
Calibration, 06/06/2017 | |||
WO 59102739309, 0-PT-38.3.4, Calibration 1-HV-F-1212A, Vent A Flow, 12/10/2015 | |||
WO 59102784040, 0-PT-77.4B, Laboratory Analysis- 1-HV-FL-3B ECCS PREACS, completed | |||
02/28/2016 | |||
WO 59102807780, 0-PT-77.14A, In Place Filter Test 1-HV-FL-3A ECCS PREACS, completed | |||
08/24/2016 | |||
WO 59102825717, 0-PT-37.1, Radiation Monitoring Equipment Source Check, 08-05-2015 | |||
WO 59102882205, Vent Stack A Normal and High Range Effluent Radiation Monitor (VG-RM- | |||
179) Channel Calibration, 01/18/2017 | |||
WO 59102882688, 0-PT-77.14B, In Place Filter Test 1-HV-FL-3B ECCS PREACS, completed | |||
02/16/2017 | |||
WO 59102888990, LW-RM-111 Clarifier Hold Up Tank Outlet Monitor Calibration, 09/04/2015 | |||
WO 59102892494, LW-RM-111 Clarifier Hold Up Tank Outlet Monitor Calibration, 08/18/2016 | |||
WO 59102904056, LW-RM-110 Clarifier Hold Up Tank Inlet Monitor Calibration, 03/15/2017 | |||
WO 59102917391, 0-PT-38.3.4, Calibration 1-HV-F-1212A, Vent A Flow, 06/13/2017 | |||
0-PT-487.10, Radiological Environmental Monitoring Program, Land Use Census, 10/15/2015 | |||
0-PT-487.10, Radiological Environmental Monitoring Program, Land Use Census, 10/19/2016 | |||
Corrective Action Documents | |||
PI-AA-200, Corrective Action, Rev. 33 | |||
Self-Assessment PIR1003232, Radioactive Effluent Control Program, 11/20/2015 | |||
CR 1043795 | |||
CR 1005452 | |||
CR 1024639 | |||
CR 1073079 | |||
CR 1010910 | |||
CR 582501 | |||
CR 1033833 | |||
CR 1072741 | |||
Section 2RS7: Radiological Environmental Monitoring Program (REMP) | |||
Procedures, Guidance Documents, and Manuals | |||
HP-1033.620, Portable Air Samplers Calibration and Operation, Rev. 9 | |||
HP-3051.010, Radiological Environmental Monitoring Program, Rev. 29 | |||
HP-3051.020, Ground Water Protection Program, Rev. 9 | |||
RP-AA-502, Groundwater Protection Program, Rev. 5 | |||
RP-AA-111-1012, Radiological Environmental Monitoring Program Review, Rev. 1 | |||
VPAP-2103N, Offsite Dose Calculation Manual (North Anna), Rev. 27 | |||
0-GEP-14, Spent Fuel Pool Telltale Drain Evaluation, Rev. 2 | |||
0-ICP-MM-MIS-001B, Backup Meteorological Tower Instrumentation Calibration, Rev. 3 | |||
14 | |||
0-ICP-MM-MIS-001P, Primary Meteorological Tower Instrumentation Calibration, Rev. 6 | |||
0-PT-440, Monitoring Normally Non-Radioactive systems for Radioactive Contamination, Rev. 9 | |||
Records and Data | |||
Annual Radiological Environmental Operating Report (AREOR), North Anna Power Station for | |||
2015 and 2016, April 2015 and 2016 | |||
Annual Radioactive Effluent Release Report (ARERR), North Anna Power Station for 2015 and | |||
2016, April 2015 and 2016 | |||
Environmental Sample Log [REMP Sampling Schedule] for August 2017 | |||
Memorandum with Attachment, North Anna Meteorological Data [Joint Frequency Distributions | |||
and Data Recovery Percentage] for 2014, 2015, and 2016, 1/14/2015, 3/10/2016, and | |||
2/17/2017 | |||
Radiological Decommissioning Record, Spill below 2-QS-41 at U-2 RWST, Sample ID# 25- | |||
SEP-15-400033, CR1011040, 9/25/2015 | |||
Radiological Decommissioning Record, NaOH Spill, Sample ID# 16-MAR-16-400072, | |||
CR1030721, 3/16/2016 | |||
Radiological Decommissioning Record, Spill below 2-QS-38, Sample ID# 29-MAR-16-400021, | |||
CR1032085, 3/29/2016 | |||
Radiological Decommissioning Record, Spill below 1-QS-24 at U-1 RWST, Sample ID# 20-FEB- | |||
17-400020, CR1060475, 2/20/2017 | |||
REMP Air Sampler Certificate of Calibration: Kit# 15, 10/21/2015, and 10/19/2016; Kit# 14, | |||
10/21/2015, and 10/19/2016; Kit# 13, 10/21/2015, and 10/19/2016; Kit# 12, 10/21/2015, and | |||
10/19/2016; Kit# 11, 10/21/2015, and 10/19/2016; Kit# 10, 10/21/2015, and 10/19/2016; Kit# 9, | |||
10/27/2015, and 10/19/2016; Kit# 8, 10/21/2015, and 10/19/2016; Kit# 7, 10/21/2015, and | |||
10/19/2016; Kit# 6, 10/21/2015, and 10/19/2016; Kit# 5, 10/21/2015, 10/19/2016; Kit# 4, | |||
10/21/2015, and 10/19/2016; Kit# 3, 10/21/2015, and 10/19/2016; Kit# 2, 10/27/2015, and | |||
10/20/2016; Kit# 1, 10/21/2015, and 10/20/2016 | |||
Spreadsheets, Direct Radiation Measurements - Sector Quarterly TLD Results [REMP TLDs], | |||
for 2015, 2016, and 1st Quarter 2017 | |||
Sample Collection/Receipt Sheet [REMP Air Sample Data for Vendor], 8/8/2017 | |||
Vendor Laboratory Cross Check Performance Summary for 2015 and 2016, [including Eckert & | |||
Zeigler Analytics, Inc, DOE's Mixed Analyte Performance Evaluation Program (MAPEP), and | |||
Environmental Resource Associates, (ERA)], Data from 2015 and 2016 AREOR | |||
Work Order (WO) 59102985187, 0-PT-40.1, Meteorological Monitoring System Calibration, | |||
12/20/2016 | |||
WO 59102932630, 01-MM-TWR-PRI-UNIT, Annual Tower Inspection [Primary Meteorological | |||
Tower], 5/17/2017 | |||
WO 59103043600, 0-PT-40.1, Meteorological Monitoring System Calibration, 6/12/2017 | |||
0-GEP-14, Spent Fuel Pool Telltale Drain Evaluation [Inspection by Engineering], 12/8/2016 and | |||
6/8/2017 | |||
2012 Priority Index Spreadsheet, North Anna Power Station Unit 1 [ranking of Structure, | |||
System, and Component risk to groundwater] | |||
2012 Priority Index Spreadsheet, North Anna Power Station Unit 2 [ranking of Structure, | |||
System, and Component risk to groundwater] | |||
Corrective Action Documents | |||
PI-AA-200, Corrective Action, Rev. 33 | |||
Audit 15-10: Offsite Dose Calculation Manual, Radiological Environmental Monitoring Program, | |||
Environmental Protection Plan, 12/16/2015 | |||
PIR1019508, Radiological Environmental Monitoring Program Review, North Anna Power | |||
Station, Q4 2014 to Q4 2015, 5/26/2016 | |||
15 | |||
CR 582528 | |||
CR 1002672 | |||
CR 1005525 | |||
CR 1012719 | |||
CR 1021114 | |||
CR 1023150 | |||
CR 1038101 | |||
CR 1055473 | |||
CR 1063665 | |||
CR 1065819 | |||
CR 1071212 | |||
Section 2RS8: Radioactive Material Processing and Transportation | |||
Procedures, Guidance Documents, and Manuals | |||
2-MOP-20.2, Resin Discharge and Addition to 2-CH-I-2, Cation Bed | |||
Demineralizer, Rev. 16 | |||
HP-1072.020, Sampling, Analyzing, and Classifying Solid Radioactive Waste, | |||
Rev. 11 | |||
HP-1071.021, Storing Radioactive Material Outside the Protected Area, Rev. 21 | |||
HP-1071.040, Packaging and Shipment of Radioactive Material, Rev. 17 | |||
HP-1072.080, Radioactive Waste Transfer to Erwin Resin Solutions, Rev. 9 | |||
PI-AA-200, Corrective Action, Rev. 33 | |||
RP-AA-232, Radioactive Material Control, Rev. 9 | |||
VPAP 2104, Dominion Station Administrative Procedure, Radioactive Waste Process Control | |||
Program (PCP), Rev. 8 | |||
Records and Data | |||
HP-1071.021, Attachment 3, Radioactive Material Inventory Record for Storage Locations | |||
Outside the Protected Area, 3/15/17 and 6/12/17 | |||
Radiological Survey, Decontamination Building, 217 Elevation, Waste Solidification Area, | |||
9/17/17 | |||
Radiological Survey, 17-RHR-31 Nut Runner from SPS, 9/19/17 | |||
Radioactive Waste Packaging, Transportation, and Disposal Training (PowerPoint Slides), | |||
HPTCTP-16-Cycle-02-LP-1 (TIR 14586 - Rev. 1) | |||
RP-AA-232, Attachment 2, Container Inspection Checklist, 5/15/17 and 8/7/17 | |||
Shipping Records and Radwaste Data | |||
Shipment No. 15-ERS-01, Primary Resin, 3/6/15 | |||
Shipment No. 16-DUR-24, DAW / Oil, 3/24/16 | |||
Shipment No. 17-DUR-02, Dewatered Blended Resin, 3/3/17 | |||
Shipment No. 17-1032, U1 Demin Liquid Sample, 9/21/17 | |||
10 CFR Part 61 Waste Stream Analyses: U1 DAW, 10/6/16; U2 DAW, 4/5/16; SRHT, 9/20/16 | |||
Corrective Action Documents | |||
CR 1003460 | |||
CR 1028592 | |||
CR 1033755 | |||
CR 1036591 | |||
CR 1042776 | |||
CR 1063026 | |||
16 | |||
CR 1068352 | |||
NUPIC Audit / Survey No. 23931, Energy Solutions, 6/15/15 | |||
Section 4OA1: Performance Indicator Verification | |||
Procedures and Guidance Documents | |||
HP-3010.022, Radioactive Liquid Waste Accountability and Dose Calculations, Rev. 6 | |||
HP-3010.032, Radioactive Gaseous Waste Accountability and Dose Calculations, Rev. 15 | |||
LI-AA-500, NRC/INPO/WANO Performance Indicator and MOR Reporting, Rev. 2 | |||
PI-AA-100-1000, Performance Indicators, Rev. 5 | |||
RP-AA-111, Monitoring and Improving Radiological Performance, Rev. 2 | |||
RP-AA-112, Radiation Safety Performance Indicator Reporting, Rev. 4 | |||
VPAP-2802, Notifications and Reports, Rev. 43 | |||
Records and Data | |||
RP-AA-124, Attachment 6, Electronic Dosimeter Dose/Dose Rate Alarm Log, 07/11/2017 | |||
Abnormal Gaseous Release, 16-AGR-01, 1/20/2016 | |||
Abnormal Gaseous Release, 16-AGR-02, 2/23/2016 | |||
Gaseous Release Permit [Gas Permit Post-Release Data], G-20160120-033-B, 1/20/2016 | |||
Gaseous Release Permit [Gas Permit Post-Release Data], G-20160223-072-B, 2/23/2016 | |||
Gaseous Effluents Cumulative Dose Summary, January through June 2017, 7/11/2017 | |||
NAPS NRC Performance Indicator, April 2016 through July 2017, various dates | |||
Report, OpenEMS, Gas Status Summary Reports, January through June 2017 [summation of | |||
all gaseous releases, including off-site dose summaries], 07/18/2017 | |||
Report, OpenEMS, Liquid Status Summary Reports, January through June 2017 [summation of | |||
all liquid releases, including off-site dose summaries], 07/18/2017 | |||
Corrective Action Documents | |||
CR 1033397 | |||
CR 1034627 | |||
CR 1043607 | |||
CR 1064034 | |||
}} |
Latest revision as of 08:50, 29 October 2019
ML17312B320 | |
Person / Time | |
---|---|
Site: | North Anna |
Issue date: | 11/08/2017 |
From: | Masters A NRC/RGN-II/DRP/RPB5 |
To: | Stoddard D Virginia Electric & Power Co (VEPCO) |
References | |
IR 2017003 | |
Download: ML17312B320 (39) | |
See also: IR 05000338/2017003
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
November 8, 2017
Mr. Daniel G. Stoddard
President and Chief Nuclear Officer
Innsbrook Technical Center
5000 Dominion Boulevard
Glen Allen, VA 23060
SUBJECT: NORTH ANNA POWER STATION - NRC INTEGRATED INSPECTION
REPORT 05000338/2017003 AND 05000339/2017003
Dear Mr. Stoddard:
On September 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) completed an
inspection at your North Anna Power Station, Units 1 and 2. On October 18, 2017, the NRC
inspectors discussed the results of this inspection with Mr. L. Lane and other members of your
staff. Inspectors documented the results of this inspection in the enclosed inspection report.
No NRC-identified or self-revealing findings were identified during this inspection.
However, NRC inspectors documented one licensee-identified violation, which was determined
to be of very low safety significance, in this report. The NRC is treating this violation as a
non-cited violation (NCV) consistent with Section 2.3.2.a of the NRC Enforcement Policy.
If you contest the violation or significance of the NCV, you should provide a response within 30
days of the date of this inspection report, with the basis for your denial, to the Nuclear
Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555-001; with
copies to the Regional Administrator Region II; the Director, Office of Enforcement, United
States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident
Inspector at the North Anna Power Station.
D. Stoddard 2
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Sincerely,
/RA/
Anthony D. Masters, Chief
Reactor Projects Branch 5
Division of Reactor Projects
Docket Nos.: 05000338, 05000339
Enclosure:
IR05000338/2017003 and 05000339/2017003
w/Attachment: Supplemental Information
cc Distribution via ListServ
OFFICE RII:DRP RII:DRP RII:DRP RII:DRP RII:DRP RII:DRS
NAME S. Ninh BBishop GCroon GEatmon RCarrion RKellner
DATE 11/1/2017 10/30/2027 10/31/2017 10/30/2017 10/31/2017 10/30/2017
OFFICE RII:DRS RII:DRP RIIDRP
NAME JRivera WPursley AMasters
DATE 10/30/17 11/1/2017 11/8/2017
U.S. NUCLEAR REGULATORY COMMISSION
REGION II
Docket Nos: 50-338, 50-339
Report No: 05000338/2017003 and 05000339/2017003
Licensee: Virginia Electric and Power Company (VEPCO)
Facility: North Anna Power Station, Units 1 & 2
Location: Mineral, Virginia 23117
Dates: July 1, 2017 through September 30, 2017
Inspectors: G. Croon, Senior Resident Inspector
G. Eatmon, Resident Inspector
R. Carrion, Senior Inspector (Sections 1R07 and 1R08)
R. Kellner, Senior Health Physicist (Sections 2RS1, 2RS7, 4OA1
and 4OA7)
J. Rivera, Health Physicist (Section 2RS8)
W. Pursley, Health Physicist (Section 2RS6)
Approved by: Anthony D. Masters, Chief
Reactor Projects Branch 5
Division of Reactor Projects
Enclosure
SUMMARY
IR 05000338/2017003, 05000339/2017003; July 1, 2017 - September 30, 2017; North Anna
Power Station, Units 1 and 2. Routine Integrated Inspection Report.
The report covered a three-month period of inspection by resident inspectors, one regional
based inspector, and three health physicists. The significance of inspection findings are
indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter (IMC) 0609, Significance Determination Process (SDP), dated April 29, 2015. All violations of NRC
requirements are dispositioned in accordance with the NRCs Enforcement Policy dated
February 4, 2015. The NRCs program for overseeing the safe operation of commercial nuclear
power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 6.
No NRC-identified or self-revealing findings were identified.
A licensee-identified violation of very low safety significance has been reviewed by the
inspectors. Corrective actions taken or planned by the licensee have been entered into the
licensees corrective action program. This violation and its associated corrective action tracking
number are listed in Section 4OA7 of this report.
REPORT DETAILS
Summary of Plant Status
Unit 1 began the inspection period at approximately 100 percent rated thermal power (RTP),
and operated at RTP for the remainder of the inspection period.
Unit 2 began the inspection period at approximately 100 percent RTP. On September 9, 2017,
the unit was taken offline for a planned refueling outage. The unit remained offline for the
remainder of the inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, and Barrier Integrity
1R01 Adverse Weather Protection
.1 Seasonal Extreme Weather Conditions
a. Inspection Scope
The inspectors reviewed the licensees adverse weather preparations for hot weather
operations, specified in 0-GOP-4.1, Hot Weather Operations, Rev. 36, 0-GOP-5.5,
EDG Hot Weather Operation, Rev.14, and the licensees corrective action program
(CAP) database for hot weather related issues. The inspectors walked down two risk-
significant systems/areas listed below to verify compliance with the procedural
requirements and to verify that the specified actions provided the necessary protection
for the structures, systems, or components.
b. Findings
No findings were identified.
.2 Impending Adverse Weather Conditions
a. Inspection Scope
The inspectors performed a site-specific weather-related inspection due to anticipated
adverse weather conditions. On April 17, 2017, the inspectors reviewed the licensee
response to severe storm warnings, with tornado watch, and high wind warnings of 40
miles an hour for the area. Specifically, the inspectors reviewed licensee adverse
weather response procedures, including 0-AP-41, Severe Weather Conditions,
Rev. 61, and site preparations including work activities that could impact the overall
maintenance risk assessments.
4
b. Findings
No findings were identified.
.3 Offsite Power and Alternate AC Power
a. Inspection Scope
The inspectors verified that plant features and procedures for operation and continued
availability of offsite and alternative alternating current (AC) power systems were
appropriate. The inspectors reviewed the licensees procedures affecting those areas,
and the communications protocols between the transmission system operator and the
nuclear power plant to verify that the appropriate information was exchanged when
issues arose that could impact the offsite power system. The inspectors evaluated the
readiness of the offsite and alternative AC power systems by reviewing the licensees
procedures that address measures to monitor and maintain the availability and reliability
of the offsite and alternative AC power systems. The inspectors walked down one risk-
significant system/area listed below to verify compliance with the procedural
requirements and to verify that the specified actions provided the necessary protection
for the structures, systems, or components.
b. Findings
No findings were identified.
1R04 Equipment Alignment
Partial Walkdowns
a. Inspection Scope
The inspectors conducted four equipment alignment partial walkdowns, listed below, to
evaluate the operability of selected redundant trains or backup systems with the other
train or system inoperable or out of service. The inspectors reviewed the functional
systems descriptions, UFSAR, system operating procedures, and Technical
Specifications (TS) to determine correct system lineups for the current plant conditions.
The inspectors performed walkdowns of the systems to verify the operability of a
redundant or backup system/train or a remaining operable system/train with a high risk
significance for the current plant configuration (considering out-of-service, inoperable, or
degraded condition); or a risk-significant system/train that was recently realigned
following an extended system outage, maintenance, modification or testing; or a risk-
significant single-train system. The inspector conducted the reviews to ensure that
critical components were properly aligned, and to identify any discrepancies which could
affect operability of the redundant train or backup system.
Documents reviewed are listed in the Attachment.
- Unit 1, Quench spray system, train A
- Unit 2, Quench spray system, train B
- Unit 1, Recirculation spray system, train A
- Unit 2, Control room ventilation system
5
b. Findings
No findings were identified.
1R05 Fire Protection
Quarterly Fire Protection Walkdowns
a. Inspection Scope
The inspectors conducted focused tours of the four areas listed below that are important
to reactor safety to verify the licensees implementation of fire protection requirements as
described in fleet procedures CM-AA-FPA-100, Fire Protection/Appendix R (Fire Safe
Shutdown) Program, Rev. 10, CM-AA-FPA-101, Control of Combustible and
Flammable Materials, Rev. 8, and CM-AA-FPA-102, Fire Protection and Fire Safe
Shutdown Review and Preparation Process and Design Change Process, Rev. 5. The
inspectors evaluated, as appropriate, conditions related to: (1) licensee control of
transient combustibles and ignition sources; (2) the material condition, operational
status, and operational lineup of fire protection systems, equipment, and features; and,
(3) the fire barriers used to prevent fire damage or fire propagation. Documents
reviewed are listed in the Attachment.
- Units 1 and 2, Service water pumphouse
- Unit 2, Motor generator set house
- Units 1 and 2, Turbine building fire fighting strategy
- Unit 2, Containment
b. Findings
No findings were identified.
1R07 Heat Sink Performance
Triennial Review of Heat Sink Performance
a. Inspection Scope
The inspectors selected the Unit 2 B Component Cooling Heat Exchanger (2-CC-E-1B),
the Unit 2 D Recirculation Spray Heat Exchanger (2-RS-E-1D), and the Unit 1 A Control
Room Chiller (1-HV-E-4A-2) based on their risk-significance in the licensees
probabilistic safety analysis, and their importance to safety-related mitigating system
support functions.
For the two heat exchangers and a control room chiller, the inspectors reviewed the
licensees inspection, maintenance, and monitoring of biotic fouling and macrofouling
programs to ensure that they were adequate. The inspectors also reviewed the
licensees inspection and cleaning activities to determine if they had established
acceptance criteria consistent with industry standards, and the as-found results were
recorded, evaluated, and appropriately dispositioned to maintain structural integrity.
6
The inspectors reviewed the condition and operation of the Unit 2 B Component Cooling
Heat Exchanger, the Unit 2 D Recirculation Spray Heat Exchanger, and the Unit 1 A
Control Room Chiller to ensure they were consistent with design assumptions in heat
transfer calculations, as described in the final safety analysis report. This included
determining whether the number of plugged tubes was within pre-established limits
based on capacity and heat transfer assumptions for the Unit 2 B Component Cooling
Heat Exchanger, and the Unit 1 A Control Room Chiller. The inspectors also determined
that the licensee had established adequate controls and operational limits to prevent
heat exchanger degradation due to excessive flow-induced vibration during operation.
The inspectors determined whether the performance of ultimate heat sinks (UHS), and
their subcomponents such as piping, intake screens, pumps, valves, etc., was
appropriately evaluated by tests or other equivalent methods, to ensure availability and
accessibility to the in-plant cooling water systems.
The inspectors determined whether the licensees inspection of the UHS was thorough
and of sufficient detail to identify degradation of the impoundment protection, or loss of
structural integrity. This included determination of whether vegetation present along the
slopes was trimmed, maintained, and not adversely impacting the embankment. In
addition, the inspectors determined whether the licensee ensured sufficient reservoir
capacity by trending and removing debris in the UHS.
The inspectors reviewed the licensees inspection of the UHS to determine if it was
comprehensive and of significant depth to ensure sufficient reservoir capacity. This
included the review of licensees periodic monitoring and trending of sediment buildup
and heat transfer capability. In addition, the inspectors reviewed licensees periodic
performance monitoring of the UHS structural integrity, to determine whether adjacent
non-seismic or nonsafety-related structures could degrade, or block safety-related flow
paths, during a severe weather or seismic event. The inspectors also performed
walkdowns of accessible portions of the UHS supply and return piping to look for
possible settlement, or movement and piping conditions that would indicate loss of
structural integrity.
The inspectors performed a system walkdown of the service water intake structure to
determine whether the licensees assessment on structural integrity and component
functionality was adequate. In addition, the inspectors determined whether service
water pump bay silt accumulation was monitored, trended, and maintained at an
acceptable level by the licensee, and that water level instruments were functional and
routinely monitored. The inspectors also determined whether the licensees ability to
ensure functionality during adverse weather conditions was adequate.
The inspectors reviewed condition reports related to the heat exchangers/coolers and
heat sink performance issues to determine whether the licensee had an appropriate
threshold for identifying issues, and to evaluate the effectiveness of the corrective
actions.
These inspection activities constituted four heat sink inspection samples as defined in
IP 71111.07-05. Documents reviewed are listed in the Attachment.
7
b. Findings
No findings were identified.
1R08 Inservice Inspection Activities Unit 2 - Outage N2R25
a. Inspection Scope
Non-Destructive Examination Activities and Welding Activities: From September 18,
through September 22, 2017, the inspectors conducted an onsite review of the
implementation of the licensees inservice inspection (ISI) program for monitoring
degradation of the reactor coolant system, emergency feedwater systems, risk-
significant piping and components, and containment systems in Unit 2. The inspectors
activities included a review of non-destructive examinations (NDEs) to evaluate
compliance with the applicable edition of the American Society of Mechanical Engineers
(ASME) Boiler and Pressure Vessel Code (BPVC),Section XI (Code of Record: 2004
Edition with no Addenda; 4th Interval, 2nd Period, 3rd Outage), and to verify that
indications and defects (if present) were appropriately evaluated and dispositioned in
accordance with the requirements of the ASME Code,Section XI, acceptance
standards.
The inspectors directly observed the following NDEs mandated by the ASME Code to
evaluate compliance with the ASME Code Section XI and Section V requirements, and
if any indications and defects were detected, to evaluate if they were dispositioned in
accordance with the ASME Code, or an NRC-approved alternative requirement.
- UT of Component 12050-WMKS-0102B / 16-WFPD-423 / 40, Elbow to Nozzle
- UT of Component 12050-WMKS-0102A / 16-WFPD-424 / 75, Elbow to Nozzle
The inspectors observed some welding activities and reviewed the welding documents
for the activities referenced below in order to evaluate compliance with procedures and
the ASME Code. Specifically, the inspectors reviewed the respective work orders,
including the weld data sheets, welding procedures, procedure qualification records, and
welder performance qualification records for the referenced welds.
- 02-RC-154-VALVE, Replace Valve IAW DC NA-17-00008, ASME Class 1, reviewed
Work Order (WO) 59103055303
- 02-CH-MOV-2267B-VALVE, Replace Valve, ASME Class 2, reviewed
- 02-CC-328-VALVE and Piping, Remove/Reinstall Valve and Piping, ASME Class 3,
reviewed WO 59103105688 and observed some of the welding activities
During non-destructive surface and volumetric examinations performed since the
previous refueling outage, the licensee did not identify any relevant indications that were
analytically evaluated and accepted for continued service. Therefore, no NRC review
was completed for this inspection procedure attribute.
8
Pressurized Water Reactor Vessel Upper Head Penetration Inspection Activities: For
the Unit 2 vessel head, a bare metal visual examination was not required during this
outage pursuant to 10 CFR 50.55a(g)(6)(ii)(D) and ASME Code Case N-729-4 as it had
been performed during the previous outage (March 2016 during refueling outage
N2R24). The inspectors also noted that the licensee had requested, and the NRC had
approved, Relief Request N2-I4-NDE-002, which extended the Code Case N-729-1
Item B4.40 volumetric/surface examination schedule for the reactor vessel closure head
nozzles and partial penetration welds from a ten-year to a fifteen-year period because
the currently installed head is constructed of alloy 690/152/52 material. This material
has exhibited much higher resistance to crack growth rates than the material of the
original reactor vessel upper head, i.e., alloy 600/182/82 material. (The licensee
replaced the original head in January 2003 after identifying extensive cracking in the
attachment welds for reactor vessel head penetrations.) Note that the requirements for
Item B4.40 of Code Case N-729-1 did not change for Item B4.40 of Code Case N-729-4.
The Relief Request allows the licensee to postpone the volumetric and surface
examinations until spring 2022, during scheduled outage N2R28 in the fifth ten-year ISI
inspection interval. These examinations were last conducted in spring 2007 during
N2R18.
Boric Acid Corrosion Control Inspection Activities: The inspectors reviewed the
licensees boric acid corrosion control (BACC) program activities to ensure
implementation with commitments made in response to NRC Generic Letter 88-05,
Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary, and applicable
industry guidance documents. Specifically, the inspectors performed an onsite record
review of procedures and the results of the licensees containment walkdown inspections
performed during the current fall refueling outage (N2R25). The inspectors also
interviewed the BACC program owner, conducted an independent walkdown of
containment to evaluate compliance with licensees BACC program requirements, and
verified that degraded or non-conforming conditions such as boric acid leaks, were
properly identified and corrected, in accordance with the licensees BACC and corrective
action programs.
The inspectors reviewed the condition reports (CRs) and associated corrective actions
(CAs) listed in the Documents Reviewed Attachment related to boric acid leakage to
evaluate if the corrective actions completed were consistent with the requirements of the
ASME Code Section XI and 10 CFR Part 50, Appendix B, Criterion XVI.
Identification and Resolution of Problems: The inspectors performed a review of a
sample of ISI-related problems that were identified by the licensee and entered into the
corrective action program as CRs. The inspectors reviewed the CRs to confirm that the
licensee had appropriately described the scope of the problem, and had initiated
corrective actions. The review also included the licensees consideration and
assessment of operating experience events applicable to the plant. The inspectors
performed this review to ensure compliance with 10CFR Part 50, Appendix B,
Criterion XVI, Corrective Action, requirements. The corrective action documents
reviewed by the inspectors are listed in the report Attachment. Documents reviewed are
listed in the Attachment.
b. Findings
No findings were identified.
9
1R11 Licensed Operator Requalification Program and Licensed Operator Performance
.1 Resident Inspector Quarterly Review
a. Inspection Scope
The inspectors reviewed a licensed operator performance on August 3, 2017, during a
simulator scenario. The inspectors observed the following elements of crew
performance in terms of communications: (1) ability to take timely and proper actions;
(2) prioritizing, interpreting, and verifying alarms; (3) correct use and implementation of
procedures, including the alarm response procedures; (4) timely control board operation
and manipulation, including high-risk operator actions; and (5) oversight and direction
provided by the shift supervisor, including the ability to identify and implement
appropriate TS actions. Documents reviewed are listed in the Attachment.
b. Findings
No findings were identified.
.2 Quarterly Control Room Operator Performance Observations
a. Inspection Scope
During the inspection period, the inspectors conducted two observations of licensed
reactor operators actions and activities to ensure that the activities were consistent with
the licensee procedures and regulatory requirements. These observations took place
during both normal and off-normal plant working hours. As part of this assessment, the
inspectors observed the following elements of operator performance: (1) operator
compliance and use of plant procedures including technical specifications; (2) control
board/in-plant component manipulations; (3) use and interpretation of plant instruments,
indicators and alarms; (4) documentation of activities; (5) management and supervision
of activities; and (6) communication between crew members.
The inspectors observed and assessed licensed operator performance during the
following events:
- 2-OP-3.7, Unit Shutdown from Mode 1 to Mode 5 for Refueling
- Unit 1 during reset of U1 generator automatic voltage regulator to AUTO after
experiencing oscillations.
b. Findings
No findings were identified.
1R12 Maintenance Effectiveness
a. Inspection Scope
For the four equipment issues listed below, the inspectors evaluated the effectiveness of
the respective licensee's preventive and corrective maintenance. The inspectors
10
performed walkdowns of the accessible portions of the systems, performed in-office
reviews of procedures and evaluations, and held discussions with licensee staff. The
inspectors compared the licensees actions with the requirements of the Maintenance
Rule (10 CFR 50.65), and licensee procedure ER-AA-MRL-10, Maintenance Rule
Program, Rev. 6. Documents reviewed are listed in the Attachment.
- Fuel cooling pump, 1-FC-P-1B, motor in alert range for vibration
- Charging pump, 1-CH-P-1A, in alert range of vibration
- 1-VG-RM-180, Gaseous Effluent Monitor Out of Service
- 1-SA-P-1A, 1A service air pump trip
b. Findings
No findings were identified.
1R13 Maintenance Risk Assessments and Emergent Work Control
a. Inspection Scope
The inspectors evaluated, as appropriate, the four activities listed below for the following:
(1) effectiveness of the risk assessments performed before maintenance activities were
conducted; (2) management of risk; (3) appropriate and necessary steps taken to plan
and control the resulting emergent work activities upon identification of an unforeseen
situation; and (4) adequate identification and resolution of maintenance risk
assessments and emergent work problems. The inspectors reviewed these
maintenance activities to verify that the licensee was in compliance with the
requirements of 10 CFR 50.65 (a)(4) and the data output from the licensees safety
monitor associated with the risk profile of Units 1 and 2. The inspectors reviewed the
corrective action program to verify that deficiencies in risk assessments were being
identified and properly resolved. Documents reviewed are listed in the Attachment.
- Motor replacement of 1-FC-P-1B due to high vibration
- 2B slave relay PT, 2-PT-213.2A
- Appendix R Alternate Shutdown/Maintenance Rule (a)(4) Fire Risk Equipment
(Technical Response Manual 7.5 for charging crosstie U1/U2)
- U2 overpressure protection, 2-PT-44.4.1
b. Findings
No findings were identified.
1R15 Operability Determinations and Functionality Assessments
Operability and Functionality Review
a. Inspection Scope
The inspectors reviewed five operability determinations (OD) and functionality
assessments, listed below, affecting risk-significant mitigating systems, to assess, as
appropriate: (1) the technical adequacy of the evaluations; (2) whether continued
11
system operability was warranted; (3) whether other existing degraded conditions were
considered as compensatory measures; (4) whether the compensatory measures, if
involved, were in place, would work as intended, and were appropriately controlled; and
(5) where continued operability was considered unjustified, the impact on TS Limiting
Conditions for Operation and the risk significance in accordance with the SDP. No
samples of operator work arounds (OWA) were reviewed because there were no OWAs
existing for either unit during the calendar year 2016. The inspectors review included a
verification that ODs were made as specified by procedure OP-AA-102, Operability
Determination, Rev. 13. Documents reviewed are listed in the Attachment.
- Operability Determination, CA3063143, Degraded Non-Conforming Condition of SW
Traveling Screens due to Electrical Design Inadequacy Identified in CR 1074806
- CA286656, 1-CC-P-1B Oil Sample has Visible Ferrous Particles
- Feedwater ultrasonic flow meter
- 1-CH-P-1A operability in alert vibrations
- Increased reactor coolant system leakage from U1 reactor coolant pump
b. Findings
No findings were identified.
1R19 Post Maintenance Testing
a. Inspection Scope
The inspectors reviewed five post-maintenance test procedures and/or test activities,
listed below, for selected risk-significant mitigating systems to assess whether: (1) the
effect of testing on the plant had been adequately addressed by control room and/or
engineering personnel; (2) testing was adequate for the maintenance performed; (3)
acceptance criteria were clear and adequately demonstrated operational readiness
consistent with design and licensing basis documents; (4) test instrumentation had
current calibrations, range, and accuracy consistent with the application; (5) tests were
performed as written with applicable prerequisites satisfied; (6) jumpers installed or
leads lifted were properly controlled; (7) test equipment was removed following testing;
and (8) equipment was returned to the status required to perform in accordance with
VPAP-2003, Post Maintenance Testing Program, Rev. 14. Documents reviewed are
listed in the Attachment.
- Main Control Room Chiller 4B
- Fire Protection Pumps - Annual Testing for 1-FP-P-2, Diesel-Driven Fire Pump, after
maintenance
- SR102 Shunt Breaker Spare replacement and oil leak repair
- 2-RS-MR02 casing cooler chiller failure and repair
- 1-RM-CNUT-193, N-16 signal converter replacement
b. Findings
No findings were identified.
12
1R22 Surveillance Testing
a. Inspection Scope
For the six surveillance tests listed below, the inspectors examined the test procedures,
witnessed testing, or reviewed test records and data packages, to determine whether the
scope of testing adequately demonstrated that the affected equipment was functional
and operable, and that the surveillance requirements of TS were met. The inspectors
also determined whether the testing effectively demonstrated that the systems or
components were operationally ready and capable of performing their intended safety
functions. Documents reviewed are listed in the Attachment.
IST Pump or Valve Test:
- 1-PT-71.3Q, 1-FW-P-3B, B Motor-Driven AFW Pump and Valve Test, Revision 53
RCS Leakage:
- 1-GOP-52.2A, Identifying Increased RCS Leakage, Rev 01
Containment Isolation Valve:
- 2-PT-57.5A, Leak Rate Test of 2-SI-P-1A and Associated Piping and Inservice
Inspection for 2-SI-6, Rev 21
- 2-PT-57.5B, Leak Rate Test of 2-SI-P-1B and Associated Piping and Inservice
Inspection for 2-SI-29, Rev 21
Other Surveillance Tests:
- 2-PT-17.1, Control Rod Operability, Revision 41
- 2-PT-83.12H, 2H Diesel Generator Test (Start by ESF Actuation) Followed by 24-
hour Run and Hot Restart Test, Revision 29
b. Findings
No findings were identified.
2. RADIATION SAFETY (RS)
2RS1 Radiological Hazard Assessment and Exposure Controls (Seven Inspection Samples
Completed)
a. Inspection Scope
Hazard Assessment and Instructions to Workers: During facility tours, the inspectors
directly observed radiological postings and container labeling for areas established
within the radiologically controlled area (RCA) of the Unit 2 (U2) Reactor Building, Unit 1
(U1) and U2 Auxiliary Buildings, and radioactive waste (radwaste) processing and
storage locations. The inspectors independently measured radiation dose rates or
directly observed conduct of licensee radiation surveys for selected RCA areas. The
13
inspectors reviewed survey records for several plant areas including surveys for airborne
radioactivity, gamma surveys with a range of dose rate gradients, surveys for alpha-
emitters and other hard-to-detect radionuclides, and pre-job surveys for upcoming tasks.
The inspectors also discussed changes to plant operations that could contribute to
changing radiological conditions since the last inspection. The inspectors attended pre-
job briefings and reviewed Radiation Work Permit (RWP) details to assess
communication of radiological control requirements and current radiological conditions to
workers.
Control of Radioactive Material: The inspectors observed surveys of material and
personnel being released from the RCA using small article monitor, personnel
contamination monitor, and portal monitor instruments. The inspectors discussed
equipment sensitivity, alarm setpoints, and release program guidance with licensee staff.
The inspectors also reviewed records of leak tests on selected sealed sources and
discussed nationally tracked source transactions with licensee staff.
Hazard Control: The inspectors evaluated access controls and barrier effectiveness for
selected High Radiation Area (HRA), Locked High Radiation Area (LHRA), and Very
High Radiation Area (VHRA) locations and discussed changes to procedural guidance
for LHRA and VHRA controls with Radiation Protection (RP) supervisors. The
inspectors reviewed implementation of controls for the storage of irradiated material
within the spent fuel pool. Established radiological controls, including airborne controls
and electronic dosimeter (ED) alarm setpoints, were evaluated for selected U2 Refueling
Outage 25 (2R25) tasks including lncore Flux Thimble modifications, Reactor Vessel
Head disassembly/assembly, and Valve Maintenance. In addition, the inspectors
reviewed licensee controls for areas where dose rates could change significantly as a
result of plant shutdown and refueling operations. The inspectors also reviewed the use
of personnel dosimetry including extremity dosimetry and multi-badging in high dose rate
gradients.
Radiation Worker Performance and RP Technician Proficiency: Occupational workers
adherence to selected RWPs and RP technician proficiency in providing job coverage
were evaluated through direct observations and interviews with licensee staff. Jobs
observed included incore flux thimble cutting, refueling, and various outage maintenance
tasks in high radiation and contaminated areas. The inspectors also evaluated worker
responses to dose and dose rate alarms during selected work activities.
Problem Identification and Resolution: The inspectors reviewed and assessed
Corrective Action Program (CAP) documents associated with radiological hazard
assessment and control. The inspectors evaluated the licensees ability to identify and
resolve the issues in accordance with licensee procedures. The inspectors also
reviewed recent self-assessment results.
Inspection Criteria: Radiation protection activities were evaluated against the
requirements of Updated Final Safety Analysis Report (UFSAR) U2 Chapters 11 and 12,
TS Section 5.7, 10 CFR Parts 19 and 20, and approved licensee procedures. Licensee
programs for monitoring materials and personnel released from the RCA were evaluated
against 10 CFR Part 20 and IE Circular 81-07, Control of Radioactively Contaminated
Material. Documents reviewed are listed in the Attachment..
14
b. Findings
No findings were identified.
2RS6 Radioactive Gaseous and Liquid Effluent Treatment (Six Inspection Samples
Completed)
a. Inspection Scope:
Radioactive Effluent Treatment Systems: The inspectors walked-down selected
components of the gaseous and liquid radioactive waste (radwaste) processing and
effluent discharge systems. To the extent practical, the inspectors observed and
evaluated the material condition of in-place waste processing equipment for indications
of degradation or leakage that could constitute a possible release pathway to the
environment. Inspected components included radwaste processing equipment in the
clarifier building, turbine building, auxiliary building and associated piping and valves.
The inspectors interviewed licensee staff regarding equipment configuration and effluent
monitor operation. The inspectors also walked down and reviewed surveillance test
records for the A and B trains of the Emergency Core Cooling System Pump Room
Exhaust Air Cleanup System (ECCS PREACS) ventilation system filters.
Effluent Sampling and Discharge: The inspectors observed the collection and
processing of liquid effluent samples from high capacity steam generator blowdown
proportional tanks in the turbine building and from the clarifier proportional tanks in the
waste disposal building and observed gaseous effluent sampling on the 291 elevation of
the auxiliary building. Technician proficiency in collecting, processing, and preparing the
applicable release permits was evaluated. The inspectors reviewed recent liquid and
gaseous release permits including pre-release sampling results, effluent monitor alarm
setpoints, and public dose calculations. For RM-111 (Clarifier Hold-Up Tank Outlet
Liquid Effluent Monitor), RM-187 (Process Vent Gaseous Effluent Monitor), RM-188
(Plant Vent A Gaseous Effluent Monitor) and RM-121 (U1 Condensate Air Ejector
Gaseous Effluent Monitor), the inspectors reviewed calibration and functional test
records and evaluated traceability of radioactive calibration sources to National Institute
of Standards and Technology (NIST) standards. The inspectors also evaluated the
licensees capability to collect high-range post-accident effluent samples from these
monitoring systems if applicable. The inspectors reviewed and discussed with licensee
staff methodology for determining vent and stack flow rates and compared current vent
flows to design values in the Offsite Dose Calculation Manual (ODCM).
The inspectors reviewed the 2015 and 2016 Annual Radioactive Effluent Release
Reports to evaluate reported doses to the public, review any anomalous events, and to
review ODCM changes. The inspectors reviewed compensatory sampling data for time
periods when selected radiation monitors were out of service. The inspectors reviewed
the results of interlaboratory cross-checks for laboratory instruments used to analyze
effluent samples. The inspectors also reviewed licensee effluent source term
characterizations and changes to effluent release points. In addition, the inspectors
evaluated recent land use census results.
15
Problem Identification and Resolution: The inspectors reviewed and discussed selected
CAP documents associated with gaseous and liquid effluent processing and release
activities including licensee sponsored assessments. The inspectors evaluated the
licensees ability to identify and resolve issues.
Inspection Criteria: Radwaste system operation and effluent processing activities were
evaluated against requirements and guidance documented in the following: 10 CFR Part
20; 10 CFR Part 50 Appendix I; ODCM; UFSAR Chapters 9 and 11; Regulatory Guide
(RG) 1.21, Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and
Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-
Cooled Nuclear Power Plants; RG 1.109, Calculation of Annual Doses to Man from
Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10
CFR Part 50 Appendix I; and TS Section 5, Administrative Requirements Documents
reviewed are listed in the Attachment.
b. Findings
No findings were identified.
2RS7 Radiological Environmental Monitoring Program (REMP) (Three Inspection Samples
Completed)
a. Inspection Scope
REMP Implementation: The inspectors reviewed the (2015 and 2016) Annual
Radiological Environmental Operating Reports and the (2015 and 2016) Annual
Radioactive Effluent Release Reports. Selected environmental measurements were
reviewed for consistency with licensee effluent data, evaluated for radionuclide
concentration trends, and compared with detection level sensitivity requirements as
described in the ODCM. The inspectors assessed the licensees response to any
missed or anomalous environmental samples. The inspectors also reviewed the results
of interlaboratory cross-checks for laboratory instruments used to analyze environmental
samples. Any changes to the ODCM, Land Use Census, or environmental program
processes were discussed with licensee staff.
The inspectors observed routine collection of airborne particulate and iodine air samples
and verified placement of environmental dosimeters and surface water sampling
equipment at selected locations as required by the licensees ODCM. The inspectors
noted the material condition of the continuous air samplers, water samplers, and
environmental dosimeters. The inspectors also reviewed calibration and maintenance
records for the selected the environmental sampling equipment.
Meteorological Monitoring Program: The inspectors observed the physical condition of
the meteorological tower and its instrumentation and discussed equipment operability
and maintenance history with licensee staff. The inspectors evaluated transmission of
locally generated meteorological data to other licensee groups such as emergency
operations personnel and main control room operators. Calibration records for the
meteorological measurements of wind speed, wind direction, and temperature were
reviewed. The inspectors also reviewed meteorological measurement data recovery for
2015 and 2016.
16
Ground Water Protection: The inspectors reviewed the licensees continued
implementation of the industrys Ground Water Protection Initiative (Nuclear Energy
Institute (NEI) 07-07) and discussed any changes to the program. The inspectors
discussed program guidance for dealing with spills, leaks, and unexpected discharges
with licensee staff and reviewed recent monitoring well results and any voluntary
communications. The inspectors also reviewed recent entries into the 10 CFR 50.75(g)
decommissioning file. The inspectors reviewed and discussed the licensees program
for monitoring of structures, systems, and components with the potential to release
radioactive material to the environment. Potential effluent release points due to onsite
surface water bodies were also evaluated.
Problem Identification and Resolution: The inspectors reviewed CAP documents in the
areas of radiological environmental monitoring and meteorological tower maintenance.
The inspectors evaluated the licensees ability to identify and resolve the issues. The
inspectors also reviewed recent self-assessment results.
Inspection Criteria: The inspectors evaluated REMP implementation and meteorological
monitoring against the requirements and guidance contained in: 10 CFR Part 20;
Appendices E and I to 10 CFR Part 50; TS Section 5.0; Offsite Dose Calculation Manual
(North Anna); UFSAR Chapter 11; RG 4.15, Quality Assurance for Radiological
Monitoring Programs (Normal Operation) - Effluent Streams and the Environment;
Branch Technical Position, An Acceptable Radiological Environmental Monitoring
Program - 1979; Safety Guide 23 Onsite Meteorological Programs; NEI 07-07,
Industry Groundwater Protection Initiative - Final Guidance Document; and approved
licensee procedures Documents reviewed are listed in the Attachment.
b. Findings
No findings were identified.
2RS8 Radiological Radioactive Solid Waste Processing and Radioactive Material Handling,
Storage, and Transportation (Six Inspection Samples Completed)
a. Inspection Scope
Radioactive Material: The inspectors walked down indoor and outdoor areas inside the
protected area as well as radioactive material storage warehouses and the steam
generator storage facility outside of the protected area (PA). During the walk-downs, the
inspectors observed the physical condition and labeling of storage containers and the
radiological postings for satellite radioactive material storage areas. The inspectors also
reviewed the licensees radwaste procedures for routine surveys and waste storage.
Radioactive Waste System Walkdown, Characterization and Classification: The
inspectors walked down accessible sections of the liquid and solid radwaste systems to
assess material condition and conformance of equipment with system design diagrams.
This included portions of the radwaste processing building. The inspectors discussed
the function of radwaste components with the radwaste operator. The inspectors
discussed possible changes to the radwaste processing systems with radwaste staff.
The processes for the dewatering of resins, spent resin tank recirculation, resin
sampling, and transfer of resins from the processing pads to the shipping casks and
temporary storage casks were reviewed and discussed with resin processing contractor.
17
The inspectors reviewed the 2016 Radioactive Effluent Release Report and the most
recent radionuclide characterization and classification for the dry active waste and
primary resin waste streams. The inspectors evaluated analyses for hard-to-detect
nuclides, reviewed the use of scaling factors, and examined quality assurance
comparison results between licensee waste stream characterizations and outside
laboratory data. The inspectors also evaluated how changes to plant operational
parameters were taken into account in waste characterization.
Shipment Preparation and Records: There were no outgoing radioactive material
shipments available for observation during the week of the inspection. The inspectors
observed the radiological survey of an incoming limited quantity shipment. The
inspectors reviewed four shipping records for consistency with licensee procedures and
compliance with NRC and Department of Transportation regulations. This included
review of emergency response information, waste classification, radiation survey results,
information on the waste manifest, and the authorization of the receiving licensee to
receive shipments. Training records for selected individuals currently qualified to ship
radioactive material were reviewed for compliance with 49 CFR Part 172 Subpart H.
Problem Identification and Resolution: The inspectors reviewed CAP documents in the
areas of radwaste/shipping. The inspectors evaluated the licensees ability to identify
and resolve the issues. The inspectors also reviewed recent self-assessment results.
Inspection Criteria: Radioactive material and waste storage activities were reviewed
against the requirements of 10 CFR Part 20. Radwaste processing activities and
equipment configuration were reviewed for compliance with the licensees Process
Control Program. Waste stream characterization analyses were reviewed against
regulations detailed in 10 CFR Part 20, 10 CFR Part 61, and guidance provided in the
Branch Technical Position on Waste Classification (1983). Transportation program
implementation was reviewed against regulations detailed in 10 CFR Part 20, 10 CFR
Part 71 (which requires licensees to comply with Department of Transportation
regulations in 49 CFR Parts 107, 171-180, and 390-397), as well as the guidance
provided in NUREG-1608. Training activities were assessed against 49 CFR Part 172
Subpart H. Documents reviewed are listed in the Attachment.
b. Findings
No findings were identified.
4. OTHER ACTIVITIES
4OA1 Performance Indicator (PI) Verification (Four Inspection Samples Completed)
.1 Reactor Safety
a. Inspection Scope
The inspectors reviewed a sample of the performance indicator (PI) data, submitted by
the licensee, for the Unit 1 and Unit 2 PIs listed below. The inspectors reviewed plant
records compiled between June 2016 to June 2017 to verify the accuracy and
completeness of the data reported for the station. The inspectors verified that the PI
data complied with guidance contained in Nuclear Energy Institute 99-02, Regulatory
18
Assessment Performance Indicator Guideline, and licensee procedures. The inspectors
verified the accuracy of reported data that were used to calculate the value of each PI.
In addition, the inspectors reviewed a sample of related corrective action documents to
verify the licensee was identifying and correcting any deficiencies associated with PI
data. Documents reviewed are listed in the attachment.
Cornerstone: Mitigating Systems
- safety system functional failure (MS05)
Cornerstone: Barrier Integrity
- reactor coolant system specific activity (BI01)
b. Findings
No findings were identified.
.2 Radiation Safety
a. Inspection Scope
Occupational Radiation Safety Cornerstone: (OR01) The inspectors reviewed the
Occupational Exposure Control Effectiveness PI results for the Occupational Radiation
Safety Cornerstone from April 2016 through July 2017. For the assessment period, the
inspectors reviewed ED alarm logs and CAP documents related to controls for exposure
significant areas. Documents reviewed are listed in the Attachment.
Public Radiation Safety Cornerstone: (PR01) The inspectors reviewed the Radiological
Control Effluent Release Occurrences PI results for the Public Radiation Safety
Cornerstone from April 2016 through July 2017. For the assessment period, the
inspectors reviewed cumulative and projected doses to the public contained in liquid and
gaseous release permits and CAP documents related to Radiological Effluent Technical
Specifications/ODCM issues. The inspectors also reviewed licensee procedural
guidance for collecting and documenting PI data. Documents reviewed are listed in the
Attachment.
b. Findings
No findings were identified.
4OA2 Problem Identification and Resolution
.1 Review of Items Entered into the Corrective Action Program
a. Inspection Scope
As required by NRC Inspection Procedure 71152, Identification and Resolution of
Problems, and in order to help identify repetitive equipment failures or specific human
performance issues for follow-up, the inspectors performed a daily screening of items
19
entered into the licensees CAP. This review was accomplished by reviewing daily CR
report summaries and periodically attending daily CR Review Team meetings.
b. Findings and Observations
No findings were identified.
.2 Semiannual Trend Review: Procedural Adherence
a. Inspection Scope
The inspectors performed a review regarding the licensees procedural adequacy. The
inspectors, through document review and interviews with licensee, reviewed the
establishment and effectiveness of a licensee program in addressing procedural
adequacy in operations and maintenance activities.
b. Findings and Observations
No findings were identified.
4OA6 Meetings, Including Exit
On October 18, 2017, the resident inspectors presented the quarterly inspection results
to Mr. L. Lane and other members of the staff. The licensee acknowledged the results of
these inspections. The inspectors verified no proprietary information was retained by the
inspectors or documented in this report.
4OA7 Licensee-Identified Violations
The following violation of very low safety significance (Green) was identified by the
licensee and is a violation of NRC requirements which meet the criteria of the NRC
Enforcement Policy, for being dispositioned as a Non-Cited Violation.
TS 5.4.1 requires, that Written procedures shall be established, implemented, and
maintained covering the following activities: a. The applicable procedures
recommended in Regulatory Guide 1.33, Revision 2, Appendix A,
February 1978. Regulatory Guide (RG) 1.33, Appendix A, identifies Access control to
radiation areas, including a Radiation Work Permit (RWP) system as one of the areas
requiring procedural controls. Additionally, procedure VPAP-2101, Radiation Protection
Program, Revision 35, Attachment 1, RCA Work Practices, identifies what workers
should know prior to entering the RCA (minimum requirements). Attachment 1 states, in
part, All workers entering the RCA are required to: 1) Notify RP prior to entering the
RCA. Contrary to the above requirements, on September 15, 2017, two maintenance
workers entered U2 Containment, a posted High Radiation Area (HRA), while signed in
on an incorrect RWP, and without checking in at the Health Physics Shift Supervisor
window prior to entering containment. The workers signed in on the RWP they had used
earlier in the day which did not allow entry into a HRA. The containment building had
been posted as a HRA in preparation for lifting the reactor head while the workers were
out of containment. HP personnel in the remote monitoring facility identified that the
individuals were on an incorrect RWP, informed HP personnel in containment, and the
workers exited containment prior to the head lift. This finding was of very low safety
20
significance (Green) because there was no substantial potential for overexposure and
the licensees ability to assess dose was not compromised. The immediate corrective
actions were documented in CR 1078223. Corrective actions included a human
performance review, coaching of the individuals by RP Management, and distribution of
a site-wide message discussing the incident and reminding site personnel to remain
aware of radiological safety.
ATTACHMENT: SUPPLEMENTAL INFORMATION
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel:
M. Becker, Manager, Nuclear Outage and Planning
R. Galbraith, ISI/NDE Supervisor
A. Garcia-Santiago, Auxiliary System Programs Engineer II
J. Jenkins, Manager, Nuclear Site Services
R. Hanson, Manager, Nuclear Protection Services
E. Hendrixson, Director, Nuclear Site Engineering
L. Hilbert, Plant Manager
J. Jenkins, Manager, Nuclear Maintenance
L. Lane, Site Vice President
K. LeBarron, Nuclear Technical Specialist III
J. Leberstien, Technical Advisor, Licensing
D. McGinnis, Technical Specialist II
R. Page, Licensing Engineer
J. Plossl, Supervisor, Nuclear Station Procedures
J. Schleser, Manager, Nuclear Organizational Effectiveness
R. Simmons, Manager, Radiation Protection and Chemistry
J. Slattery, Manager, Nuclear Operations
W. Standley, Director, Nuclear Station Safety & Licensing
D. Taylor, Manager, Station Licensing
B. Thompson, Manager, Nuclear Training
B.J Thompson, Superintendent, Radiation Protection Technical Services
M. Whalen, Technical Advisor, Licensing
J. Collins - Corporate Director, Emergency Preparedness (EP)
B. Miller - EP Specialist
D. Plogger - EP Specialist
T. Shalaski - EP Specialist
N. Turner, EP Manager
LIST OF ITEMS OPENED, CLOSED AND DISCUSSED
Opened and Closed
None
Attachment
LIST OF DOCUMENTS REVIEWED
Section 1R04: Equipment Alignment
Procedures, Guidance Documents, and Manuals
1-OP-7.4A, Valve Checkoff - Quench Spray System, Revision 10.
CR1041263 BACC 1-QS-P-1A at shaft seal
Section 1R05: Fire Protection
Procedures, Guidance Documents, and Manuals
2-FS-C-1, Loss Prevention Fire Strategy, Containment - Unit 2, Revision 4
2-PT-105.4.1, Loss Prevention Periodic Test, Fire Protection - Hose Station Flow Test,
Revision 3
1-FS-SW-1, Loss Prevention Fire Strategy, Service Water Pump House Units 1 and 2,
Revision 2
0-PT-105.3, Loss Prevention Periodic Test, Hose House Inspection, Revision 5
CM-AA-FPA-100, Fire Protection/Appendix R (Fire Safe Shutdown) Program, Revision 13
0-PT-105.1.1, Loss Prevention Period Test, Fire Door Inspection - Turbine Building, Control
Room, and Office Area, Revision 10
0-FS-TB-1, Loss Prevention Fire Strategy, Turbine Building Fire Fighting Strategy, Revision 2
2-FS-MG-1, Firefighting Strategy, Motor Generator Set House Unit 2, Dated May 28, 1992
Section 1R07: Heat Sink Performance
Procedures
0-AP-12, Abnormal Procedure, Loss of Service Water, Revision 40
0-EPM-2303-01, Inspection of Service Water Cathodic Protection System, Revision 12
0-EPM-2303-02, Corrosion Survey of Service Water Cathodic Protection System, Revision 0
0-OP-49.1, Operating Procedure, Service Water System Normal Operation, Revision 20
0-OP-49.6, Operating Procedure, Service Water System Throttling Alignment, Revision 24
0-PT-75.7, Engineering Periodic Test, Service Water Reservoir - Ground Water Level,
Revision 7
0-PT-75.8, Engineering Periodic Test, Service Water Reservoir Loss Monitoring Procedure,
Revision 5
0-PT-75.24A, Service Water MIC Leakage Inspection - Units 1 and 2, Revision 9
0-PT-75.12, Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike
and Toe, Revision 7
0-PT-75.15, Engineering Periodic Test, Generic Letter 89-13 Service Water System Testing
Requirements Coordination, Revision 6
0-PT-75.22, Engineering Periodic Test, Service Water System Reservoir Sludge Depth
Measurement, Revision 7
0-PT-115, Engineering Periodic Test, Survey of Settlement Monitoring Points, Revision 13
1-PT-75.6, Engineering Periodic Test, Service Water System Flow Balance, Revision 24-MR1
2-PT-75.6, Engineering Periodic Test, Service Water System Flow Balance, Revision 23
ER-AA-AMP-101, Implementation of Activities Performed by License Renewal Aging
Management Coordinators, Revision 7
ER-AA-BPM-10, Underground Piping and Tank Integrity Program Description, Revision 7
ER-AA-BPM-101, Underground Piping and Tank Integrity Program, Revision 10
ER-AA-HTX-10, Heat Exchanger Program, Revision 6
3
ER-NA-INS-101, Main Dam Annual Inspection, Revision 2
ER-NA-SYS-320, Generic Letter 89-13 Program, Revision 2
CH-32.939, Service Water Chemical Addition System: Operation, Revision 14
CH-32.940, Service Water System: Aqua Shade Addition, Revision 2
CHAP-0105, Auxiliary Cooling Water System Chemistry Control Program (North Anna),
Revision 26
VPAP-0811, Service Water System Inspection and Maintenance Program, Revision 6
Corrective Action Documents
CR 0580154, Service Water flow indication on 'B' supply header is indicating high
CR 1010758, Extension shaft material for SW Spray Array MOVs (and Bypass MOVs) do not
support torque requirement
CR 1010761, Unable to confirm material removed from the "B" SW header
CR 1010918, Through-Wall Leak in the 1B2 Spray Array Piping
CR 1010927, Through-Wall Leak identified on the 2A2 Spray Array
CR 1010934, 2A2 SW spray array surging
CR 1010936, 2-SW-MOV-222A Internal Inspection Findings
CR 1011052, Mop head fibers lodged in 2" continuous drains
CR 1050193, 2-SW-354 has a MIC leak at the pipe weld
CR 1071375, Weld Repairs identified on 10 Tee off of 24-WS-102-151-Q3
Work Orders (WOs)
WO 59102243628, Control Room Chiller Equipment Performance Test (1-HV-E-4A)
WO 59102493734, Inspection and Cleaning of 01-HV-E-4A-2-HTEXCH
WO 59102498132, CC Heat Exchanger Tube Cleaning/Plugging 02-CC-E-1B HTEXCH
WO 59102888926, Annual Corrosion Survey of Service Water Cathodic Protection System per
0-EPM-2303-02
WO 59102999245, Eddy Current Testing of 01-RS-E-1B-HTEXCH
WO 59102999267, Perform Eddy Current Testing I As-Found Tubesheet Inspection of
01-RS-E-1 D-HTEXCH
Other Documents Reviewed
Main Dam Annual Inspection using ER-NA-INS-101, dated 10/16/14
Main Dam Annual Inspection using ER-NA-INS-101, dated 8/19/15
Main Dam Annual Inspection using ER-NA-INS-101, dated 11/3/16
Calculation 07797-US(B)-280, Containment Recirculation Heat Exchanger UAs, dated 5-3-00
Calculation ME-0530, Component Cooling Heat Exchanger Tube Plugging, dated 2/10/97
Calculation ME-0932, Evaporator and Condenser Tube Plugging Evaluation for the Main
Control Room Chillers and Front Office Chillers, dated 10/16/12
Design Change NA-15-00106, Removal of Weko Pipe Seals in the A Service Water Return
Header (36-WS-4-151-Q3)
Design Change NA-16-00058 Removal of Weko Pipe Seals in the B Service Water Supply
Header (36-WS-2-151-Q3)
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7,
dated 11/25/14
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7,
dated 6/10/15
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7,
dated 1/6/16
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7,
dated 6/20/16
4
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7,
dated 1/10/17
Engineering Periodic Test, Service Water Reservoir-Ground Water Level using 0-PT-75.7,
dated 6/15/17
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated
1/28/15
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated
7/30/15
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated
2/4/16
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated
8/9/16
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated
1/25/17
Engineering Periodic Test, Service Water Reservoir Loss Monitoring using 0-PT-75.8, dated
6/19/17
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe
using 0-PT-75.12, dated 11/26/14
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe
using 0-PT-75.12, dated 5/6/15
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe
using 0-PT-75.12, dated 12/7/15
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe
using 0-PT-75.12, dated 6/16/16
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe
using 0-PT-75.12, dated 12/5/16
Engineering Periodic Test, Visual Inspection of the Service Water Reservoir Dike Crest and Toe
using 0-PT-75.12, dated 5/31/17
Engineering Periodic Test of Generic Letter 89-13 Service Water System Testing Requirements
Coordination using 0-PT-75.15, dated 8/31/15
Engineering Periodic Test of Generic Letter 89-13 Service Water System Testing Requirements
Coordination using 0-PT-75.15, dated 8/12/16
Engineering Periodic Test, Service Water System Sludge Depth Measurement using
0-PT-75.22, dated 12/6/16
Engineering Periodic Test of Generic Letter 89-13 Service Water System Components using
0-PT-75.15, dated 8/31/15
Engineering Periodic Test of Generic Letter 89-13 Service Water System Components using
0-PT-75.15, dated 8/12/16
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated
10/2/14
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated
3/27/15
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated
9/30/15
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated
3/31/16
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated
10/2/16
Engineering Periodic Test, Survey of Settlement Monitoring Points using 0-PT-115, dated
3/21/17
Engineering Periodic Test, Service Water System Flow Balance using 1-PT-75.6, dated 3/13/15
5
Engineering Periodic Test, Service Water System Flow Balance using 1-PT-75.6, dated
10/11/16
Engineering Periodic Test, Service Water System Flow Balance using 2-PT-75.6, dated 9/24/14
Engineering Periodic Test, Service Water System Flow Balance using 2-PT-75.6, dated 4/6/16
Engineering Technical Evaluation ETE-NA-2012-0064, Life Cycle Management Plan -
Underground Piping and Tank Integrity Program - North Anna Power Station, Revision 4
EPRI TR-108009, Balance of Plant Heat Exchanger Condition Assessment and Inspection
Guide, December 1999
EPRI TR-110392, Eddy Current Testing of Service Water Heat Exchangers for Engineers
Guideline, February 1999
Federal Energy Regulatory Commission (FERC) Dam Safety Inspection Report on the Service
Water Reservoir Dam, submitted on May 24, 2016
Plant Health Issues List (PHIL) 3171, Obsolescence: SW System Component Obsolete (SW
Travelling Screens)
SDBD-NAPS-SW, System Design Basis Document for Service Water System - North Anna
Power Station, Revision 19
Service Water System Health Report for 3rd Quarter 2014
Service Water System Health Report for 4th Quarter 2014
Service Water System Health Report for 1st Quarter 2015
Service Water System Health Report for 2nd Quarter 2015
Service Water System Health Report for 3rd Quarter 2015
Service Water System Health Report for 4th Quarter 2015
Service Water System Health Report for 1st Quarter 2016
Service Water System Health Report for 4th Quarter 2016
Service Water System Health Report for 1st Half 2017
Technical Report LR-2754, Service Water System Inspections, North Anna Power Station
Unit 1 PT of isolation capabilities for interface valves between SW and non-safety-related or
non-seismic piping using Operations Periodic Test Procedure 1-PT-57.4, dated 9/30/16
Unit 2 PT of isolation capabilities for interface valves between SW and non-safety-related or
non-seismic piping using Operations Periodic Test Procedure 2-PT-57.4, dated 3/31/16
Updated Final Safety Analysis Report (FSAR) Section 9.2.1, Service Water System
Water Hammer Analysis from the Service Water System Operational Performance Assessment,
July 11 - July 29, 1994 (CNS Report No. 94-03- NAPS-A)
Section 1R08: Inservice Inspection Activities
Procedures
ER-AA-NDE-PT-301, ASME Section XI Liquid Penetrant Examination Procedure, Revision 7
ER-AA-NDE-PT-301, Balance of Plant (BOP) Liquid Penetrant Examination Procedure,
Revision 7
ER-AA-NDE-UT-801, Ultrasonic Examination of Ferritic Piping Welds in Accordance with ASME
Section XI, Appendix VIII, Revision 7
ER-AP-BAC-10, Boric Acid Corrosion Control Program, Revision 12
ER-AP-BAC-101, Boric Acid Corrosion Control Program (BACCP) Inspections, Revision 12
ER-AP-BAC-102, Boric Acid Corrosion Control Program (BACCP) Evaluations, Revision 13
Corrective Action Documents
CR 1044128, Manifold at 2-CH-MAN-2147 has moist boric acid leak
CR 1044134, Excessive boric acid leak found on 2-CH-249
CR 1050623, BACC packing leak on 2-SI-MOV-2867C excessive and discolored
CR 1050625, BACC actively leaking on 2-CH-250
6
CR 1054222, Excessive wet boric acid on 2-SI-RV-2857 Leak-Off Line
CR 1055826, Excessive boric acid deposit on 2-CH-240
CR 1055829, Discolored boric acid deposit on 2-SI-MOV-2867D
CR 1060028, Excessive dry boric acid from packing on 1-CH-316
CR 1063045, Manifold at 2-CH-MAN-2147 has moist boric acid leak
CR 1064466, Excessive, discolored boric acid on 2-SI-83
CR 1064483, Moist, discolored boric acid on 2-CH-MOV-2287A
CR 1077711, Excessive boric acid leakage at 2-RC-48 packing
CR 1077834, Excessive boric acid found on various components
CR 1077970, 2-CH-ICV-3154 excessive boric acid leak
CR 1077973, 2-CH-FT-2155A excessive discolored Boric Acid
CR 1078234, Discolored boric acid noted at packing of 2-CH-ICV-3019
Corrective Actions (CAs)
CA3037522, Perform Boric Acid Review to Restore Full Qualification for Boric Acid Leak Found
on 2-CH 249 (associated with CR1044134
CA3044983, Perform Boric Acid Review for Excessive Wet Boric Acid on 2-SI-RV-2857 Leak
Off-Line (associated with CR1054222)
CA3053391, Perform Boric Acid Review (02-CH-MAN-2147-VALVE) (associated with
CR1063045)
CA3054717, Perform Boric Acid Review for Excessive, Discolored Boric Acid on 2-SI-83
(associated with CR1064466)
CA3054879, Perform Boric Acid Review: Moist, Discolored Boric Acid on 2-CH-MOV-2287A
(associated with CR1064483
Welding Documentation
Work Order (WO) 59103055303, Replace Valve IAW DC NA-17-00008 (02-RC-154-VALVE),
Repair/Replacement Plan 2017-102
Weld Map for location 02-RC-154
Weld Material Field Control Sheet for Welds # 50, 51, and 52A
Weld Data Record for Welds # 50, 51, and 52A
Procedure Qualification Record 801, Revision 2
Procedure Qualification Record 830
Procedure Qualification Record 831
Liquid Penetrant Examination Report BOP-PT-17-790 of Weld 50
Liquid Penetrant Examination Report BOP-PT-17-730 of Welds 51 & 52A
Welder Performance Qualification (WPQ) of J. Hamilton, J. Olson, and A. Pennington
Welding Technique Sheet for Welding Technique Number 801, Revision 8
WO 59102981224, Valve (02-CH-MOV-2267B-VALVE) Replacement Due to History of Leakby,
Repair/Replacement Plan 2017-019
Weld Map for location 2-CH-MOV-2267B
Weld Material Field Control Sheet for Welds # 7, 8, and SW32
Welder Performance Qualification (WPQ) of J. Coleman, T. McGlothlin, and N. Sadler
Welding Technique Sheet for Welding Technique Number 801, Revision 2
Welding Technique Sheet for Welding Technique Number 803, Revision 9
Welding Technique Sheet for Welding Technique Number 805, Revision 3
Welding Technique Sheet for Welding Technique Number 809, Revision 2
Welding Technique Sheet for Welding Technique Number 830
7
Welding Technique Sheet for Welding Technique Number 831
Ultrasonic Examination Report BOP-UT-17-013 of Welds 7 and SW32
Ultrasonic Examination Report BOP-UT-17-025 of Weld 8
Liquid Penetrant Examination Report BOP-PT-17-733 of Final Welds 7 and SW32
Liquid Penetrant Examination Report BOP-PT-17-771 of Final Weld 8
Liquid Penetrant Examination Report PT-17-001 of 12050-WMKS-0111AP / 6-Sl-441 / 7
Liquid Penetrant Examination Report PT-17-002 of 12050-WMKS-0111AP / 6-Sl-441 /
SW32
Liquid Penetrant Examination Report PT-17-006 of 12050-WMKS-0111AQ / 6-CH-603 / 8
Radiography Report NDE-R-2017-48 of Weld Joint #7
Radiography Report NDE-R-2017-48 of Weld Joint #8
Radiography Report NDE-R-2017-48 of Weld Joint #SW32
Ultrasonic Examination Report UT-17*002 of 12050-WMKS-0111AP / 6-Sl-441 / SW32
Ultrasonic Examination Report UT-17*003 of 12050-WMKS-0111AP / 6-Sl-441 / 7
Ultrasonic Examination Report UT-17*011 of 12050-WMKS-0111AP / 6-Sl-441 / 7
Ultrasonic Examination Report UT-17*012 of 12050-WMKS-0111AP / 6-Sl-441 / SW32
WO 59103105688, Remove/Reinstall Valve (02-CC-328-VALVE) and Piping, ASME Class 3
Repair/Replacement Plan 2017-111
Weld Map for location 02-CC-328-VALVE
Weld Data Record for Welds # 34
Weld Material Field Control Sheet for Welds # 34
Welding Technique Sheet for Welding Technique Number 103, Revision 8
Procedure Qualification Record 101, Revision 5
Procedure Qualification Record 102, Revision A
Procedure Qualification Record 103
Procedure Qualification Record 105, Revision 4
Procedure Qualification Record 135
Welder Performance Qualification (WPQ) Records of R. Stewart, J. Olson, and A.
Pennington
Other Documents
ASME Code Cases N-729-1 and N-729-4
Ultrasonic Examination Report UT-17-038 of 12050-WMKS-0102B / 16-WFPD-423 / 40, Elbow
to Nozzle
Ultrasonic Examination Report UT-17-037 of 12050-WMKS-0102A / 16-WFPD-424 / 75, Elbow
to Nozzle
Calibration Certificate digital thermometer, Serial Number 1079BGCY
Certificate of Calibration (Certificate #172330SRAM1) for light meter, serial number OSRAM-1
Certificate of Certification for Ultra Gel II, Batch# 12J066
Certification for Magnaflux Spotcheck, SKC-S, Batch #: 16H07K
Certification for Magnaflux Penetrate, SKC-S, Batch #: 16H07K
Certificate of Certification, Spotcheck Penetrant, SKL-SP2, Batch# 15J02K
Certificate of Certification, Spotcheck Developer, SKD-S2, Batch# 14K04K
Krautkramer Transducer Certificate of Conformity for Serial Number OlCXBJ
Krautkramer Transducer Certificate of Conformity for Serial Number OlCXBN
NDE Personnel Certification Records for J. Block, T. Coburn, and C. Popp
Relief Request N2-I4-NDE-002
Report Number L-17-012, Ultrasonic Instrument Linearity for Olympus Model EPOCH 600,
Serial Number 150864802
8
Self-Assessment Report (SAR) 000486, Nuclear Welding Program Formal Fleet Self-
Assessment
SAR 002257, Inservice Inspection/Risk-Informed Inservice Inspection Program Formal Self-
Assessment
SAR 002813, Boric Acid Corrosion Control Program (BACCP) Self Assessment
Section 1R11: Licensed Operator Requalification Program and Licensed Operator
Performance
Licensed Operator Requalification Program, Cycle 17-6, Segment 1B, Revision 5
Licensed Operator Requalification Program, Cycle 17-6, Segment 1C, Revision 4
2-OP-3.7, Unit Shutdown from Mode 1 to Mode 5 for Refueling, Revision 48
Section 1R12: Maintenance Effectiveness
1-PT-97.1B, Operations Periodic Test, Spent Fuel Pit Cooling Pump (1-FC-P-1B) Test,
Revision 17
Nuclear Electric Insurance Limited Loss Control Manual, January 2017 Edition
North Anna Narrative Logs regarding 1-FC-P-1B dated January 1, 2017-August 2, 2017
Vibration Trend for 1-FC-P-1B from June 24, 2008 to August 2, 2017
Corrective Action Documents
CR 1073731, 1-FC-P-1B Vibration Data in Alert Range
Work Order
Section 1R13: Maintenance Risk Assessments and Emergent Work Control
NUMARC 93-01, Industry Guidelines for Monitoring the Effectiveness of Maintenance at
Nuclear Power Plants, Revision 4A
1-Log-14, Non-Routine Surveillance Log, Initiate the following Maintenance Rule(a)(4) Fire RMA
Defense-in-Depth Measures for TR 7.5
WM-AA-301, Operational Risk Assessment, Revision 14
1-AP-27, Malfunction of Spent Fuel Pit System, Revision 26
Work Order
WO59102932957
WO59102933066
Section 1R15: Operability Determinations and Functionality Assessments
OD CA 3063143 - Degraded Non-Conforming Condition of SW Traveling Screens due to
Electrical Design Inadequacy Identified in CR1074806
CR1074806,Reduced Margin due to Temperature Derating of SWPH MCC Bucket
Transformers/Fuses
Operation Department Shift Orders for August 25, 2017
OP-AA-102, Operability Determination, Revision 15
9
1-AR-J-H6, SW Screens 1A-1B No Rotation, SW Screens Hi P, Revision 3
ME-0305, Service Water Pump NPSH, Revision 0
CR554449, 1-CC-P-1B Outboard Pump Bearing Oil Sample Discoloration
CA286656, Track and document oil sample results for 1-CC-P-1B
Engineering Log Entry for 7/25/2017, 1-CC-P-1B Oil Sample has Visible Ferrous Particulates
Work Order
WO05910312409
Corrective Action Documents
CR 1073832
CR 3062123
CR 1079324
CR 1000423
Section 1R19: Post Maintenance Testing
Procedures, Guidance Documents, and Manuals
0-PT-100.2, Fire Protection Pumps - Annual Test, Revision 26
CR1075127, Tagged 1FP-P-2 for pump replacement
CR1075979, 1-FP-P-2 New Pump high vibrations on return to service
1-PT-77.11B.1, Control Room Chiller 1-HV-E-4B IST Comprehensive Pump and Valve Test,
Revision 12-OTO1
Work Order
WO59103085096
Section 1R22: Surveillance Testing
Procedures, Guidance Documents, and Manual
1-PT-71.3Q, 1-FW-3B, B Motor-Driven AFW Pump, and Valve Test, Revision 53
CR1073791, 2-PT-71.3Q.1 test results need engineering evaluation
2-PT-17.1, Control Rod Operability, Revision 41
2-AP-1.2, Dropped Rod, Revision 18
2-AR-A-H1, Rod Bank A Lo/lo-lo Limit, Revision 1
2-AR-A-H2, Rod Bank B Lo/lo-lo Limit, Revision 1
2-AR-A-H3, Rod Bank C Lo/lo-lo Limit, Revision 3
2-AR-A-H4, Rod Bank D Lo/lo-lo Limit, Revision 3
2-PT-82.4A, 2H Diesel Generator Test (Start by ESF Actuation), Revision 75
2-PT-82.4B, 2J Diesel Generator Test (Start by ESF Actuation), Revision 72
2-PT-82.2A, 2H Diesel Generator Test (Simulated Loss of Off-Site Power), Revision 74
2-PT-82.2A, 2J Diesel Generator Test (Simulated Loss of Off-Site Power), Revision 76
2-PT-83.12H, 2H Diesel Generator Test (Start by ESF Actuation) followed by 24-hour Run and
Hot Restart Test, Revision 29
2-PT-142.10A.1, Valve Inservice Inspection Associated with 2-EG-TK-2HA for 2-EB-15 Check
Valve, Revision 3
2-PT-142.10A.2, Valve Inservice Inspection Associated with 2-EG-TK-2HB for 2-EB-61 Check
Valve, Revision 3
Procedure 2-PT-36.7.1, Engineered Safety Features and Containment Isolation Valve
10
Response Time, Rev 23
Procedure 2-PT-57.5A, Leak Rate Test of 2-SI-P-1A and Associated Piping and Inservice
Inspection for 2-SI-6, Rev 21
Procedure 2-PT-57.5B, Leak Rate Test of 2-SI-P-1B and Associated Piping and Inservice
Inspection for 2-SI-29, Rev 21
Procedure 2-PT-213.5J, Valve Inservice Inspection (2-QS-MOV-201B), Rev 10
Work Order
WO59080458701
WO59060120201
Section 2RS1: Radiological Hazard Assessment and Exposure Controls
Procedures, Guidance Documents, and Manuals
HP-1032.080, Controlled Area and Unrestricted Area Radiological Surveys, Rev. 9
HP-1032.110, Dose Rate Trending, Rev. 1
HP-1032.131, Initial Movement of Irradiated Fuel Assemblies to and From the Reactor Vessel,
Rev. 0
HP-1032.140, Guidance/Actions to Take When Licensed Material is Detected at Exposure
Control, Rev. 0
HP-1032.202, Radiological Informational Posting, Rev. 0
North Anna Power Station Outage ALARA Guide, Unit Two Refueling Outage September 2017
RP-AA-101, Radiological Protection Organization and Administration, Rev. 3
RP-AA-109, Radiological Survey Program, Rev. 0
RP-AA-201, Access Controls for High and Very High Radiation Areas, Rev. 8
RP-AA-202, Radiological Posting, Rev. 10
RP-AA-222, Radiation Surveys, Rev. 3
RP-AA-223, Contamination Surveys, Rev. 4
RP-AA-224, Airborne Radioactivity Surveys, Rev. 3
RP-AA-225, Unrestricted Release of Material, Rev. 6
RP-AA-226, Alpha Monitoring, Rev. 5
RP-AA-230, Personnel Contamination Monitoring and Decontamination, Rev. 11
RP-AA-240, Discrete Radioactive Particle Control, Rev. 2
RP-AA-270, Providing HP Coverage During Work, Rev. 2
RP-AA-271, Use of Remote Monitoring, Rev. 2
RP-AA-275, Radiological Risk Assessment Process, Rev. 3
VPAP-2101, Radiation Protection Program, Rev. 35
Records and Data
Air Sample Analysis: 259' A Gas Stripper, Routine Gas & Particulate, Filename: 13-Jul-17-
400030 and 13-Jul-17-400031, 7/13/2017 and Filename: 10-Aug-17-400017 and 400020,
8/10/2017; 259' B Gas Stripper, Routine Gas & Particulate, Filename: 13-Jul-17-400032
and 13-Jul-17-400032, 7/13/2017 and Filename: 10-Aug-17-400018 and 400019, 8/10/2017;
Unit 1 Quench Spray Pump House and Main Steam, Routine Particulate, Filename: and 01-
Aug-17-400028, 8/1/2017 and Filename: 05-Sep-17-400001, 9/5/2017; Hot Lab, Routine
Particulate, Filename: 06-Jul-17-400003, 7/6/2017 and Filename: 03-Aug-17-400001,
8/3/2017
11
List, Location of Locked High Radiation Areas (LHRAs) and Very High Radiation Areas
(VHRAs) [including areas with the potential to become a LHRA during routine operations or
outages], 8/29/2017
List, Non-Fuel Items Stored in the NAPS Spent Fuel Pool [based on Assembly Information
Reports, Fig File: N2EOC25.fig, 8/24/2017 and 8/30/2017], 8/30/2017
List, 2017 Non-Outage RWP [including dose and dose rate alarms by task], 7/26/2017
List, 2017 Unit 2 Outage RWPs [including dose and dose rate alarms by task], 9/6/2017
Non-Outage Radiological Surveys: Decon Building 251' Spent Resin Hold-up Tank Area,
1/5/2015; Aux Building, 274' VCT Cubes, 2/10/2016; U2 Containment, 216' lncore access
(keyway), 4/5/2016; U1 Containment, 216' lncore access (keyway), 9/16/2016; U2 Reactor
Cavity, 4/4/2017; Unit 2 Unit 1 and Unit 2 Equipment Hatch Platforms, Perform PT-60.1B
and Alarm Checks, 4/16/2017; Unit 2 Personnel Hatch, Security Alarm Checks, 6/25/2017;
Unit 1 Personnel Hatch, Security Alarm Checks, 6/25/2017; Demin Alley, Resin Transfer,
6/28/2017; Waste Solids Area, 6/29/2017; Decon Building, 251', 6/29/2017; Aux Building,
259' Gas Strippers, 7/13/2017 and 8/10/2017; Aux Building, 244' Gas Strippers, 7/13/2017
and 8/10/2017; Unit 1 Quench Spray Pump House and Main Steam 272, 8/1/2017 and
9/5/2017; U1 & U2 Charging Pump Cubicles, 7/31/2017 and 9/4/2017; Health Physics
Office, Count Room, and Chemistry Office/Lab, 7/6/2017 and 8/3/2017
NSTS Annual Inventory Reconciliation Report, for License Number NPF-4, Confirmation of
Annual Inventory Reconciliation, 1/20/2017
Outage Radiological Surveys: U2 Reactor Cavity, Initial Cavity Dose Rate Survey, 9/10/2017;
U2 Reactor Cavity, Initial Cavity Contamination Survey, 9/10/2017; U2 Containment, 241'
"B" Loop Room 2-PT-46.21, 9/10/2017; U2 Containment, 231' RHR and Excess Letdown
HX Platform, 9/10/2017; U2 Containment, Top of Pressurizer, 9/10/2017; U2 Reactor Head,
Dose Rate and Contamination Survey, 9/11/2017; U2 Containment, Top of Pressurizer
Removal of 2-RC-SV-2115B, 9/12/2017; U2 Reactor Cavity, Reactor Head Lift, 9/15/2017;
U2 Containment, 241' During Head Lift & Move To Lower Containment, 9/15/2017; U2
Containment, 262' During Head Lift & Move To Lower Containment, 9/15/2017; U2
Containment, 216' Reactor Head on Head Stand in Lower Containment, 9/15/2017; U2
Containment, 291' Refuel Floor Post Head Lift, 9/15/2017; U2 Reactor Cavity, Upper
Internals Lift & Move, 9/16/2017; U2 Containment, 291', 9/18/2017; U2 Reactor Cavity,
Remove and Cut 11 Thimbles, 9/19/2017; U2 Containment 262' "B" Cubicle, Open & Inspect
2-CH-340, 9/21/2017;
Radiation Work Permit (RWP) 17-2002, Maintenance activities within the Unit 2 Circulating
Water Tunnel, Rev 0
Radioactive Source Master Listing (NAPS) [radioactive source inventory], 8/21/2017
RWP 17-2201, lncore Drive unit 5 and 10 path maintenance, Rev. 0
RWP 17-2215, Valve Maintenance in Locked High Radiation Areas, Rev. 0
RWP 17-2251, Disassemble and reassemble Reactor Vessel Head, Rev. 0
RWP 17-2266, Perform DCP 15-00088, lncore Flux Thimble modifications, Rev. 0
Site-Wide Communication, U2 RFO RP Update, Radiological Postings, 9/22/2017
Spreadsheet, North Anna Power Station Radiological Survey Schedule Check Sheet [Survey
Frequency], August 2017
Corrective Action Documents
PI-AA-200, Corrective Action, Rev. 33
PI-AA-300, Cause Evaluation, Rev. 14
Nuclear Oversight Audit Report, Audit 16-04 RP, PCP, Chemistry & Millstone Refueling,
5/26/2016
Self-Assessment, PIR Number 1019510, Exit Monitor Reliability, 4/15/2016
Self-Assessment, PIR Number 1057549, Radiological Work Control Program Review, 3/14/2017
12
Self-Assessment Results Measurement Review, PIR1019510 - Exit Monitor Reliability
CR 1032511
CR 1032902
CR 1032903
CR 1034024
CR 1034627
CR 1034930
CR 1039806
CR 1043768
CR 1061774
CR 1067020
CR 1074424
CR 1078100
CR 1078223
CR 1078811
Section 2RS6: Liquid and Gaseous Effluents
Procedures, Guidance Documents, and Manuals
HP-3010-020, Radioactive Liquid Waste Release Permits, Rev. 5
HP-3010-021, Radioactive Liquid Waste Sampling and Analysis, Rev. 23
HP-3010-031, Radioactive Gaseous Waste Sampling and Analysis, Rev. 40
HP-3010-032, Radioactive Gaseous Waste Accountability and Dose Calculations, Rev. 15
HP-3010.040, Radiation Monitoring System Setpoint Determination, Rev. 26
VPAP-2103N, Offsite Dose Calculation Manual (North Anna), Rev. 27
0-HSP-LQC-001, Confirmatory Measurements Using Blind Samples, Rev. 0
0-PT-37.1, Radiation Monitoring Equipment Source Check, Rev. 08
Records and Data
Annual Radioactive Effluent Release Report, 2015 and 2016
Certificate Detalonnage (Calibration Certificate), MGP Instruments, S/N 6012 and 6054,
10/19/2000
Certificate of Conformance, Westinghouse Electric Corporation, S/N 01-315 and 01-317,
05/12/1989
Certificate of Conformance, Westinghouse Electric Corporation, S/N 02-691 and 02-754,
07/01/1989
Eckert & Ziegler Radiochemistry Cross Check Program for 2015, 2016 and the 1st Quarter 2017
Gaseous Release Permit# G-20170801-277-B, BRT Vent, 08/07/2017
Gaseous Release Permit# G-20170801-276-B, Aux Bldg Roof Fans, 08/07/2017
Gaseous Release Permit# G-20170801-283-C, Unit 1 CAE, 08/07/2017
Gaseous Release Permit # G-20160223-072-B, Process Vent, 02/23/2016
Liquid Release Permit # L-20170728-064-C, Clarifier, 07/28/2017
Liquid Release Permit # L-20170701-066-C, Unit 1 HCBD, 07/01/2017
Liquid Release Permit # L-20170701-067-C, Unit 2 HCBD, 07/01/2017
List, Effluent Radiation Monitors Out of Service for Greater than 24 Hours since 06/01/2015
North Anna Power Station Equipment Reliability List for System Radiation Monitoring, Updated
08/26/2014
Nuclide Distribution Report, 10CFR61 Waste Stream Analyses for Multiple Waste Streams,
2016
Radioactive Sealed Source Certificate and Test Report, QSA Global, S/N 8788GS, 03/13/2001
Unplanned Gaseous Release Record, ID 16-AGR-01, U2 RWST Gas Space, 01/20/2016
13
Unplanned Gaseous Release Record, ID 16-AGR-02, Process Vent Hi Hi Alarm, 02/23/2016
Work Order (WO) 5910201495932, U1 RM-178 Process Vent Normal Range, 01/23/2014
WO 59102473155, U1 SW-RM-130, Discharge Tunnel Effluent Radiation Monitor Calibration,
08/05/2015
WO 59102488682, LW-RM-110 Clarifier Hold Up Tank Inlet Monitor Calibration, 06/17/2014
WO 59102721714, 0-PT-77.4A, Laboratory Analysis- 1-HV-FL-3A ECCS PREACS, completed
07/09/2015
WO 59102735956, Condenser Air Ejector In-Line Radio Gas Monitor (2-SV-RM-221) Channel
Calibration, 12/04/2015
WO 591029166517, Condenser Air Ejector In-Line Radio Gas Monitor (2-SV-RM-221) Channel
Calibration, 06/06/2017
WO 59102739309, 0-PT-38.3.4, Calibration 1-HV-F-1212A, Vent A Flow, 12/10/2015
WO 59102784040, 0-PT-77.4B, Laboratory Analysis- 1-HV-FL-3B ECCS PREACS, completed
02/28/2016
WO 59102807780, 0-PT-77.14A, In Place Filter Test 1-HV-FL-3A ECCS PREACS, completed
08/24/2016
WO 59102825717, 0-PT-37.1, Radiation Monitoring Equipment Source Check, 08-05-2015
WO 59102882205, Vent Stack A Normal and High Range Effluent Radiation Monitor (VG-RM-
179) Channel Calibration, 01/18/2017
WO 59102882688, 0-PT-77.14B, In Place Filter Test 1-HV-FL-3B ECCS PREACS, completed
02/16/2017
WO 59102888990, LW-RM-111 Clarifier Hold Up Tank Outlet Monitor Calibration, 09/04/2015
WO 59102892494, LW-RM-111 Clarifier Hold Up Tank Outlet Monitor Calibration, 08/18/2016
WO 59102904056, LW-RM-110 Clarifier Hold Up Tank Inlet Monitor Calibration, 03/15/2017
WO 59102917391, 0-PT-38.3.4, Calibration 1-HV-F-1212A, Vent A Flow, 06/13/2017
0-PT-487.10, Radiological Environmental Monitoring Program, Land Use Census, 10/15/2015
0-PT-487.10, Radiological Environmental Monitoring Program, Land Use Census, 10/19/2016
Corrective Action Documents
PI-AA-200, Corrective Action, Rev. 33
Self-Assessment PIR1003232, Radioactive Effluent Control Program, 11/20/2015
CR 1043795
CR 1005452
CR 1024639
CR 1073079
CR 1010910
CR 582501
CR 1033833
CR 1072741
Section 2RS7: Radiological Environmental Monitoring Program (REMP)
Procedures, Guidance Documents, and Manuals
HP-1033.620, Portable Air Samplers Calibration and Operation, Rev. 9
HP-3051.010, Radiological Environmental Monitoring Program, Rev. 29
HP-3051.020, Ground Water Protection Program, Rev. 9
RP-AA-502, Groundwater Protection Program, Rev. 5
RP-AA-111-1012, Radiological Environmental Monitoring Program Review, Rev. 1
VPAP-2103N, Offsite Dose Calculation Manual (North Anna), Rev. 27
0-GEP-14, Spent Fuel Pool Telltale Drain Evaluation, Rev. 2
0-ICP-MM-MIS-001B, Backup Meteorological Tower Instrumentation Calibration, Rev. 3
14
0-ICP-MM-MIS-001P, Primary Meteorological Tower Instrumentation Calibration, Rev. 6
0-PT-440, Monitoring Normally Non-Radioactive systems for Radioactive Contamination, Rev. 9
Records and Data
Annual Radiological Environmental Operating Report (AREOR), North Anna Power Station for
2015 and 2016, April 2015 and 2016
Annual Radioactive Effluent Release Report (ARERR), North Anna Power Station for 2015 and
2016, April 2015 and 2016
Environmental Sample Log [REMP Sampling Schedule] for August 2017
Memorandum with Attachment, North Anna Meteorological Data [Joint Frequency Distributions
and Data Recovery Percentage] for 2014, 2015, and 2016, 1/14/2015, 3/10/2016, and
2/17/2017
Radiological Decommissioning Record, Spill below 2-QS-41 at U-2 RWST, Sample ID# 25-
SEP-15-400033, CR1011040, 9/25/2015
Radiological Decommissioning Record, NaOH Spill, Sample ID# 16-MAR-16-400072,
CR1030721, 3/16/2016
Radiological Decommissioning Record, Spill below 2-QS-38, Sample ID# 29-MAR-16-400021,
CR1032085, 3/29/2016
Radiological Decommissioning Record, Spill below 1-QS-24 at U-1 RWST, Sample ID# 20-FEB-
17-400020, CR1060475, 2/20/2017
REMP Air Sampler Certificate of Calibration: Kit# 15, 10/21/2015, and 10/19/2016; Kit# 14,
10/21/2015, and 10/19/2016; Kit# 13, 10/21/2015, and 10/19/2016; Kit# 12, 10/21/2015, and
10/19/2016; Kit# 11, 10/21/2015, and 10/19/2016; Kit# 10, 10/21/2015, and 10/19/2016; Kit# 9,
10/27/2015, and 10/19/2016; Kit# 8, 10/21/2015, and 10/19/2016; Kit# 7, 10/21/2015, and
10/19/2016; Kit# 6, 10/21/2015, and 10/19/2016; Kit# 5, 10/21/2015, 10/19/2016; Kit# 4,
10/21/2015, and 10/19/2016; Kit# 3, 10/21/2015, and 10/19/2016; Kit# 2, 10/27/2015, and
10/20/2016; Kit# 1, 10/21/2015, and 10/20/2016
Spreadsheets, Direct Radiation Measurements - Sector Quarterly TLD Results [REMP TLDs],
for 2015, 2016, and 1st Quarter 2017
Sample Collection/Receipt Sheet [REMP Air Sample Data for Vendor], 8/8/2017
Vendor Laboratory Cross Check Performance Summary for 2015 and 2016, [including Eckert &
Zeigler Analytics, Inc, DOE's Mixed Analyte Performance Evaluation Program (MAPEP), and
Environmental Resource Associates, (ERA)], Data from 2015 and 2016 AREOR
Work Order (WO) 59102985187, 0-PT-40.1, Meteorological Monitoring System Calibration,
12/20/2016
WO 59102932630, 01-MM-TWR-PRI-UNIT, Annual Tower Inspection [Primary Meteorological
Tower], 5/17/2017
WO 59103043600, 0-PT-40.1, Meteorological Monitoring System Calibration, 6/12/2017
0-GEP-14, Spent Fuel Pool Telltale Drain Evaluation [Inspection by Engineering], 12/8/2016 and
6/8/2017
2012 Priority Index Spreadsheet, North Anna Power Station Unit 1 [ranking of Structure,
System, and Component risk to groundwater]
2012 Priority Index Spreadsheet, North Anna Power Station Unit 2 [ranking of Structure,
System, and Component risk to groundwater]
Corrective Action Documents
PI-AA-200, Corrective Action, Rev. 33
Audit 15-10: Offsite Dose Calculation Manual, Radiological Environmental Monitoring Program,
Environmental Protection Plan, 12/16/2015
PIR1019508, Radiological Environmental Monitoring Program Review, North Anna Power
Station, Q4 2014 to Q4 2015, 5/26/2016
15
CR 582528
CR 1002672
CR 1005525
CR 1012719
CR 1021114
CR 1023150
CR 1038101
CR 1055473
CR 1063665
CR 1065819
CR 1071212
Section 2RS8: Radioactive Material Processing and Transportation
Procedures, Guidance Documents, and Manuals
2-MOP-20.2, Resin Discharge and Addition to 2-CH-I-2, Cation Bed
Demineralizer, Rev. 16
HP-1072.020, Sampling, Analyzing, and Classifying Solid Radioactive Waste,
Rev. 11
HP-1071.021, Storing Radioactive Material Outside the Protected Area, Rev. 21
HP-1071.040, Packaging and Shipment of Radioactive Material, Rev. 17
HP-1072.080, Radioactive Waste Transfer to Erwin Resin Solutions, Rev. 9
PI-AA-200, Corrective Action, Rev. 33
RP-AA-232, Radioactive Material Control, Rev. 9
VPAP 2104, Dominion Station Administrative Procedure, Radioactive Waste Process Control
Program (PCP), Rev. 8
Records and Data
HP-1071.021, Attachment 3, Radioactive Material Inventory Record for Storage Locations
Outside the Protected Area, 3/15/17 and 6/12/17
Radiological Survey, Decontamination Building, 217 Elevation, Waste Solidification Area,
9/17/17
Radiological Survey, 17-RHR-31 Nut Runner from SPS, 9/19/17
Radioactive Waste Packaging, Transportation, and Disposal Training (PowerPoint Slides),
HPTCTP-16-Cycle-02-LP-1 (TIR 14586 - Rev. 1)
RP-AA-232, Attachment 2, Container Inspection Checklist, 5/15/17 and 8/7/17
Shipping Records and Radwaste Data
Shipment No. 15-ERS-01, Primary Resin, 3/6/15
Shipment No. 16-DUR-24, DAW / Oil, 3/24/16
Shipment No. 17-DUR-02, Dewatered Blended Resin, 3/3/17
Shipment No. 17-1032, U1 Demin Liquid Sample, 9/21/17
10 CFR Part 61 Waste Stream Analyses: U1 DAW, 10/6/16; U2 DAW, 4/5/16; SRHT, 9/20/16
Corrective Action Documents
CR 1003460
CR 1028592
CR 1033755
CR 1036591
CR 1042776
CR 1063026
16
CR 1068352
NUPIC Audit / Survey No. 23931, Energy Solutions, 6/15/15
Section 4OA1: Performance Indicator Verification
Procedures and Guidance Documents
HP-3010.022, Radioactive Liquid Waste Accountability and Dose Calculations, Rev. 6
HP-3010.032, Radioactive Gaseous Waste Accountability and Dose Calculations, Rev. 15
LI-AA-500, NRC/INPO/WANO Performance Indicator and MOR Reporting, Rev. 2
PI-AA-100-1000, Performance Indicators, Rev. 5
RP-AA-111, Monitoring and Improving Radiological Performance, Rev. 2
RP-AA-112, Radiation Safety Performance Indicator Reporting, Rev. 4
VPAP-2802, Notifications and Reports, Rev. 43
Records and Data
RP-AA-124, Attachment 6, Electronic Dosimeter Dose/Dose Rate Alarm Log, 07/11/2017
Abnormal Gaseous Release, 16-AGR-01, 1/20/2016
Abnormal Gaseous Release, 16-AGR-02, 2/23/2016
Gaseous Release Permit [Gas Permit Post-Release Data], G-20160120-033-B, 1/20/2016
Gaseous Release Permit [Gas Permit Post-Release Data], G-20160223-072-B, 2/23/2016
Gaseous Effluents Cumulative Dose Summary, January through June 2017, 7/11/2017
NAPS NRC Performance Indicator, April 2016 through July 2017, various dates
Report, OpenEMS, Gas Status Summary Reports, January through June 2017 [summation of
all gaseous releases, including off-site dose summaries], 07/18/2017
Report, OpenEMS, Liquid Status Summary Reports, January through June 2017 [summation of
all liquid releases, including off-site dose summaries], 07/18/2017
Corrective Action Documents
CR 1033397
CR 1034627
CR 1043607
CR 1064034