IR 05000261/2022002
| ML22221A225 | |
| Person / Time | |
|---|---|
| Site: | Robinson, 07200060  |
| Issue date: | 08/09/2022 |
| From: | David Dumbacher Division Reactor Projects II |
| To: | Flippin N Duke Energy Progress |
| References | |
| EA-22-060 IR 2022002 | |
| Download: ML22221A225 (12) | |
Text
SUBJECT:
H.B. ROBINSON STEAM ELECTRIC PLANT - INTEGRATED INSPECTION REPORT 05000261/2022002, 07200060/2022001 AND EXERCISE OF ENFORCEMENT DISCRETION
Dear Ms. Flippin:
On June 30, 2022, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at H.B. Robinson Steam Electric Plant. On July 14, 2022, the NRC inspectors discussed the results of this inspection with you and other members of your staff. The results of this inspection are documented in the enclosed report.
The NRC identified a violation of 10 CFR 72.212 (b)(6) associated with tornado hazard protection. Because this violation was identified during the discretion period covered by Enforcement Guidance Memorandum 22-001, Enforcement Discretion for Noncompliance of Tornado Hazard Protection requirements at Independent Spent Fuel Storage Installations, and because the licensee was implementing compensatory measures and has taken or plans to take the necessary actions to restore compliance, the NRC is exercising enforcement discretion by not issuing an enforcement action for the violation and is allowing continued Independent Spent Fuel Storage Installations (ISFSI) handling operations.
No findings or violations of more than minor significance were identified during this inspection.
August 9, 2022 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 Title 10 of the Code of Federal Regulations 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely, David E. Dumbacher, Chief Reactor Projects Branch 3 Division of Reactor Projects Docket No. 05000261 and 07200060 License No. DPR-23
Enclosure:
As stated
Inspection Report
Docket Number:
05000261 and 07200060
License Number:
Report Number:
05000261/2022002 and 07200060/2022001
Enterprise Identifier: I-2022-002-0028 and I-2022-001-0041
Licensee:
Duke Energy Progress, LLC
Facility:
H.B. Robinson Steam Electric Plant
Location:
Hartsville, SC
Inspection Dates:
April 01, 2022 to June 30, 2022
Inspectors:
B. Bishop, Senior Project Engineer
P. Cooper, Senior Reactor Inspector
M. Fannon, Senior Resident Inspector
J. Walker, Emergency Response Inspector
Approved By:
David E. Dumbacher, Chief
Reactor Projects Branch 3
Division of Reactor Projects
Enclosure
SUMMARY
The U.S. Nuclear Regulatory Commission (NRC) continued monitoring the licensees
performance by conducting an integrated inspection at H.B. Robinson Steam Electric Plant, in
accordance with the Reactor Oversight Process. The Reactor Oversight Process is the NRCs
program for overseeing the safe operation of commercial nuclear power reactors. Refer to
https://www.nrc.gov/reactors/operating/oversight.html for more information.
List of Findings and Violations
No findings or violations of more than minor significance were identified.
Additional Tracking Items
Type
Issue Number
Title
Report Section
Status
Enforcement Action 22-060:
Tornado Hazards Protection
Requirements at
Independent Spent Fuel
Storage Installations (EGM 22-001)
60855
Closed
PLANT STATUS
Unit 2 began the inspection period at rated thermal power (RTP). On June 17, 2022, the unit
was down powered to 53 percent RTP for repairs on an electro-hydraulic leak on the left main
steam stop valve. The unit was returned to RTP on June 18, 2022. The unit remained at or
near RTP for the remainder of the inspection period.
INSPECTION SCOPES
Inspections were conducted using the appropriate portions of the inspection procedures (IPs) in
effect at the beginning of the inspection unless otherwise noted. Currently approved IPs with
their attached revision histories are located on the public website at http://www.nrc.gov/reading-
rm/doc-collections/insp-manual/inspection-procedure/index.html. Samples were declared
complete when the IP requirements most appropriate to the inspection activity were met
consistent with Inspection Manual Chapter (IMC) 2515, Light-Water Reactor Inspection
Program - Operations Phase. The inspectors performed activities described in IMC 2515,
Appendix DProperty "Inspection Manual Chapter" (as page type) with input value "NRC Inspection Manual 2515,</br></br>Appendix D" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., Plant Status, observed risk significant activities, and completed on-site portions of
IPs. The inspectors reviewed selected procedures and records, observed activities, and
interviewed personnel to assess licensee performance and compliance with Commission rules
and regulations, license conditions, site procedures, and standards.
REACTOR SAFETY
71111.01 - Adverse Weather Protection
Seasonal Extreme Weather Sample (IP Section 03.01) (1 Sample)
(1)
The inspectors evaluated readiness for seasonal extreme weather conditions prior to
the onset of seasonal hot temperatures and hurricane season for the following
systems:
Offsite power and emergency diesel generators (EDGs) on May 16 through 19, 2022.
External Flooding Sample (IP Section 03.03) (1 Sample)
(1)
The inspectors evaluated that flood protection barriers, mitigation plans, procedures,
and equipment are consistent with the licensees design requirements and risk
analysis assumptions for coping with external flooding on May 22 through 25, 2022.
71111.04 - Equipment Alignment
Partial Walkdown Sample (IP Section 03.01) (4 Samples)
The inspectors evaluated system configurations during partial walkdowns of the following
systems/trains:
(1)
'A' safety injection (SI) on April 5, 2022
(2)
Service water at the intake on April 13, 2022
(3)
'A' EDG on May 3, 2022
(4)
'B' component cooling water (CCW) during 'C' CCW maintenance activities on June
14, 2022
71111.05 - Fire Protection
Fire Area Walkdown and Inspection Sample (IP Section 03.01) (5 Samples)
The inspectors evaluated the implementation of the fire protection program by conducting a
walkdown and performing a review to verify program compliance, equipment functionality,
material condition, and operational readiness of the following fire areas:
(1)
Fire zones 9 and 10, north and south cable vaults on April 5, 2022
(2)
Fire zone 29, intake service water pump area on April 13, 2022
(3)
Fire zones 31 and 32, refueling and primary water storage tank area on May 2, 2022
(4)
Fire zone 30, diesel fuel oil storage tank area on May 9, 2022
(5)
Fire zones 17 and 18, control room ventilation equipment room on June 22, 2022
71111.11Q - Licensed Operator Requalification Program and Licensed Operator Performance
Licensed Operator Performance in the Actual Plant/Main Control Room (IP Section 03.01) (1
Sample)
(1)
The inspectors observed and evaluated licensed operator performance in the Control
Room during nuclear instrument testing and alarm response actions on June 3, 2022.
Licensed Operator Requalification Training/Examinations (IP Section 03.02) (1 Sample)
(1)
The inspectors observed and evaluated an annual exam on June 21, 2022.
71111.12 - Maintenance Effectiveness
Maintenance Effectiveness (IP Section 03.01) (2 Samples)
The inspectors evaluated the effectiveness of maintenance to ensure the following
structures, systems, and components (SSCs) remain capable of performing their intended
function:
(1)
'C' CCW pump out of service for outboard seal replacement
(Work Order [WO] 20500343)
(2)
'A' charging pump recirculation root isolation leakage that was identified during 'B'
charging pump maintenance activities (Nuclear Condition Report (NCR) 2424072)
71111.13 - Maintenance Risk Assessments and Emergent Work Control
Risk Assessment and Management Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the accuracy and completeness of risk assessments for the
following planned and emergent work activities to ensure configuration changes and
appropriate work controls were addressed:
(1)
'B' charging pump maintenance activities on April 6, 2022
(2)
'B' motor driven auxiliary feedwater (MDAFW) maintenance and testing on
April 12, 2022
(3)
'C' CCW outboard seal replacement on April 18, 2022
(4)
'B' CCW pump maintenance activities and control room emergency filtration system
maintenance activities on May 24, 2022
(5)
'C' CCW inboard seal replacement and 'C' charging pump packing replacement on
June 14 and 15, 2022
(6)
'C' SI maintenance activities on June 21, 2022
71111.15 - Operability Determinations and Functionality Assessments
Operability Determination or Functionality Assessment (IP Section 03.01) (5 Samples)
The inspectors evaluated the licensee's justifications and actions associated with the
following operability determinations and functionality assessments:
(1)
NCR 2422946, investigate noise from 'A' CCW pump motor
(2)
NCR 2424072, 'A' charging pump recirculation root isolation leak
(3)
NCR 2424167, 'C' CCW inboard seal leak
(4)
NCR 2427281, N-44 power range lower detector spiked for approximately 90
seconds
(5)
NCR 2429825, loss of containment average temperature indication
71111.18 - Plant Modifications
Temporary Modifications and/or Permanent Modifications (IP Section 03.01 and/or 03.02) (1
Sample)
The inspectors evaluated the following temporary or permanent modifications:
(1)
Engineering Change 421076, EDG fuel injector pump thread engagement
Severe Accident Management Guidelines (SAMG) Update (IP Section 03.03) (1 Sample)
(1)
The inspectors verified the site SAMG were updated in accordance with the
pressurized water reactor generic severe accident technical guidelines and validated
in accordance with NEI 14-01, Emergency Response Procedures and Guidelines for
Beyond Design Basis Events and Severe Accidents, Revision 1.
71111.19 - Post-Maintenance Testing
Post-Maintenance Test Sample (IP Section 03.01) (6 Samples)
The inspectors evaluated the following post-maintenance testing activities to verify system
operability and/or functionality:
(1)
OST-201-2, 'B' MDAFW component test following maintenance activities on
April 12, 2022
(2)
OST-908-4, 'C' CCW surveillance test following outboard seal replacement on
April 18 and 19, 2022
(3)
OST-352-2, containment spray component test following maintenance activities on
May 11, 2022
(4)
OST-010, power range calorimetric following N-44 power range detector activities on
May 19, 2022
(5)
WO 20510070, 'A' control room emergency filtration system operational check
following belt replacements on June 1, 2022
(6)
OST-151-6, 'C' SI pump comprehensive flow test following maintenance on
July 21, 2022
71111.22 - Surveillance Testing
The inspectors evaluated the following surveillance testing activities to verify system operability
and/or functionality:
Surveillance Tests (other) (IP Section 03.01) (2 Samples)
(1)
OST-023, monthly surveillances on April 12, 2022
(2)
OST-409-2, 'B' EDG fast start surveillance test on April 17, 2022
Inservice Testing (IP Section 03.01) (1 Sample)
(1)
OST-908-4, 'C' CCW pump test on June 15, 2022
FLEX Testing (IP Section 03.02) (1 Sample)
(1)
OST-453, annual test of the 'A' diverse and flexible coping strategies diesel generator
on May 12, 2022
OTHER ACTIVITIES - BASELINE
71151 - Performance Indicator Verification
The inspectors verified licensee performance indicators submittals listed below:
IE04: Unplanned Scrams with Complications (USwC) Sample (IP Section 02.03) (1 Sample)
(1)
April 1, 2021 through March 31, 2022
MS05: Safety System Functional Failures (SSFFs) Sample (IP Section 02.04) (1 Sample)
(1)
April 1, 2021 through March 31, 2022
MS06: Emergency AC Power Systems (IP Section 02.05) (1 Sample)
(1)
April 1, 2021 through March 31, 2022
71152A - Annual Follow-up Problem Identification and Resolution
Annual Follow-up of Selected Issues (Section 03.03) (2 Samples)
The inspectors reviewed the licensees implementation of its corrective action program
related to the following issues:
(1)
NCR 2383030, corrective actions for the plant vent flow estimation when the flow
instrument is out of service
(2)
NCR 2412278, fire watch procedure revised due to lack of clarity for duties and
assignments of a continuous fire watch
71152S - Semiannual Trend Problem Identification and Resolution
Semiannual Trend Review (Section 03.02) (1 Sample)
(1)
The inspectors reviewed the licensees corrective action program for potential
adverse trends in equipment reliability and equipment issue trending that might be
indicative of a more significant safety issue.
OTHER ACTIVITIES - TEMPORARY INSTRUCTIONS, INFREQUENT AND ABNORMAL
60855 - Operation of an Independent Spent Fuel Storage Installations (ISFSI)
Inspections were conducted using the appropriate portions of the IPs in effect at the beginning
of the inspection unless otherwise noted. Currently approved IPs with their attached revision
histories are located on the public website at http://www.nrc.gov/reading-rm/doc-
collections/insp-manual/inspection-procedure/index.html. Samples were declared complete
when the IP requirements most appropriate to the inspection activity were met consistent with
Inspection Manual Chapter (IMC) 2690, Inspection Program for Storage of Spent Reactor Fuel
and Reactor-Related Greater-than-Class C Waste at ISFSI and for 10 CFR Part 71
Transportation Packagings."
Operation Of An ISFSI (1 Sample)
(1)
From May 16 - 19, 2022, the inspectors performed a review of the licensees ISFSI
activities to verify compliance with regulatory requirements. During the on-site
inspection, the inspectors observed and reviewed licensee activities in each of the
five safety focus areas including occupational exposure, public exposure, fuel
damage, confinement, and impact to plant operations.
The inspectors reviewed selected procedures and records, observed activities, and
interviewed personnel to assess licensee performance and compliance with
Commission rules and regulations, license conditions, site procedures, and
standards. Additionally, the inspectors performed independent walkdowns of the
heavy load lifting equipment and the ISFSI haul path. The inspector also performed
an independent radiation survey of the ISFSI pad.
INSPECTION RESULTS
Enforcement
Discretion
Enforcement Action EA-22-060: Enforcement Action 22-060:
Tornado Hazards Protection Requirements at Independent
Spent Fuel Storage Installations (EGM 22-001)
60855
Description: Upon issuance of U.S. NRC Enforcement Guidance Memorandum 22-001
(ML22087A496), dated April 15, 2022, the licensee performed an assessment of all outdoor
dry cask storage activities that are not explicitly analyzed for tornado hazards in the cask
licensing basis. Several configurations were identified by the licensee including when a
loaded Dry Shielded Canister (DSC) with the shield plug is transferred out of the Spent Fuel
Pool to the Cask Handling Facility and when the transfer cask lid is removed to insert the
DSC into the Horizontal Storage Module (HSM). These configurations are not explicitly
analyzed in the Standardized NUHOMS 72-1004 FSAR. Title 10 of the Code of Federal
Regulations (CFR) 72.212 (b)(6), states, in part, that the general licensee must: review the
Safety Analysis Report referenced in the Certificate of Compliance (CoC) or amended CoC
and the related NRC Safety Evaluation Report, prior to use of the general license, to
determine whether or not the reactor site parameters, including analyses of earthquake
intensity and tornado missiles, are enveloped by the cask design bases considered in these
reports. The results of this review must be documented in the evaluation made in paragraph
(b)(5) of this section. Tornado hazards are evaluated in the Standardized NUHOMS 72-1004
FSAR section 3.2.1, Tornado and Wind Loadings, and section 8.2.2, Tornado
Winds/Tornado Missile. These sections of the FSAR do not include an analysis for tornado
hazards for these configurations. Additionally, the licensee did not have an evaluation
demonstrating the reactor site parameters enveloped the cask design basis for tornado
missiles.
Corrective Actions: The licensee entered the issue into its corrective action program to
address the actions specified in EGM 22-001. Specifically, the licensee established additional
measures that:
1.
mitigate tornado hazards, through procedures, during periods of ISFSI handling
operations which include:
a.
precluding outdoor dry cask storage activities during periods of adverse
weather
b.
establishing meteorological criteria and designating staff to monitor weather
during ISFSI handling operations
c.
Describing actions to take in the event of severe weather necessary to place
the cask in an analyzed condition
d.
Minimizing the duration of ISFSI handling operations during which ISFSI
important to safety SSCs are in an unanalyzed condition.
2.
document that required weather checks are complete prior to the start of ISFSI
handling operations
3.
document in the corrective action program (CAP) a request for the CoC holder to
request an amendment within six months of the date of the EGM.
Because the licensee implemented compensatory measures and plans to take necessary
actions to restore compliance in accordance with the EGM, the NRC is allowing continued
ISFSI handling operations.
Corrective Action References: AR 02428806
Enforcement:
Significance/Severity: The inspectors assessed the issue as being more than minor
significance but not more than Severity Level IV. Consistent with the guidance in EGM 22-
001 discussed below, the NRC is exercising enforcement discretion.
Violation: Title 10 of the Code of Federal Regulations (CFR) 72.212 (b)(6), states, in part,
that the general licensee must: review the Safety Analysis Report referenced in the CoC or
amended CoC and the related NRC Safety Evaluation Report, prior to use of the general
license, to determine whether or not the reactor site parameters, including analyses of
earthquake intensity and tornado missiles, are enveloped by the cask design bases
considered in these reports. The results of this review must be documented in the evaluation
made in paragraph (b)(5) of this section.
Contrary to the above, on May 19, 2022, the licensee did not have a documented evaluation
determining whether the reactor site parameters, including analyses of tornado missiles, were
enveloped by the cask design bases considered in the Safety Analysis Report. Specifically,
the licensee failed to have an analysis for tornado hazards when a loaded DSC with the
shield plug is transferred out of the Spent Fuel Pool to the Cask Handling Facility and when
the transfer cask lid is removed to insert the DSC into the HSM.
Basis for Discretion: Because this violation was identified during the discretion period
covered by Enforcement Guidance Memorandum 22-001, Enforcement Discretion for
Noncompliance of Tornado Hazard Protection requirements at Independent Spent Fuel
Storage Installations, and because the licensee was implementing compensatory measures
and has taken or plans to take the necessary actions to restore compliance, the NRC is
exercising enforcement discretion by not issuing an enforcement action for the violation and
is allowing continued ISFSI handling operations.
EXIT MEETINGS AND DEBRIEFS
The inspectors verified no proprietary information was retained or documented in this report.
On July 14, 2022, the inspectors presented the integrated inspection results to Nicole
Flippin and other members of the licensee staff.
On May 19, 2022, the inspectors presented the operation of an ISFSI inspection results
to Nicole Flippin and other members of the licensee staff.