ML16123A331
| ML16123A331 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 05/02/2016 |
| From: | Dave Hills NRC/RGN-III/DRS/EB1 |
| To: | Boles B FirstEnergy Nuclear Operating Co |
| References | |
| IR 2016007 | |
| Download: ML16123A331 (12) | |
See also: IR 05000346/2016007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
May 2, 2016
Mr. Brian D. Boles
Site Vice President
FirstEnergy Nuclear Operating Co.
Davis-Besse Nuclear Power Station
5501 N. State Rte. 2, Mail Stop A-DB-3080
Oak Harbor, OH 43449-9760
SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION - POST-APPROVAL SITE
INSPECTION FOR LICENSE RENEWAL REPORT 05000346/2016007
Dear Mr. Boles:
On April 8, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed the outage
segment of the Post-Approval Site Inspection for License Renewal at your Davis-Besse Nuclear
Power Station. The enclosed report documents the results of this inspection, which were
discussed on April 8, 2016, with Mr. B. Kremer and other members of your staff.
This inspection was an examination of activities conducted under your renewed license as they
relate to the completion of commitments made during the renewed license application process
and compliance with the Commissions rules and regulations and the conditions of your
operating license. Within these areas, the inspection involved examination of selected
procedures and representative records, observations of activities, and interviews with
personnel. On the basis of the sample selected for review, there were no findings of
significance identified during this inspection.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public
Inspections, Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy
of this letter, its enclosure, and your response (if any) will be available electronically for public
inspection in the NRCs Public Document Room or from the Publicly Available Records (PARS)
component of the NRC's Agencywide Documents Access and Management System (ADAMS).
ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html
(the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-346
License No. NPF-3
Enclosure:
cc w/encl: Distribution via LISTSERV
Enclosure
U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Docket No:
50-346
License No:
Report No:
Licensee:
FirstEnergy Nuclear Operating Company
Facility:
Davis-Besse Nuclear Power Station
Location:
Oak Harbor, OH
Dates:
March 28 - April 8, 2016
Inspectors:
S. Sheldon, Senior Reactor Engineer (Lead)
T. Bilik, Senior Reactor Engineer
Approved by:
D. Hills, Chief
Engineering Branch 1
Division of Reactor Safety
2
SUMMARY
Inspection Report 05000346/2016007, 03/28/2016 - 04/08/2016; Davis-Besse Nuclear Power
Station; Post-Approval Site Inspection for License
The inspection was conducted by two regional based inspectors. No instances were noted
of incomplete license renewal commitments with respect to timeliness or adequacy. No
findings were identified by the inspectors. The significance of inspection findings is indicated
by their color (i.e., greater than Green, or Green, White, Yellow, Red) and determined using
Inspection Manual Chapter 0609, "Significance Determination Process," dated April 29, 2015.
Cross-cutting aspects are determined using Inspection Manual Chapter 0310, "Aspects Within
the Cross-Cutting Areas," dated December 4, 2014. All violations of U.S. Nuclear Regulatory
Commission (NRC) requirements are dispositioned in accordance with the NRCs Enforcement
Policy, dated February 4, 2015. The NRC's program for overseeing the safe operation of
commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process,"
dated February 2014.
No findings were identified.
3
REPORT DETAILS
Summary of Plant Status
The unit was in a refueling outage during the period of this inspection.
4.
OTHER ACTIVITIES
4OA5 Other Activities
.1
Post-Approval Site Inspection for License Renewal (Phase I) - Inspection
Procedure 71003
a.
Inspection Scope
(1) Review of Newly Identified Systems, Structures and Components
The inspectors discussed the identification of new systems, structures, and components,
under the purview of Title 10 of the Code of Federal Regulations (CFR), Part 54.37(b),
with the licensees license renewal staff. The licensee personnel indicated that no new
components have been identified to date that should have been within the scope of the
License Renewal Program.
(2) Review of Revised Commitments
Based on discussion the inspectors had with licensee staff, at the time of the inspection
there were no revised commitments.
(3) Review of Commitments
The inspectors reviewed supporting documents including completed surveillance
records, conducted interviews, observed non-destructive examination activities,
performed visual inspection of structures and components, including those not
accessible during power operation, and observed the activities described below
that the licensee completed to comply with the license conditions associated with
the renewed operating license. The inspectors verified the licensee implemented
the outage-related Aging Management Programs included in, Safety Evaluation
Report Related to the License Renewal of Davis-Besse Nuclear Power Station,
dated September 2013 (ML13248A267) in accordance with 10 CFR Part 54,
Requirements for the Renewal of Operating Licenses for Nuclear Power Plants.
b.
Findings and Observations
The inspectors reviewed portions of the activities listed below, which are referenced
to the Aging Management Programs from the licensees License Renewal Application
(LRA) and the commitments noted in Appendix A of the Safety Evaluation Report where
applicable. Activities observed related to these commitments are also listed.
(1) (B.2.8) Closed Cooling Water Chemistry Program (Commitment Item 32)
The Closed Cooling Water Chemistry Program is intended to mitigate damage due to
loss of material, cracking, and reduction in heat transfer of components that are within
the scope of license renewal and contain closed cooling water. The program manages
4
the relevant conditions that could lead to the onset and propagation of a loss of material,
cracking, or reduction in heat transfer through proper monitoring and control of corrosion
inhibitor concentrations consistent with the current Electric Power Research Institute
water chemistry guideline.
Commitment item 32 states the licensee will make the following enhancements to the
Closed Cooling Water Chemistry Program prior to October 22, 2016:
Document the results of periodic inspections of opportunity, performed when
components are opened for maintenance, repair, or surveillance;
Ensure that a representative sample of piping and components will be inspected on
a 10-year interval, with the first inspection taking place prior to entering the period of
extended operation; and
Ensure that component cooling water radiochemistry is sampled on a weekly interval
to verify the integrity of the letdown coolers and seal return coolers.
The inspectors reviewed records from a sample of completed inspections. Specific
records are listed in the list of documents reviewed. The inspectors identified no
concerns with these inspections.
The inspectors also observed the licensee perform a visual examination (VT-1,
direct/remote using video probe) of CC-150 valve and adjacent piping, for component
cooling water to decay heat pump 2 alternate source, per Work Order (WO) 200638210.
The inspectors had no concerns with the observed activities.
(2) (B.2.23) Inservice Inspection Program - IWF (Commitment Item 50)
The Inservice Inspection (ISI) Program - IWF establishes responsibilities and
requirements for conducting American Society of Mechanical Engineers (ASME)
Code Section XI, Subsection IWF inspections as required by 10 CFR 50.55a. The
ISI Program - IWF includes visual examination for supports based on sampling of the
total support population. The sample size varies depending on the ASME class.
Commitment item 50 states the licensee will make numerous enhancements to the
ISI Program - IWF prior to October 22, 2016.
The inspectors observed the licensee perform VT-3 direct visual examinations of
DG-JKY WTR HTXCHR-1-1-AW, diesel generator jacket water heat exchanger E10-1
supports, per WO 2000616036. One of the examiners failed to properly perform the
ASME Code required illumination verification check. The exams were concurrently
performed by another examiner who found no recordable indications. The licensee
captured this issue in CR-2016-04439. Except for the minor issue noted, the inspectors
had no concerns with the observed activities.
5
(3) (B.2.24) Inservice Inspection Program
The ISI Program manages cracking of reactor coolant pressure boundary components
and once-through steam generator secondary side components. The program includes
periodic visual, surface, or volumetric examination and leakage (pressure) testing of
ASME Class 1, 2, or 3 components, and their integral attachments, as well as repair,
modification, or replacement of same.
The inspectors observed ultrasonic examination of reactor coolant pump cover to case
studs, RC-RCP-1-1-1-STUDS; per WO 200616040, and RC-30-CCA-8-1-SWB through E,
per WO 200629210. The inspectors also observed dye penetrant examinations of reactor
coolant system (RCS) pipe-to-elbow weld, RC-CCA-23-S-CV030, per WO 20061038, and
RCS pipe-to-elbow weld, RC-MK-A-93-SW51, per WO 200616038. The inspectors had
no concerns with the observed activities.
(4) (B.2.28) Nickel-Alloy Management Program (Commitment Item 49)
The Nickel-Alloy Management Program manages primary water stress corrosion
cracking and stress corrosion cracking/intergranular attack for nickel-alloy pressure
boundary components, other than reactor vessel closure head nozzles and steam
generator tubes, exposed to reactor coolant. Mitigative actions include replacement
of Alloy 600/82/182 components with materials known to be less susceptible to primary
water stress corrosion cracking and stress corrosion cracking/intergranular or repair of
those components through weld overlay, weld inlay (also known as weld underlay),
mechanical stress improvement process or surface conditioning. The condition
monitoring portion of the program uses a number of inspection techniques to detect
cracking, including volumetric and bare metal visual examinations.
Commitment item 49 states the licensee will enhance the Nickel-Alloy Management
Program to:
Provide for inspection of dissimilar metal butt welds in accordance with the
requirements of ASME Code Case N-770-1, Alternative Examination Requirements
and Acceptance Standards for Class 1 PWR [Power Water Reactor] Piping and
Vessel Nozzle Butt Welds fabricated with UNS N06082 or UNS W86182 Weld Filler
Material With or Without Application of Listed Mitigation Activities,Section XI,
Division 1, as modified by the 10 CFR 50.55a(g)(6)(ii)(F).
The inspectors observed a manual phased array ultrasonic examination of a RCS
10 branch connection-to-pipe overlay, per WO 200616038. The inspectors had no
concerns with the observed activities.
(5) (B.2.30) One-Time Inspection Program (Commitment Item 13)
The One-Time Inspection Program is a new program that is intended to provide
assurance that aging which has not yet manifested itself is indeed not occurring, or
that the age-related degradation is so insignificant that an Aging Management Program
is not warranted.
6
The inspectors observed the licensees activities to implement Commitment Item 13, of
the license renewal Safety Evaluation Report. This commitment documents the licensee
will implement the One-Time Inspection Program, as described in LRA Section B.2.30,
prior to October 22, 2016.
The inspectors observed the licensee perform a visual examination of MS891A Steam
Generator 2 Drain Line valve per WO 200635583, MS109A, MS109B Main Steam
System Pressure Indicator Valves per WO 200631009, the fuel transfer tube 2 isolation
valve per WO 200636246, and the FW145 Steam Generator 1 Feedwater Header Vent
per WO 200639572. The inspectors had no concerns with the observed activities. The
inspectors reviewed a sample of completed inspections. Specific records are listed in
the list of documents reviewed.
The licensee stated that overall results will be evaluated once all of the inspections
have been completed. This evaluation should be reviewed during the 71003 Phase II
inspection.
(6) (B.2.31) Open-Cycle Cooling Water Program
The Open-Cycle Cooling Water Program manages loss of material due to crevice,
galvanic, general, pitting, and microbiologically-influenced corrosion, and also due to
erosion for components located in the Service Water (SW) System, and for components
connected to or cooled by the SW System, and also in the Circulating Water System.
The program also manages fouling due to particulates (e.g., corrosion products) and
biological material (micro- and macro-organisms) resulting in reduction in heat transfer
for heat exchangers within the scope of the program. The program includes of
inspections, surveillances, and testing to detect and evaluate fouling, loss of material,
combined with chemical treatments and cleaning activities to minimize fouling and loss
of material.
The inspectors observed visual inspection of the SW cross tie to auxiliary feedwater per
WO 200606738 including records of as found condition and direct observation of as left
condition. During a direct visual inspection, an NRC inspector observed a section of
pipe that still had a thick layer of silt and tubercles. The inspector conveyed this
observation to the licensee, and in response, the licensee initiated CR 2016-04754,
SW261 Clean/Inspect piping - NRC inspectors post cleaning piping walkdown
observed that the SW piping segment had not yet been cleaned. The licensee
subsequently cleaned the pipe before reassembly. Except for the work in progress
issue noted, the inspectors had no concerns with the observed activities.
(7) (B.2.37) Small Bore Class 1 Piping Inspection (Commitment Item 19)
The Small Bore Class 1 Piping Inspection is intended to detect and characterize
cracking of small bore ASME Code Class 1 piping less than 4 inches nominal pipe size
(NPS 4), which includes pipe, fittings, and branch connections. The inspection will
consist of volumetric examination of a representative sample of small bore piping
locations that are susceptible to cracking. The inspection sample includes both socket
Commitment item 19 states the licensee will implement the Small Bore Class 1 Piping
Inspection, as described in LRA Section B.2.37, prior to October 22, 2016.
7
The inspectors observed phased array volumetric inspections of 1 elbow-to-pipe RC
welds RC-FSK-M-CCA-19-1-24a and RC-FSK-M-CCA-19-1-29, and pipe-to-elbow weld
RC-FSK-M-CCA-19-1-23a, per WO 200629207.
The inspectors had no concerns with the observed activities.
(8) B.2.39 Structures Monitoring Program (Commitment Item 20)
The Structures Monitoring Program is part of the Maintenance Rule Program. It is
an existing program that is designed to ensure age-related degradation of the plant
structures and structural components within its scope are managed such that each
structure and structural component retains the ability to perform its intended function.
The program includes period inspections of structures.
Commitment item 20 states the licensee will make numerous enhancements to the
Structures Monitoring Program prior to October 22, 2016.
The inspectors observed visual inspection of the auxiliary building, 643 elevation
main steam pipe rooms 601 and 602 in accordance with EN-DP-01511, Structures
Monitoring. The inspectors had no concerns with the observed activities.
(9) Service Level III Coatings and Linings Monitoring Program (Commitment Item 51)
The Service Level III Coatings and Linings Monitoring Program is a plant-specific
condition monitoring program for Davis-Besse. The program consists of periodic visual
inspections of all Service Level III coatings and linings on the internal surfaces of piping,
piping components, and tanks in mechanical fluid systems that are within the scope of
license renewal. The program includes organic (e.g., elastomeric or polymeric) and
inorganic (e.g., zinc-based) coatings and linings (e.g., rubber, cementitious).
The program is intended to manage loss of coating integrity due to blistering, cracking,
flaking, peeling, delamination, or physical damage of coatings and linings to ensure
that degradation does not result in loss of intended function due to unanticipated or
accelerated corrosion or flow blockage of in-scope mechanical components.
Commitment item 32 states the licensee will implement the Service Level III Coatings
and Linings Monitoring Program prior to October 22, 2016.
The inspectors observed visual inspection of the SW60 containment air cooler service
water header cross connect butterfly valve (WO 200423706). The inspectors had no
concerns with the observed activities.
4OA6 Management Meetings
.1
Exit Meeting Summary
April 8, 2016 the inspectors presented the inspection results to Mr. B. Kremer and
other members of your staff. The licensee acknowledged the issues presented.
The inspectors confirmed that none of the potential report input discussed was
considered proprietary.
ATTACHMENT: SUPPLEMENTAL INFORMATION
Attachment
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee
B. Boles, Site Vice President
D. Saltz, Plant Manager
K. Zellers, License Renewal Project Manager
S. Dort, Aging Management Coordinator
G. Clark, License Renewal
C. Daft, License Renewal
D. Munson, License Renewal
A. Scheanwald, ISI Program Owner
G. Wolf, Regulatory Affairs
LIST OF ITEMS OPENED, CLOSED AND DISCUSSED
Opened, Closed and Discussed
None
LIST OF ACRONYMS USED
Agencywide Documents Access and Management System
American Society of Mechanical Engineers
CFR
Code of Federal Regulations
Inservice Inspection
NRC
U.S. Nuclear Regulatory Commission
Publicly Available Records System
Work Order
2
LIST OF DOCUMENTS REVIEWED
The following is a partial list of documents reviewed during the inspection. Inclusion on this list
does not imply that the NRC inspector reviewed the documents in their entirety, but rather that
selected sections or portions of the documents were evaluated as part of the overall inspection
effort. Inclusion of a document on this list does not imply NRC acceptance of the document or
any part of it, unless this is stated in the body of the inspection report.
Condition Reports Initiated During the Inspection
- CR 2016-04754; SW261 Clean/Inspect piping - NRC inspectors post cleaning piping
walkdown observed that the SW piping segment had not yet been cleaned; dated 04/06/16
- CR-2016-04439; NRC Observation of Visual Examination Acuity Verification; dated 04/02/16
Completed Work Orders and Inspections
- 200499963; Auxiliary Building Room 601 4" Floor Drain (TDF-4-1) A-2356 (601F-95);
dated 05/06/15
- 200542646; SBO DG Primary Fuel Filter; dated 02/16/15
- 200630441; MDFP Lube Oil Filter Housing; dated 09/09/15
- 200631602; Boric Acid Evaporator 1 Outlet To Condensate Tank Steam Trap Body;
dated 12/02/15
- BOP-VT-15-115; E144-2 (Post-Accident Sample Cooler 1-2); dated 08/18/15
- BOP-VT-15-177; SH289 & HX Tubing (Radwaste Heating Coil Inlet Isolation); dated 09/30/15
- BOP-VT-15-201; P95, SH326 (Secondary Hot Water Fuel Handling Pump); dated 10/08/15
- BOP-VT-15-220; Emergency Diesel Generator 1-2 Lube Oil Heat Exchanger; dated 11/09/15
- BOP-VT-15-227; FE1476 (DG Jacket Cooling Water HX 2 CC Outlet Flow Element);
dated 11/10/15
- BOP-VT-15-256; AC302 Computer Room AC Inlet Valve; dated 12/07/15
- BOP-VT-16-031; CC496A (Reactor Coolant Pump 2-2 Pump Seal CCW Return Line Vent);
dated 03/31/16
- BOP-VT-16-032; CC496 (Reactor Coolant Pump 2-2 Pump Seal CCW Return Line Vent);
dated 03/31/16
- BOP-VT-16-033; CC494 (Reactor Coolant Pump 2-2 Pump Seal CCW Supply Line Drain);
dated 03/31/16
- BOP-VT-16-034; CC494A (Reactor Coolant Pump 2-2 Pump Seal CCW Supply Line Drain);
dated 03/31/16
- SW256-2016; DB-SW256; dated 03/30/16
- SW60-2016; DB-SW60; dated 03/31/16
- BOP-VT-16-059; FW145 SG 1 Feedwater Header Vent; dated 04/04/16
- BOP-UT-16-019; SW261; dated 04/07/16
- BOP-VT-16-043; Fuel Transfer Tube 2 Isolation Valve; dated 04/01/16
Miscellaneous
- DBRM-ER-0001; One-Time Inspection Program Components; Rev. 00
- Structures Monitoring Inspection Worksheet; auxiliary building, 643 elevation, rooms 601 and
602; dated 04/07/16
- ACI 349.3R-02; Evaluation of Existing Nuclear Safety-Related Concrete Structures
3
Observed Inspections
- WO 200635583; MS891A Steam Generator 2 Drain Line; dated 03/30/16
- WO 200631009; MS109A, MS109B Main Steam System Pressure Indicator Valves;
dated 03/30/16
- WO 200423706; SW60 Containment Air Cooler Service Water Cross Connect Valve;
dated 03/31/16
- WO 200636246; Fuel Transfer Tube 2 Isolation Valve; dated 04/01/16
- WO 200639572; FW145 SG 1 Feedwater Header Vent; dated 04/04/16
- WO 200606738; Service Water Cross Tie to AFW; dated 04/05/16
Procedures
- 54-ISI-369-003; VT-1, VT-3, General and Detailed Visual Examinations; Rev. 3
- 54-ISI-615-001; Procedure for Manual and Semi-Automated Phased Array Ultrasonic
Examination of Socket Fillet Welds; Rev. 1
- 54-ISI-864-003; Manual Phased Array Ultrasonic Examination of Weld Overlaid Similar and
Dissimilar Metal Welds; Rev. 3
- 54-ISI-864-005; Manual Phased Array Procedure for Weld Overlaid Similar and Dissimilar
Metal Welds; Rev. 5
- EN-DP-01511; Structures Monitoring; Rev. 04
- EN-DP-01515; Service Level III Coatings and Linings Condition Assessment Inspection;
Rev. 00
- NA-QC-05560; Visual Examination Procedure for VT-1, VT-3, and General Visual
Examinations; Rev. 11
- NG-EN-00551; Service Level III Coatings and Linings Monitoring Program; Rev. 00
- NG-EN-00552; One-Time Inspection Program; Rev. 00
- NOP-ER-2006; Service Water Reliability Management Program; Rev. 02
- Program Basis Documents
- LRPD-05 Att 2.16; Service Level III Coatings and Linings Monitoring Program; Rev. 1
- LRPD-05 Att 2.11; One-Time Inspection Program; Rev. 7
- LRPD-05 Att 2.6b; Closed Cooling Water Chemistry Program; Rev. 4
- LRPD-05 Att 2.12; Open-Cycle Cooling Water Program; Rev. 3
Mr. Brian D. Boles
Site Vice President
FirstEnergy Nuclear Operating Co.
Davis-Besse Nuclear Power Station
5501 N. State Rte. 2, Mail Stop A-DB-3080
Oak Harbor, OH 43449-9760
SUBJECT: DAVIS-BESSE NUCLEAR POWER STATION - POST-APPROVAL SITE INSPECTION FOR
LICENSE RENEWAL REPORT 05000346/2016007
Dear Mr. Boles:
On April 8, 2016, the U.S. Nuclear Regulatory Commission (NRC) completed the outage segment of the
Post-Approval Site Inspection for License Renewal at your Davis-Besse Nuclear Power Station. The
enclosed report documents the results of this inspection, which were discussed on April 8, 2016, with Mr.
B. Kremer and other members of your staff.
This inspection was an examination of activities conducted under your renewed license as they relate to
the completion of commitments made during the renewed license application process and compliance
with the Commissions rules and regulations and the conditions of your operating license. Within these
areas, the inspection involved examination of selected procedures and representative records,
observations of activities, and interviews with personnel. On the basis of the sample selected for review,
there were no findings of significance identified during this inspection.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR) 2.390, Public Inspections,
Exemptions, Requests for Withholding, of the NRC's "Rules of Practice," a copy of this letter, its
enclosure, and your response (if any) will be available electronically for public inspection in the NRCs
Public Document Room or from the Publicly Available Records (PARS) component of the NRC's
Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the
NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
David E. Hills, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 50-346
License No. NPF-3
Enclosure:
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OFFICE
RIII
RIII
RIII
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NAME
SSheldon:cl
DHills
DATE
04/29/16
05/02/16
OFFICIAL RECORD COPY