ML18058B619
ML18058B619 | |
Person / Time | |
---|---|
Site: | Cook |
Issue date: | 02/27/2018 |
From: | Laura Smith NRC/RGN-III |
To: | |
References | |
IR 2018002 | |
Download: ML18058B619 (6) | |
See also: IR 05000316/2018002
Text
INSPECTION PLAN
DC Cook U2 - lnservice Inspection Activities
l.o
Inspection Report Numbe 50/31,.6- 2018002
Inspection Objectives/Focus
IP-71111.08- lnservice Inspection - This inspection fulfills the baseline inspection program
requirements for the biennial review of the inservice inspection (ISi) activities. The inspection
objectives are to verify that the program for monitoring degradation of the reactor coolant system
boundary, risk - significant piping system boundaries, and the containment boundary are
effective. This objective will be accomplished by direct observation of non-destructive
examinations, review of records and interviews of ISi personnel associated with inspection and
repair of Code components. The selection of components and level of effort will be aligned to
the extent practical with the percentages identified in each cornerstone identified for this
procedure.
Cornerstones: Initiating Events (50%), Barrier Integrity (50%).
Onsite Inspection Dates: March 5th 2018 - April 13th 2018
Inspection Procedures: IP 71111-08 - lnservice Inspection Activities
Prepared By
Approved By: u. "2-),27);
D. Hills, Branch Chief, DRS, EB1
t
Reviewed By: --,...-+-----* *__i_6_1_t1f
__ __
K."Riemer, Branch Chief, DRP, Branch 2
ADAMS Accession Number ML: 18058B619
INSPECTION PLAN DETAILS
I lnspectors: L Smith and M Holm a*4 .(.,r" PPL' ist""-r.
Rvû!c'rr4 Aelcq (¿r
ll lnspection Schedule
)
a lnformation Request lssue Date:
o January 10,2018.
o ln-Office Preparation Dates:
o February 26,2018 - March 2,2018
O Date for Ehtrance and Exit Meetings:
'
o Entrance - March 5,2011 - Monday.
o Exit - TBD (Dependent on baffle bolt status)
a Target for Draft Report lnput to Branch Chief:
o Two weeks post-exit.
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lll Specific Inspection Activities
tP7111108 Requirement Activity Review Targets
Section
02.01(a)-(c) Review a sample of nondestructive examination 31712018
(NDE) activities. The review sample should consist of:
1. 55499763-1 3 2-FW-78-09F PIPE TO PIPE 2 UT 3t7t18
(50 hrs)
55499763-1 3 2-FW-78-10S PIPE TO TEE 2 UT 3t7t18
Two or three types of NDE activities
2.
As a backup:
Order of preference for reviewed NDE
3t8t2018
activities:
(a) Volumetric examinations 55499766-06 2-RC-28-16 PIPE TO ELBOW 1 UT 3t8t18
(b) Surface examinations 55499766-06 2-RC-28-17 ELBOW TO PIPE 1 UT 3t8t18
(c) Visual examinations
3t16t18 VT-3
For each NDE activity reviewed, perform the
55467355-04 PERFORM BAFFLE Edge bolts 16-Mar-18 16-Mar-18
following through either direct observation (preferred w-3 04:00 22:OO
method) or record review:
1. Verify that the activities are performed in
accordance with ASME Boiler and Pressure Vessel
Code requirements or industry augmented inspection
requirements.
2. Verify that indications and defects, if present,
are appropriately dispositioned in accordance with the
ASME Code, licensee procedures and NRC
requirements.
02.01d Review one or two surface or volumetric examinations None identified by the licensee.
from the previous outage with recordable indications
(0hrs) that have been accepted by the licensee for continued
service. Verify that the licensee's acceptance for
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continued service was appropriate, and in accordance
with the ASME Code or NRC approved alternative.
02.01e lf applicable, for modifications, repairs, or
wo# Description and weld numbers
replacements consisting of welding on pressure
55503076-0r 2-WPX-736-V1 Replace valve/Pipe
(16 hrs) boundary risk significant systems, verify for one to
three welds that the welding activities, and any
applicable NDE performed, were performed in
accordance with ASME Code requirements, or an
N RC approved alternative.
02.02 PWR Upper Head Penetration lnspection Alloy 690 Replaced Head. No Head lnspections required this outage
Licensee has scheduled a bare metalvisual and
0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> nonvisual examination of the reactor vessel head.
a. For these exams, inspectors will review the
examination procedure; and either observe portions of
these examinations, and/or review the post
examination records to confirm they are consistent
with Code Case N-7294 and 10 CFR
50.55a(s)(6XiiXD)
lf welding repairs are needed and completed on
upper head penetrations, the inspectors will review a
sample of these repairs. Verify that the welding
process and welding examinations were performed in
accordance with ASME Code requirements and 10
CFR 50.55a(gX6XiiXD) or an NRC approved
alternative.
Boric Acid Corrosion Control (BACC) lSl
02.03 lnterview resident inspectors to get insights from their observations of BACC
walkdowns.
(6hrs) a. (Resident lnspectors) Review a sample of
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Boric Acid Corrosion Control (BACC)walkdown visual Look for boric acid deposits during NDE observations in containment. Confirm
examination activities through direct observation. licensee has identified and documented boric acid leaks and perform reviews
b. Verify that visual inspections emphasizes of site procedures and review site evaluations of components affected by boric
acid.
locations where boric acid leaks can cause
deg radation of safety sig n ificant com ponents.
Selected samples from condition reports (ARs) related to boric acid leakage to
c. Review one to three engineering followup on licensee evaluations and corrective actions.
evaluations performed for oric acid found on RCS
piping and components. ln addition, verify that
degraded or non-conforming conditions are identified
properly in licensee in licensee's corrective action
system.
d. Review one to three corrective actions
performed for evidence of boric acid leaks identified, if
available during the time frame of this inspection.
Confirm that these corrective actions were consistent
with requirements of the ASME Code and l0 CFR 50
Appendix B Criterion XVl.
02.04 Steam Generator (SG) Tube lSl No steam generator tube inspections are planned
Verify that qualified equipment is used for the active or
(0 hrs) anticipated tube damage mechanisms. Verify that
examination scope is consistent with TS and EPRI
guidance. Verify that licensee is applying appropriate
screening criteria on degraded tubes that could
challenge the SG tube performance criteria. (i.e.,
operational leakage, structural integrity, or accident
leakage). Observe any tubes which require pressure
testing. Review any trends for primary-to-secondary
leakage, or reported potential degraded condition due
to SG design, water chemistry, material properties, or
newly identified degradation mechanisms.
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02.05 ldentification and Resolution of Problems.
(26 hrs) Verify that the licensee is identifying lSl problems Observe sample of baffle former bolt replacement activities.
at an appropriate threshold and entering them in the
Review a sample of corrective action records related to lSl, foreign materials
corrective action pro!ram. Determine whether the
intrusion into safety related systems, or materials degradation of code
licensee's procedures direct the licensee to perform a
components. The inspectors review will include site evaluation of operating
root cause evaluation and take corrective actions
when appropriate. For a selected sample of problems
experience related to baffle-former bolts and a copy of the proposed or
associated with inservice inspection and steam completed corrective actions records associated with these evaluations. ln
generator inspection documented by the licensee, particular, cook u2 is a tier 1 plant (Highest susceptibility bin) with type 347 SS
verify the appropriateness of the corrective actions. bolts operated in the down-flow configuration as identified in Nuclear Safety
See lnspection Procedure 71152, "ldentification and Advisory Letter (NSAL)-16-1 "Baffle-Former Bolts." The inspectors will review
Resolution of Problems," for additional guidance. ln to determine if the licensee has evaluated the NSAL-16-1 and has taken or
addition, a licensee's evaluation of industry operating assigned actions consistent with this document.
experience can be critical. Determine whether
The inspectors will document this review and the results in accordance with the
licensees are correctly assessing the applicability of
operating experience to their respective plants.
latest revision to the lSl template. Review corrective actions for defective baffle
former edge bolts and the baffle assembly upflow conversion.
Total 98
hrs
lV) Gompletion Status
The baseline lSl procedure 71 1 1 108 will be completed for Unit 2 with one sample as defined by reviews above
v) Resource Estimate lP 71111 08 reviews will take approximately 98 hours0.00113 days <br />0.0272 hours <br />1.62037e-4 weeks <br />3.7289e-5 months <br />, but is highly variable based on logistical challenges in observing
these examinations and the additional scope necessary to cover baffle former bolt repairs which will likely result in exceeding the upper end
of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> identified within this lP Overtime will be requested and likely needed to support observation of examinations outside scheduled
work hours.
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