ML18058B619

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Inspection Plan for Donald C. Cook, Unit 2, for Inservice Inspection Activities; Inspection Report 05000316/2018002 (DRS-L.Smith)
ML18058B619
Person / Time
Site: Cook American Electric Power icon.png
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

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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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