IR 05000306/1998021
| ML20198H797 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 12/17/1998 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20198H790 | List: |
| References | |
| 50-306-98-21, NUDOCS 9812300019 | |
| Download: ML20198H797 (10) | |
Text
..
. _. -
___....___ _.
. -. _
.-
. _ _..
.....
_ _. _.. _. _ -.. _ _ _. _..
,
[
' -
\\
.
,
U.S. NUCLEAR REGULATORY COMMISSION
REGION 111
Docket No.:
50-306 License No.:
,
i Report No.:
50-306/98021(DRS)
'
Licensee:
Northern States Power Company Facility:
Prairie Island Nuclear Generating Plant Location:
1717 WUonade Drive East Welch, MN 55089 L
Dates:
November 16-20, 23-24,1998 i
Inspector:
D. E. Jones, Reactor Inspector
. Approved by:
James A. Gavula, Chief, Engineering Specialists Branch 1 Division of Reactor Safety l
l
.
i
!
!
!
i l
s s
l'
9812300019 981217 PDR ADOCK 05000306 G
PDR s-
.-
-.
..... -
-.
..,- -.
~ - -
. -.. -.
. -.. -. _ _
- _..
-
l.
'
EXECUTIVE SUMMARY l
'
Prairie Island Nuclear Power Station, Unit 2 NRC Inspection Report 50-306/98021 This inspection included a review of the implementation of the inservice inspection (ISI) program for the Prairie Island refue!!ng outage cycle 19. The report covers on-site inspection by a
,
l regionalinspector, l
,
l Maintenance:
,
{
l Nondestructive examinations were performed in accordance with applicable procedures.
The ISI data evaluation and review was timely and accurate. Overall, the ISI program l --
was implemented in an effective manner with excellent engineering involvement in the
'
oversight of the ISI activities. (Section M1.1)
Nondestructive examinations were conducted in accordance with the appropriate
procedures and ISI program. The licensee's ISI program implementation met ASME f
Code requirements. (Section M3.1)
l Nondestructive examination was performed by qualified personnel. (Section MS.1)
'
L i
l
,
l
!
l
,'
<
l l
,
.. _
... _
_
_ - _
__... _...
.. - _ _. _ _ _ _ _ _ _ _ _. _ _. _ _ _. _.
'
i:
-
l
l Report Details i:
II. Maintenance
!
M1 Conduct of Maintenance -
,
l l
M1.1 Inservice insoection (ISI)
a.
Inspection Scope (73753 and 73755)
The inspector observed ISI examinations and reviewed ISI examination data packages
)
to assure appropriate examination was performed and data was recorded as required by
' ;
l the ASME Code.
b.
Observations and Findinos The inspector observed all or portions of the following nondestructive examination (NDE)
activities:
'
e i
Ultrasonic testing of pressurizer surge line nozzle-to-pipe welds 1 and 2 e
(ISO # 2-ISI-31).
Ultrasonic testing of main steam loop A welds 1 and 2 (ISO # 2-ISI-46A)
Eddy current data acquisition of hot and cold leg tubes of steam generators (SG)
L
21 and 22
,
,
'
'
e Wire brushing and tube rolling of SGs 21and 22 Ultrasonic testing of reactor vesselloops A and B hot leg outlet nozzles welds N7 e
and N10 i
!
e Visual examination of reactor vessel upper internal components
'
i The SG eddy current examination inspection scope included 100% bobbin coil examination of all open tubes,100% plus point coil examination of the hot leg tubesheet area,100% of the dented intersections with plus point, row 1 and 2 U-bends,100% of the hot and cold leg inconel 600 rolled plugs, and 25% of hot leg inconel 690 rolled
. plugs.
In situ pressure testing of 10 tubes (3 in SG 21, and 7 in SG 22) was conducted for condition monitoring assessment. This process provided reasonable assurance that indications left in service would be able to withstand the loadings specified in L
Regulatory Guide 1.121 for the operating interval between inspections. No leakage was
identified from the 10 tubes tested. There were a total of 22 plugs installed (10 in SG 21, l-and 12 in SG 22), and 365 tubes rolled (204 in SG 21, and 161 in SG 22).
i.
l
_
.
__
.
.
.
._
-__
- _ _ _.
.
._ _ _ _ _ _ _
_ _ _ _. _ _ _ _ __
L
,
.
,
The inspector determined that the NDE data packages were properly reviewed by the licensee and the Authorized Nuclear Inservice inspector (ANil). Ultrasonic indications recorded on the data sheets were also properly eva_luated. The inspector also reviewed certifications for equipment and consumable materials associated with these examinations. The NDE data packages, and equipment and consumable material certification records were found to be complete and accurate.
Excellent contractor oversight was noted in the management of the ISI contractors.
Each NDE contractor was assigned a licensee engineer to provide coordination and l
oversight of the inspection activities. The inspector observed good interaction between i
the licensee and contractor NDE personnel during the eddy current examination of the steam generators and the reactor vessel interior visual examination.
c.
Conclusions l
Nondestructive examinations were performed in accordance with applicable procedures, i
The ISI data evaluation and review was timely and accurate. Overall, the ISI program was implemented in an effective manner with excellent engineering involvement in the oversight of the ISI activities.
l M3 Maintenance Procedures and Documentation
!
M3.1 Prooram and Procedure Review a.
Inspection Scoce (73051. 73052)
The inspector reviewed the ISI program and its implementation for compliance with Technical Specifications, ASME Code and NRC requirements.
b.
Observations and Findinas The inspector reviewed the licensee's third ten-year ISI program plan, " Inservice Inspection Examination Plan". Revision 1, effective December 21,1994 through December 20,2004. All ISI procedures reviewed were found to be in accordance with ASME Code,Section V and XI,1989 Edition requirements. Examinations were performed in accordance with the Technical Specifications, the ASME Code,Section XI and Generic Letter 95-03 "Circumferential Cracking of Steam Generator Tubes." Where ASME requirements were determined to be impractical, specific relief requests were submitted to Nuclear Reactor Regulation in writing. The licensee had requested relief from ASME Code requirements for the use of existing calibration blocks (Relief Request 7, conditionally approved on February 22,1996).
The licensee procured the services of an ANil from Hartford Steam Boiler Inspection and insurance Co. of Hartford, Connecticut. The ANil reviewed procedures, personnel qualifications, instrument and material certifications, and examination results. The NRC inspector's review indicated that the ISI program was acceptable.
.
_
_ _ _ _
._
.
_ _ _.
_ _ _
. _ _ _ _ _ _ __
_
_ _ _.
.
c.
Conclusions i
Nendestructive examinations were conducted in accordance with the appropriate
'
procedures and ISI program. The licensee's ISI program implementation met ASME Code requirements.
MS Maintenance Staff Training and Qualification M5.1 ISI Personnel Qualifications l
a.
Inspection Scope (73753)
The inspector reviewed ISI personnel qualifications of licensee and contract personnel performing the ISI activities observed in Section M1.
b.
Observations and Findinos Qualification of personnel performing NDE work was verified. NDE personnel were j
knowledgeable of procedural requirements and proficient in the performance of NDE.
Personnel performing NDE were found to have proper qualifications which had been reviewed and accepted by the licensee staff and the ANil.
' c.
Conclusions q
NDE was performed by qualified personnel.
M8 Miscellaneous Maintenance issues (92902)
j M8.1 (Closed) VIO 50-282/97003-01(a)(b)(DRS): 50-306/97003-01(a)(b)(DRS): Failure to obtain Code relief pursuant ta 10 CFR 50.55 (g) and Technical Specification 4.2 for welds associated with reactor vessel and inservice examinations. The licensee responded to the Notice of Violation (Notice) by letter dated April 14,1997. The inspector confirmed that the corrective actions referenced in the licensee's response to the Notice were being implemented. The licensee issued procedure ISI-LTS-1,
" Limitations to NDE," which provides instruction for identifying, quantifying and recording of limitations encountered while performing examinations under the ISI program.
L Paragraph 7.7 of the procedure stated that when the maximum examination coverage practically achievable for a code required item was less than required; a relief request
was required to be submitted to the NRC. In addition, the licensee has submitted a relief request following the Unit 1 outage and review of first period,3rd intervallimited
'
examinations.
!
l
!
l i
.
_.,
_.
.
.
.
..... _. _ _ -. _ _. _. - _. _.. _.... ~ _
_. _.
_.. ~.. _ _... _
i
-
,
V. Manaaement Meetinas X1<
Exit Meeting Summary
l The inspector presented the inspection results to a member of licensee management at the
,
conclusion of the inspection on November 24,1998.- The licensee acknowledged the findings presented and did not identify any of the potential report input discussed as proprietary.
,
..
'l l
'
l l
v.-
..
,.
,
PARTIAL LIST OF PERSONS CONTACTED i
Northern States Power Comoany (NSP)
- K. Albrecht, Engineering Manager
- P. Hajovy, Plant ISI Coordinator
- R. Pearson, Steam Generator Manager
- S. Redner, NDE Consulting Specialist
'
- J. Ricker, Superintendent, Materials and Special Processes
- J. Sorenson, Plant Manager Lambert MacGill Thomas. Ing.
D. Halling, Lead l
Framatone. Inc.
B. Grisham, Lead Wes Dyne D. Kurek, Level ill ABB CE B. Smith, Lead U.S. Nuclear Reaulatory Commission (NRC)
- P. Krohn, Resident inspector S. Ray, Senior Resident inspector S. Thomas, Resident inspector Hartford Steam Boiler Inspection and Insurcnce Company (HSB)
L. Dillon, ANil
- Denotes those present during the exit interview on November 24,1998.
.-
.
-
.... -.
~.
..
........_ -.
..
...
-
.-
,.
INSPECTION PROCEDURES USED
,
IP.73753 Inservice inspection l
l lP 73051 Inservice inspdction-Review of Program.
j
.
IP 73052 Inservice Inspection-Review of Procedures IP 73755 Inservice inspection-Review of Data i
IP 92902 Followup-Maintenance
'
._
ITEMS OPENED, CLOSED, AND DISCUSSED Closed 50-282/97003-01(a)(DRS)
VIO Failure to obtain Code relief pursuant to 10 CFR 50.55(g)
50-306/97003-01(a)(DRS)
and Technical Specification 4.2 for 14 welds associated with reactor vessel examinations L
50-282/97003-01(b)(DRS)
VIO Failure to obtain Code relief pursuant to 10 CFR 50.55(g)
l
' 50-306/97003-01(b)(DRS)
and Technical Specification 4.2 for 73 inservice examinations l
I i
!
,
.
,_
.
. - _ _ _.
_
_
.__
__
_. _
_.
_ _ _ _ _
..
,
LIST OF DOCUMENTS REVIEWED Prairie Island Unit 2 Category C-3 Inspection Results, Preliminary Report to the NPC-November 17,1998
Procedure Revision Title
-
ISI-ET-1.0
Bobbin Coil Data Analysis Guidelines ISI-ET-2.0
Eddy Current Data Management Procedure ISI-ET-3.0
Rotating Co;l Data Analysis Guidelines ISI-ET-4.0 -
Eddy Current Independent ODA ISI-ET-5.0
Eddy Current Site Specific Performance Demonstration
. H25.1
Assessment of Steam Generator Tube Degradation Mechanisms H25.3
Steam Generator Tube Repair Criteria ISI-UT-1
Ultrasonic Examination of Ferritic Steel Pipe and Fitting Welds ISI-UT-3
Ultrasonic Examination of Ferritic Welds ISI-VT-5.0
Visual Examination of Prairie Island Reactor Vessel i
interior
>
NSP-ISI-154
Remote Inservice Examination of Reactor Vessel Inlet Nozzles NSP-ISI-54
Manual Ultrasonic Examination for the Reactor Vessel Upper Shell to Flange Weld 2008374-In Situ
in Situ Pressure Test Using the Computerized Data Acquisition System 2008374-RR
Rerolling of Steam Generator Tubes with 0.0875" O.D. by 0.050" Wall
-
!
!
-.
...
.. -... -...... -
.. -. -.. -. ~. -. ~. -... -.
. ~........ -.. - -....-.
,
c,.....-
LIST OF ACRONYMS USED ANil -
Authorized Nuclear Inservice inspector
]
.ASME.
American Society of Mechanical Engineers -
CFR:-
Code of Federal Regulations:
.
~
. Division of Reactor Safety--
ISI Inservice inspection.
NDEi Nondestructive Examination
'
NRC Nuclear Regulatory Commission SG-Steam Generator
. VIO Violation
,
i i
I l
l p
i I,
Io
-
F#
l '
(..
..
,
,
- -