ML20136J485

Insp Repts 50-282/97-03 & 50-306/97-03 on 970203-13. Violations Noted.Major Areas Inspected:Performance of Listed Activities

ML20136J485
Person / Time
Site:	Prairie Island
Issue date:	03/14/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20136J454	List: ML20136J450 ML20136J465 ML20136J485
References
50-282-97-03, 50-282-97-3, 50-306-97-03, 50-306-97-3, NUDOCS 9703200121
Download: ML20136J485 (36)

See also: IR 05000282/1997003

Text

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U.S. NUCLEAR REGULATORY COMMISSION

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REGION lil

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Docket Nos.:

50-282: 50-306

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Licenses No.:

DPR-42; DPR-60

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Reports No.:

50-282/97003(DRS); 50-306/97003(DRS)

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Licensee:

Northern States Power Company

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Facility:

Prairie Island Nuclear Generating Plant

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Location:

1717 Wakonade Drive East

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Welch, MN 55089

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Dates:

February 3 - 13,1997 and

final phone exit February 20,1997

Inspector:

M. Holmberg, Reactor inspector

Approved by:

Wayne Kropp, Chief

Engineering Specialists Branch 1

Division of Reactor Safety

9703200121 970314

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PDR

ADOCK 05000282

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Report Details

II. Maintenance

M1

Conduct of Maintenance

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M1.1 Inservice Examinations (ISI) for U0iL2

a.

Scooe (73753. 73052)

Inspectors observed contracted ISI personnel from Lambert-MacGill Thomas, Inc.

(LMT) performing the following activities:

Ultrasonic examination (UT) calibration activities for the main steam line

elbow to pipe weld W-4.

Dye Penetrant examination (PT) on the eight inch diameter HHR hot leg

elbow weld (W-2) of line 8-2RH-1B.

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PT on the three inch diameter safety injection elbow weld (W-22) of line

3-2SI-15C.

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Visual examination (VT) of hangers H-3 and H-5 on the pressurizer spray line

3 2RC-5.

Underwater remote VT of the upper core internals.

Wet magn tic particle examination (MT) of a reactor vessel head stud.

Automated UT of the reactor vessel head to flange weld W-6.

Inspectors observed contracted ISI personnel from Zetec and Rockridge

Technologies performing the following activities:

Eddy current examinat'on (ET) and data acquisition for inservice steam

generator (SG) tubes ar d Babcock and Wilcox (B&W) rolled tube plugs

installed in SG-21 and SG-22.

ET data analysis for inservice tubes and B&W rolled tube plugs installed in

SG-21 and SG-22.

b.

Observations and Findinos

Code ISI activities executed well

LMT personnel performed ultrasonic equipment system calibration in preparation for

UT of main steam line weld W-4. The LMT personnel identified the refracted angle

of the transducer, verified the amplitude linearity of the machine, and established

the distance amplitude correction curve in accordance with procedure ISI-UT-1,

" Ultrasonic Examination of Ferritic Steel Pipe and Fitting Welds," Revision 11.

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Additionally, the inspector observed the LMT personnel performing the post.

examination calibration check. No recordable indications were detected for this

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examination.

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The inspector observed LMT personnel performing pre-cleaning of the welds W-2

and W-22, applying the dye penetrant with the appropriate dwell times, and

claaning and applying the developer for interpreting the exam results in accordance

with procedure ISI-PT-1, " Solvent Removable, Visible Dye Penetrant Examination,"

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Revision 10. LMT personnel were well prepared with materials staged near the

work site and encountered no difficulties with the examinations. Additionally, these

ISI examinations were within the same area and puformed simultaneously, which

demonstrated good as low as reasonably achievable (ALARA) radiological work

practices. No relevant indications were detected.

LMT personnel performed visual inspection of hangers H-3 and H 5, which included

hand tightness checks of anchor bolting and visual observation of the entire hanger

against the component support assembly drawing for missing parts, cracked welds

bolt alignment, thread engagement and proper fit,in accordance with procedure ISI-

VT-2.0, " Visual Examination of Components and Their Supports," Revision 7. No

discrepant conditions were identified.

LMT personnel performed wet fluorescent MT of a reactor vessel head stud. The

LMT personnel performed the verification of the fluorescent particle concentration,

correctly checked the magnetic field strength using a pie gage, and performed this

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examination in accordance with procedure ISI-MT-2, " Wet Magnetic Particle

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Examination," Revision 8. No relevant indications were identified.

LMT personnel performed remote underwater visual examination of the upper core

intemal structure. The LMT personnel performed the camera setup, calibration

check (resolve 1/32" line on 18 percent neutral gray card), and examination in

accordance with procedure ISI-VT 5.0, " Visual Examination of Prairie Island Reactor

Vessel Interior," Revision 2. The on-site ISI program engineer and Authorized

Nuclear Inservice Inspector observed this activity, which indicated active contractor

oversight. No rejectable indications were identified.

LMT personnel performed automated UT on the reactor vessel head weld W-6. For

this examination, inspectors verified that scan parameters / equipment, which

included scanning level gain settings, scanning speeds, scanning increments,

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transducer angles, calibration block, and transducer frequencies were in accordance

with procedure IDI-UT-3A, " Ultrasonic Examination of Reactor Vessel Welds,"

Revision 6. The LMT personnel demonstrated knowledge of the examination being

perform by comparing the location and amplitude response of previously recorded

indications related to weld geometry. LMT personnel were able to spend much of

this examination within a low dose area, which demonstrated good ALARA

radiological work practices, due to the use of remote controlled automated UT

equipment. No Code reportable indications were detected.

The inspector reviewed LMT personnel qualification and certification records and

determined that they met the American Society for Nondestructive Testing

Recommended Practice No. SNT-TC-1 A and the American Society of Mechanical

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Engineers (ASME) Code,1989 Edition,Section XI requirements. These

certifications had been reviewed and accepted by the Authorized Nuclear Inservice

Inspector.

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The inspector reviewed the ISI procedures used for the examinations observed and

determined that the procedures met the ASME Code,1989 Edition,Section XI and

Section V requirements. These procedures had been reviewed and accepted by the

Authorized Nuclear Inservice Inspector.

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Overall, the inspector observed good preplanning, preparation, and demonstrated

knowledge of the examinations performed, which resulted in ALARA radiological

work practices.

Unit 2 SG ET executed well

The inspector reviewed the scope of the Unit 2 SG tube ET inspection which

included:

100 percent full tube length bobbin inspection (except the row one and two

U-bend region).

100 percent hot-leg side tubesheet inspection using a motor rotating

pancake coil probe (MRPC) including existing F* re-roll locations. This probe

contained a + Point * coil, a 0.115 diameter pancake coil, and a 0.080

diameter pancake coil.

20 percent cold-leg side tubesheet inspection using a MRPC probe.

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100 percent of row one and two U bends with a MRPC probe (contained a

+ Point

coil).

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100 percent of all dented locations (greater than 5 volts) with a MRPC

probe.

Hot-leg side inspection of B&W mechanical plugs with a MRPC probe

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(contained a + Point

coil).

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The inspector determined that this inspection scope exceeded the technical

specification requirements and licensee commitments to generic letter (GL) 95-03

"Circumferential Cracking of Steam Generator Tubes." In addition, the licensee

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staff chose to use probes containing the + Point * coil for the B&W plua

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inspections and on the cold-leg side of the tubesheet, which had reporc

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been done before. The ET program engineer stated that he felt that the i .)oint*

coil provided the best possible inspection of these areas. As a result of ET

inspections using a rotating + Point * coil, three B&W mechanical plugs in tubes on

the hot-leg side of SG-22 were identified with circumferentially oriented indications.

The predominant type of ET indications detected were axial oriented inside diameter

indications located at the SG tube roll expansions on the hot-leg side of the SG.

This mode of degradation is consistent with past ET inspections and was indicative

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of primary water stress corrosion cracking. The ET performed consistently

detected previously identified tube imperfections such as cold leg tube thinning,

. tube wear, and manufactured burnish marks at the expected locations, which

indicated an effective inspection.

The inspector observed Rockridge Technologies personnel performing ET data

acquisition for the Unit 2 SG tubes and B&W tube plugs. The inspector verified

that the ET equipment setup parameters, methodology and equipment used were in

accordance with procedure 42-EC-248, "Multifrequency Eddy Current Procedure

Steam Generator Tubing Digital Eddy Current System Prairie Island, Units 1 & 2,"

Revision 2. The ET equipment and techniques used for the tube inspection were

consistent with qualified techniques per Appendix H of EPRI-NP-6201, "EPRI PWR

Steam Generator Ext mination Guidelines," Revision 3. The personnel observed

performing ET data acquisition demonstrated conservative inspection techniques

such as frequently verifying the robot positioning tool at the correct tube location

by using the existing tube plugs as reference points.

The ET data analysis was performed by Rockridge Technologies and Zetec

personnel using Zetec Eddynet95

software. ET data analysis was performed by

prianary and secondary analysts located off-site, with the exception of one primary

data analyst and the resolution analysts located on-site. The on-site analysts

performed ET data analysis in accordance with ISI-ET-1.0, " Bobbin Coil Data

Analysis Guidelines," Revision 7, and with ISI-ET-3.0, " Rotating Coi! Data Analysis

Guidelines," Revision 4. The on-site data analysts demonstrated knowledge of the

latest ET data analysis techniques and made conservative clas6fications of

potential SG tube degradation.

The inspector reviewed Zetec and Rockridge Technologies personnel qualification

and certification records and determined that they met the American Society for

Nondestructive Testing Recommended Practice No. SNT-TC-1 A and ASME Code,

1989 Edition,Section XI requirements. Additionally, the ET data analysts had been

qualified to Appendix G of EPRI-NP-6201, "EPRI PWR Steam Generator Examination

Guidelines," Revision 3. These certifications had been reviewed and accepted by

the Authorized Nuclear Inservice inspector.

The inspector reviewed the ISI procedures used for the ET data acquisition and data

analysis and determined that the procedures met the ASME Code,1989 Edition,

Section XI requirements. These procedures had been reviewed and accepted by the

Authorized Nuclear Inservice Inspector.

c.

Conclusions

The inspector observed good preplanning, preparation, and demonstrated

knowledge of the inservice examinations performed, which resulted in ALARA

radiological work practices. Additionally, the inspector identified the following

steam generator inspection staff decisions which demonstrated the licensee staff

focus on safety:

The decision to implement the best available technology for inspection of the

B&W mechanical plugs resulted in detecting potentially degraded plugs.

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The decision to perform an ET scope that exceeded Technical Specifications

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and NRC commitments.

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The decision to use " state-of-the-art" ET. equipment and " qualified"

personnel and techniques.

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M1.2 Comorehensive Unit 2 SG Tube Reoairs

a.

Scone (73753, 73755)

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The inspector reviewed SG tube repair lists generated as a result of the Unit 2 SG

ET inspection and the Unit 2 secondary side pressure tests.

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The inspector observed Combustion Engineering (ABB CE) personnel performing

removal of the cold-leg side, Westinghouse mechanical plugs with heats potentially

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susceptible to cracking.

The inspector observed ABB CE personnel performing in-situ hydrostatic and leak

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testing of individual SG tubes.

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b.

Observations and Findinas

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As a result of ET, the licensee planned the following SG tube repairs:

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F" Tubes

Plugged SG tubes

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During a secondary side pressure test of SG 22 a Westinghouse explosively welded

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plug installed in 1977 was found to have seepage at the primary tubesheet face.

Vendor ABB CE was scheduled to remove and replaced this plug with an inconel

690 welded plug.

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The vendor ABB CE removed the remaining Westinghouse mechanical plugs with

heats that had been identified as potentially susceptible to cracking (identified in

NRC Bulletin 89-01 " Failure of Westinghouse Steam Generator Tube Mechanical

Plugs" and NRC informatio'n notice 94-87 " Unanticipated Crack in a Particular Heat

of Alloy 600 Used for Westinghouse Mechanical Flugs for Steam Generator

Tubes"). ABB CE had been tasked by the licensee to replace these 145 plugs with

inconel 690 rolled plugs. At the conclusion of this inspection, the licensee staff

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indicated that they planned to replace the three B&W plugs with circumferentially,

oriented ET indications.

During secondary side pressure testing and visual examination of the SG tubesheet

area, the licensee identified ten tubes in SG-21 and two tubes in SG-22 with

leakage. Each of these tubes had been previously repaired by adding an additional

hard-roll and applying the F* criterion. Only one tube in SG-21 had measurable

leakage (2 drops per minute) and one tube in SG 22 had measurable leakage (one

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drop in 3 minutes). The licensee developed an action plan which included:

evaluating previous torque traces and calibration records, conducting profilometry

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of selected rerolls, determining the leak rate at main steam line break conditions

with in-situ pressure tests, evaluation of process parameters against the F*

qualification report, and confirming changes in roll transition ET indications after

hydraulic expansion.

On February 5,1997, the Office of Nuclear Reactor Regulation (NRR) staff

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requested the licensee to resolve NRC staff questions relating to the SG tube

leakage implications on the bounding leakage assumed in the qualification reports

for the F* repair process prior to plant startup. At the conclusion of this inspection

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on February 13,1997, the licensee staff had met with NRR staff to resolve the

NRC staff questions.

The licensee staff choose to perform in-situ pressure testing (at main steam line

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break pressures) to assess the structural and leak tight integrity of the as found

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condition of 45 F* tubes. The inspector confirmed that this scope included all

leaking tubes which had been identified during the secondary side pressure testing.

At the completion of this inspection the licensee had identified the following

leakage from in-situ pressure testing SG tubes at main steam line break (MSLB)

differential pressure conditions:

SG

Tube Location

Measured Leak-rate

No.

(Row / Column)

(Gallons Per Hour)

SG-21

R18C44

0.024

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SG-22

R16C38

0.05-0.11

SG-22

R13C46

0.00064

The licensee staff determined that the maximum potentialleak rate under MSLB

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differential pressure conditions could have been 0.53 gallons per minute

contribution from the total population of 288 F* tubes. The licensee staff had

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planned on installing additional rerolls for each of the F' tubes with measurable

leakage and had scheduled a secondary side pressure test to ensure that these

tubes were not leaking prior to plant startup.

c.

Conclusions

The inspector considered that the licensee actions; to perform in-situ pressure

testing of SG tubes for assessment of the as found integrity, to oromptly put in

place a repair plan and address NRC staff questions related to leaking F* SG tubes,

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to replace tube plugs with heats susceptible to cracking (without identified

leakage), demonstrated a steam generator repair program focused on safety.

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M4

Maintenance Staff Knowledge and Performance

M4.1 ISI Proaram imolementation

a.

Scoce (73051)

The inspector reviewed the inservice inspection data results for the Unit 1 reactor

vessel examination performed in May of 1994 and the Unit 2 reactor ves.sel

examination performed in November of 1993 as part of the ASME Code second

interval inspections.

The inspector reviewed the ISI Summary Reports for the third period second interval

ASME Code examinations for each unit.

The inspector reviewed licensee docketed submittals and participated by phone in a

licensee and NRR staff meeting held on February 6,1996, associated with a

licensee request to use ASME Code Case N-521 " Alternative Rules for Deferral of

inspections of Nozzle-to-Vessel Welds, inside Radius Sections, and Nozzle-to Safe

End Welds of a Pressurized Water Reactor (PWR) Vessel Section XI, Division 1."

The inspector reviewed NRR staff requests for additionalinformation associated

with Code relief requests submitted by the licensee as part of their Third 10-Year

Interval inservice inspection Examination Plan for both Units.

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b.

Observations and Findinas

Code Relief Not Obtained for ISI Examinations

Technical Specification 4.2.A.1 requires that the " inservice inspection of ASME

Code Class 1, Class 2, and Class 3 components be performed in accordance with

Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as

required by 10 CFR 50, Section 50.55(g), except where relief has been granted by

the Commission pursuant to 10 CFR 50.55(g)(6)(i)."

ASME Code,Section XI,1980 Edition Winter 1981 Addenda, lWB-2500(a) requires

" Components shall be examhed and tested as specified in Table IWB-2500-1."

Table IWB-2500-1 requires Volumetric examination of weld volumes defined by

Figure IWB-2500-4 for Category 81.30 welds and volumetric examination of weld

volumes defined by Figures IWB-2500-7(a) through (d) for Category 83.90 welds.

10 CFR 50.55a(g)(5)(iii) requires "If the licensee has determined that a Code

requirement is impractical for its facility, the licensee shall notify the commission

and submit, as specified in 50.4, information to support the determinations."

10 CFR 50.55a(g)(5)(iv) requires "Where an examination requirement by the Code

or addenda is determined to be impractical by the licensee and is not included in the

revised inservice inspection program as permitted by paragraph (g)(4) of this

section, the basis for this determination must be demonstrated to the satisfaction

of the Commission no later than 12 months after the expiration of the initial 120-

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month period of operation and each subsequent 120-month period of operation

during which the examination is determined to be impractical."

10 CFR 50.55a(g)(6)(i) states "The Commission will evaluate determinations under

paragraph (g)(5) of this section that code requirements are impractical. The

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Commission may grant such relief and may impose such alternative requirements as

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it determines is authorized. . . ."

Contrary to these requirements, on February 10,1997, the inspector identified

seven welds in each unit (identified below) for which Code volumetric examination

requirements had not beer, met and for which authorized Code relief had not been

obtained pursuant to 10 CFR 50.55a(g)(6)(i) and Technical Specification 4.2.A.1

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requirements. Failure to obtain ASME Code relief is considered a violation (50-

282/97003-01 (a); 50-306/97003-01 (a)) .

Unit 21993 vessel inspections

Percentage

of Code

IWB-2500

Volume

Code Relief

Weld #

Weld Description

Category

examined

Request

RPV-W1

Flange to Shell

B1.30

71 % *

None

RPV-W10

Outlet Nozzle to Shell

B3.90

15% * *

None

Weld 11

Safety injection Nozzle to Shell

B3.90

55% *

None

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RPV-W6

Inlet Nozzie to Shell

B3.90

87% *

None

RPV-W7

Outlet Nozzle to Shell

83.90

15% * *

None

Weld 8

Safety Injection Nozzle to Shell

B3.90

55% *

None

RPV-W9

Inlet Nozzle to Shell

B3.90

87% *

None

• Average coverage estimated by the inspector based on data reported.

• * A 1985 inspection examined these welds from the nozzle bore; however, the licensee

was unable to quantify the additional amount of Code required volume that had been

inspected.

Unit 1 1994 vessel inspections

Percentage

of Code

IWB-2500-

Volume

Code Relief

Weld #

Weld Description

1 Category

examined

Request

RPV-W1

Flange to Ghell

B1.30

71 %

None

RPV-W10

Outlet Nozzle to Shell

B3.90

38% * *

None

Weld 11

Safety injection Nozzle to Shell

B3.90

40 %

None

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%

Percentage

of Code

IWB-2500-

Volume

Code Relief

Weld #

Weld Description

1 Category

examined

Request

RPV-W6

Inlet Nozzle to Shell

B3.90

82%

None

RPV-W7

Outlet Nozzle to Shell

B3.90

38% * *

None

Weld 8

Safety injection Nozzle to Shell

B3.90

40%

None

RPV-W9

Inlet Nozzle to Shell

B3.90

82%

None

• A 1985 inspection examined these welds from the nozzle bore; however, the licensee

was unable to quantify the additional amount of Code required volume that had been

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inspected.

The inspector reviewed ISI summary reports for Code examinations performed for

Unit 1 and Unit 2 in the third period of the second interval. In the Unit 1

examination report 94-01088L that performed UT of a 31 inch diameter reactor

coolant system elbow seam weld, a 4 inch wide restraint was listed as a limitation

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preventing a complete Code volumetric examination. No documentation could be

located to indicate the basis for the licensee's determination that the restraint

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removal was impractical. Thus, the inspector was concerned with 73 Code

examinations, which listed limitations (see third period second interval examinations

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listed in Attachment A) that prevented meeting the ASME Section XI Code

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examination requirements, and for which 10 CFR 50.55a(g)(4) requirements of

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" extent practical" may not have been met. If the licensee had submitted relief

requests as required by 10 CFR 50.55a(g)(5)(iii) there would have been NRC

reviews and authorization of the " extent practical."

ASME Code,Section XI,1980 Edition Winter 1981 Addenda, IWB-2500(a) requires

" Components shall be examined and tested as specified in Table IWB-2500-1,"

IWC-2500(a) requires " Components shall be examined and pressure tested as

specified in Table IWC-2500-1 and IWF-2500 requires " Components supports

subject to examination shall be examined and tested as specified in Table IWF-

2500-1."

Contrary to these requirem'ents on February 12,1997, the inspector identified 73

examinations, affecting both units (identified in attachment A as * limited exam") for

which Code examination requirements had not been met and for which authorized

Code relief had not been obtained pursuant to 10 CFR 50.55a(g)(6)(i) and Technical Specification 4.2.A.1 requirements. Failure to obtain ASME Code relief for these

examinations is considered an additional example of violation (50-282/97003-

01(b);50-306/97003-01(b)). Based on these findings, the inspector considered that

the extent of this problem was programmatic and many additional examinations

existed which required Code relief.

The licensee staff initially stated that A3ME Code requirements for these

examinations or similar examinations were not required to be met, since they were

examined to the extent practical and limited t,; the design, geometry and/or

materials of construction pursuant to 10 CFR 50.55a(g)(4) requirements. However,

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at the completion of this inspection during the final phone exit on February 20,

1997, the licensee staff acknowledged this violation and indicated that Monticello

(applicable Technical Specification is 4.15) was in the same condition. The licensee

did not commit to any actions or schedule to address this situation.

Inadeauate Relief Reauest is Denied

On November 1,1995,.the licensee submitted an ASME Code relief request to use

Code Case 521 relating to ASME Code Section XI examination schedule B

requirements for the deferral of inspections of nozzle-to-vessel welds and inside

radius section examinations for both Units. The following chronology of events

transpired relating to this request:

November 20,1995

NRR assigned the review of this relief request to Idaho

National Engineering Laboratory (INEL).

December 13,1995

A conference call was held with NRR, INEL, and the

licensee to request additional information to clarify and

support the basis for this relief request.

July 25,1996

The licensee submitted a historical inspection summary,

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which referred to Westinghouse Report WCAP-10363,

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" Handbook on Flaw Evaluation, Prairie Island 1 and 2

Reactor Vessels" for justification.

July 29,1996

INEL requested the licensee to provide WCAP-10363.

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August 9,1996

The licensee submitted WCAP-10363 and a

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Westinghouse Report WCAP-10562, " Background and

Technical Basis of Handbook on Flaw Evaluation."

November 6,1996

A conference call was held with NRR, INEL, and the

licensee to clarify the information in the current

submittals.

November 8,1996

A conference call was held with NRR, INEL, and the

licensee to discuss the licensee's basis for the relief

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request and in response the licensee committed to

revise the relief request.

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November 26,1996

The licensee submitted further information and revised

the basis for its' proposal to exclude the vessel-to-shell

welds; and enhanced the overall basis for this relief

request.

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January 7,1997

A Request for Additional Information (RAl) was issued

by NRR staff to obtain clarification pertaining to the

licensee's basis for this relief request.

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February 6,1997

At the licensee's request, a meeting was held at the

NRC headquarters office to discuss RAI questions and

resolve technical questions associated with this relief

request.

February 7,1997

The technicalissues could not be resolved and NRR

staff denied this relief request and gave the licensee the

option to withdraw this request.

A significant amount of NRC staff resources were involved in attempting to review

thi.s poorly prepared and inadequately based relief request. Although subsequent

submittals improved this relief request, ultimately the technical issues could not be

resolved and the licensee opted to withdraw this relief request.

The inspector reviewed the NRR staff requests for additionalinformation associated

with six relief requests submitted by the licensee as part of the Prairie Island Unit 1

Third 10-Year Intervalinservice Inspection Examination Plan. NRR technical staff

issued requests for additionalinformation on four of the six relief requests

submitted by the licensee. Two relief requests required additional technical

justification, one required specific drawings identifying the areas needing relief, and

one should not have been submitted based on an existing NRC endorsed ASME

Code Case, which bounded the issue.

The inspector reviewed the NRR staff requests for additional information associated

with seven relief requests submitted by the licensee as part of the Prairie Island

Unit 2 Third 10-Year Intervalinservice inspection Examination Plan. NRR technical

staff issued requests for additionalinformation on four of the seven relief requests.

Two relief requests required additional technical justification, one required specific

drawings identifying the areas needing relief, and one should not have been

submitted based on an existing NRC endorsed ASME Code Case, which bounded

the issue.

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c.

Conclusions

Because of an inadequately prepared relief request, the NRC staff expended a

significant amount of resources in th9 review of the licensee's relief request to

defer Code mandated examinations associated with the reactor vessel. Although

subsequent submittals improved this relief request, ultimately the technical issues

could not be resolved and the licensee decided to withdraw this relief request. The

inspector identified additional sxamples of relief requests submitted as part of the

licensee's Third 10-Year Interval inservice Inspection Examination Plan, which

lacked detail or an adequate technical basis as originally submitted. The inspector

considered these examples to demonstrate a weakness in the licensee staff's

understanding of the level of detail and technical basis needed to support ASME

Code,Section XI, ISI relief requests.

The inspector identified in excess of 80 examinations which did not meet ASME

Code ISI requirements, without NRC approved Code relief. The inspector

considered this to demonstrate a lack of understanding by the licensee's staff of

regulatory requirements related to Code ISI relief requests.

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M8

Miscellaneous Maintenance issues (90712)

M8.1 (Closed) LER 282/06011: In this licensee event report, the results of a licensee

initiated re-review of UT data for Combustion Engineering Tungsten inert Gas

welded sleeves in Unit 1 SG were identified. The licensee identified three sleeved

SG tubes returned to service with areas of lack of fusion in the upper sleeve weld

and three additional tubes with UT data taken outside of the upper sleeve weld

area. Based on review of the licensee safety evaluation #453, Revision one, and

j

review of issue tracking report commitments, the inspector considered licensee

corrective actions completed to date and/or planned for this issue to be acceptable.

111. Enaineerina

i

E2

Engineering Support of Facilities and Equipment

E 2.1

Insoector Uodated Safety Analysis Reoort (UFSAR) Review

While performing the inspections discussed in this report, the inspectors reviewed

UFSAR sections:

'

4.1.1.2

Performance Standards

4.1.2.1

Reactor Coolant Pressure Boundary

4.3.2

Steam Generators

4.7.1

Reactor Coolant System inspection and Testing

11.1.5

Codes and Classifications

13.4.6

Inservice Inspection and Testing Program

i

The inspectors did not identify any UFSAR discrepancies as a result of this special

review.

V. Manaaement Meetinas

X1

Exit Meeting Summary

At the conclusion of the inspection on February 13,1997, and final phone exit on

February 20,1997, the inspector met with licensee representatives identified herein and

summarized the scope and findings of the inspection activities. The inspector questioned

licensee personnel as to the potential for proprietary information in the likely inspection

report material discussed at the exit. No proprietary information was identified.

Attachment: Prairie Island Summary Report

13

1

,

.

PARTIAL LIST OF PERSONS CONTACTED

Licensee

'

K. Albrecht, General Superintendent Engineering

D. Cooper, Plant Engineering

L. Dahlman, ISI Coordinator

T. Jones, Materials and Special Processes

C. Kinney, Materials and Special Processes

J. Laveille, NSP Licensing

J. Mak, Outage Manager

R. Pearson, Plant Engineering

J. Ricker, Materials and Special Processes

)

J. Scobie, Plant Engineering

'

J. Sorensen, Plant Manager

T. Tran, Materials and Special Processes

i

NRC

S. Ray, Senior Resident inspector

'

The NRC inspector also contacted and interviewed other licensee and contractor

employees.

INSPECTION PROCEDURES USED

h

IP 73753:

Inservice inspection

'

IP 73755:

Inservice inspection, Data Review and Evaluation

IP 73051:

Inservice inspection, Review of Program

iP 73052:

Inservice Inspection, Review of Procedures

'

ITEMS OPENED, CLOSED, AND DISCUSSED

Ooened

50-282/306/97003-01(a)(DRS)

VIO

Failure to obtain Code relief pursuant to 10 CFR 50.55(g) and Technical Specification 4.2 for 14

welds associated with reactor vessel

examinations

50-282/306/97003-01(b)(DRS)

VIO

Failure to obtain Code relief pursuant to 10 CFR 50.55(g) and Technical Specification 4.2 for 73

inservice examinations

j

Closed

50-282/96011

LER

Sleeved SG tubes with areas of lack of fusion

i

14

,

._ _ . . .

. .

_ _ . _ . _ . _ .

_ _ . _ _ _

_ . _ - -

_ _ . _ .

. - _ _

_ _. . . _ _ _ _ _ _

._ _ _ _

.

2

.

4

LIST OF ACRONYMS USED

,

ABB CE

Combustion Engineering

,

i

ALARA

As Low As Reasonably Achievable

ASME

American Society of Mechanical Engineers

B&W

Babcock and Wilcox

i

DRS

Division of Reactor Safety

i

EPRI

Electric Power Research Institute

j

ET

Eddy Current Examination

F* Distance The distance from the bottom of the hardroll transition toward the bottom of

{

the tubesheet that has been conservatively determined to be 1.07 inches

(not including eddy current uncertainty).

F*Tybe

A tube with degradation, below the F" distance, equal to or greater than

40%, and not degraded (i.e., no indications of cracking) within the F*

distance).

'

1

INEL

Idaho National Engineering Laboratory

i

IP

inspection Procedure

'

IR

inspection Report

j

ISI

Inservice Inspection

.

LER

Licensee Event Report

i

LMT

Lambert-MacGill Thomas, INC

MT

Magnetic Particle Examination

,

MRPC

Motor Rotated Pancake Coil

j

NRC

Nuclear Regulatory Commission

i

NRR

Office of Nuclear Reactor Regulation

PT

Dye Penetrant Examination

PWR

Pressurized Water Reactor

.

!

RAI

Request for AdditionalInformation

l

SG

Steam Generator

1

l

TS

Technical Specification

j

!

UFSAR

Updated Safety Analysis Report

UT

Ultrasonic Examination

1

VIO

Violation

VT

Visual Examination

]

s

i

i

1

4

i

15

-

_

..

-

NORTHERN STATES POWER

SUMMARY REPORT

o

INSERVICE INSPECTION

PRAIRIE ISLAND UNIT 2.1995

i

-

APPENDIX A

INTERVAL 2 PERIOD 3 INSPECTIONS BY ISO

5 Pages

,

'

1

l

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s

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IR NO. 50-282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A. Page 1 of 21

~

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. _ . . _ -

. . . . _

.

.

._ -

~.m.

. . ~ _ .

_ _-_

. . . _ .

m

m

'

1

a

1

Prairie Islead 3haclear Generating

Zaservice Zaspection Beport leg

Northerm States Power Company

1

1117 wakonade Drive

second Zaterval

By Zoo / Item

414 Micollet Mall

'

solch, set $5089

Commercial service Dates December 20, 1974

ulamaapo118, MN 55401

i

j

ISO

Item

Beport Nueber

Method

Results

,

Byeten

Item Descriptico

Buem Date

ASMB Section 22 Item

l

2 131 1A

Flange S W-2

95-0033

VT1

NAD

4

Seal Injectic,a A

Flange / Pipe

05/19/95

B1 50

Examined in place

2 ISI- 1C

Flange e W-54

95-0031

W1

NAD

,

Seal Injection A

Flange Bolts

05/19/95

8 1. 50

Examined ir place

d

2 ISI- 1C

PRCVCH-1515/N

95 0045

VT3

NAD

Seal Injection A

Support

05/22/95

IWF

i

!

2-ISI- 1C

W 58

95-0016

PT

NAD

'

fSealInjectionA

Pipe / Flange

05/16/95

B 9. 21

t

I

i

,. 15; 70

W 22A St

95-0012

PT

NAD

'

} ipray To P*r Dr A

Safe End/Nortle

05/16/95

8 5. 40

t

.

- "S;- 70

W-22A St

95-0054

trr4 5

NAD

i

,

l 3; rey Te P*r 3r A

Safe End/ Nozzle

05/22/95

8 5. 40

I

i

Limited exa-

!S;- 70

W-22B

95-0013

PT

NAD

f3;rayToPar3:

'

A

Reducer / Safe Ind

05/16/95

B 9. 11

'

i

.-!$1- 7C

W-22B

95 0051

W45

GIG

,

q

3; ray To P2; Br A

Reducer / Safe End

05/22/95

8 9. 11

1

l

.-IS; 10A

9 - 2 st.HR - 7 / C

95-00'1

VT3

NAD

EG K;, Takeof f A

Rupt Res't

05/15/95

IWF

.1

2-ISI-11

WR

95-0059

trr45

NAD

A::wn Discharge A

Branch

05/25/95

8 9. 31

1-ISI-12A

FLANGE e W-61

95-0034

VT1

NAD

3eal Injection B

Flange Bolts

05/19/95

B7 50

Examined ir. ;*. ace

2-131-130

FLANGE O W 83A

95 0032

VT1

NAD

l

C:1d Leg Charging B

Flange Bolts

05/19/95

B 7. 50

Examined in ;* ace

2 151 18

W-k

95-0055

trr45

NAD

JIS High Head B

Branch

05/23/95

B 9. 31

Limited exat

2-ISI-35

N-1 IR

95-0050BL

W45

NAD

Pressurizer

Surge Nottle

05/22/95

B 3,120

Angles per procedure

2-ISI-35

W- 2 IR

95-0046BL

trr45

NAD

Pressuriser

Spray Nozzle

05/18/95

8 3.120

Angles per ;rocedure

2-ISI-35

N- 3 IR

95-00473L

trr4 5

NAD

Pressurizer

Relief Nozzle

05/18/95

D 3.120

Angles per prxedure

2-ISI-35

N 4A IR

95-004tSL

("r4 5

NAD

Pressuriser

Safety Nozzle

05/16/95

D 3.120

Angles per troredure

2-151-35

N 49 IR

95-00498L

trr45

NAD

Pressuzizer

Safety Nozzle

05/10/95

8 3.120

Angles per prxedure

2-151 37

FW Ring / Support

95 0036

vri

NAD

S eam Generator 21

N 1 FW Nozzle Supt

06/02/95

IN 93 20

2-151-37

N-4

95 0017

MT

NAD

Steam Generator 22

Top Head /Nostle

05/11/95

C 2. 21

2-ISI-37

N-4

95 0024

trro

NAD ~

Steam Generator 22

Top Head / Nozzle

05/17/95

C 2. 21

Limited exam

7 1$1-37

N-4

95-0030

trr45

NAD

Steam Generator 22

rop Head / Nozzle

05/18/95

C 2.

21

Limited exam

• ' ' ' "

IR NO. 50 282/97003(DRS): 50-306/97003(DRS) ATTACHMENT A Page 2 of 21

.

.

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. _ . .

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...__.. _ .- - - - - . ... . . . . . .

. - . . - .

.

1

t

e

I

i

Prairie Zeland Nuclear Generating

Zaeervice Inspection Report Log

3 fort 3nera States Power Campeay

"

1111 Wakemade Drive

second Interval

By Zoo / Item

414 Nicollet Itall

<j

t

unich,1st 55069

Ccamercial service Dates December 20, 1974

ulnacepolis, ta8 55401

i

ISO

Iten

Beport Number

Method

Rossite

System

Item Description

Baem Date

AsasE section II Item

i

'

2-131-37

N-4

95-0029

11T60

NAD

l

3:eaa Generator 22

Top Head / Nozzle

05/18/y5

C 2. 21

I

j

1

limited exas

,

1

2-:31-37

W1 IR

95-0061 (A)

prr

NAD

3: eat Generaror 21

Nozzle Inner Radius

06/02/95

IN 93 20

,

Limited exam

'

2-;5;-37

W-A

95-0005 (A)

trf 60

NAD

3:ea Generator 22

Chnl Head / Tube Sheet

06/13/95

8 2. 40

No growth cf previous

indication

g . .3; 37

WF Intestor 52:

95 0062 (A)

VT1

NAD

g 1:ea Generator 21

Upper Transit.:-

06/02/95

IN 93 20

'

+

i

Interior $2rfs:es

' . * 3.* - 4 3

' Bolts Pump B

95-0065

g VT1

NAD

,1: >;?p 22 SH Bolts

• ower Seal House

06/07/95

l 8 7. 60

w

l

l Examined D.sasse. bled

. . :3*-43

Bolts Pump &

95 0066

Vr1

NAD

{

i

{ A

P. p 22 SH Bolts

Upper Seal Heuse

06/07/95

B7 60

i

,

Examined dis asse eled

. ;J; 43A

W- 1

95-0010BL

VT1

NAD

1: P;rp 21

l Putp Casemen- ne' i

05/17/95

B12. 10

l

t

,

O

• 3*-44

jool:s 1 - 24

g95-0064 (A)

VTO

NAD

j A: P; p 21 F1g Bolts

gFlangeBolts

{05/26/95

B 6.180

l

f

I

Examined 1. .arthouse

ja-;5;-44

Bolts 1 - 24

95-0063 (A)

VT1

IND

1: P; p 21 F1g Bolts

Flange Bolts

05/26/95

B 6.100

• []

Exam in were..:;se, machining

.,

,f

mark on one ::lt

• 5*-44

Bolts 1 - 24

95-0063R1

VT1

NAD

j

s

.

R: P2?p 21 Flg Bolts

Flange Bolts

06/02/95

8 6.180

l

Bolt removed fr:e stock

. ;5;-45

Flyvneel Periph

95-0060 (A)

MT

NAD~

.R

Pap 21 Flywheel

Flywheel

05/30/95

RG / TS.4.2 .

IF*dnSteamA

* 5 * 4 6A

MSH 39/F

95 0019

MT

IND

Support

05/11/95

C 3. 20 / IW7

Linear Indi:a: ion

5

46A

MSH-39/F

95-0019A1

MT

NAD

• 4:n Steam A

Support

05/26/95

C 3. 20 / IirF

Repaired

2-;5;-46A

MJH-51/B

95-0021

MT

IND

Fair. Steam A

Support

05/10/95

INF/C3.20

Linear Indication

*S;-46A

MSH-51/B

95-0021R1

MT

NAD

Main Steam A

Su.*po rt

05/26/95

Iwr/C3.20

h

Repaired

2 13:-46A

MSH-53/E

l95-0022

VT3

NAD

Main Stear. A

Hanger

105/18/95

Iwr

}

1

.

.

_ . .2 :5: 469

• r.3H-91/T

95-0025

VT3

NAD

j

l Support

Maan Steam A

05/18/95

IWF

2 23; 460

M3-41

j95 0026

MT

NAD

Fa :i Steam A

Valve / Pipe

)05/18/95

C 5. 21/FSAA

i

"lT!5 -46C

MS 41

95-0027

trT45

~

NAL '

Main Steam A

Valve / Pipe

05/10/95

C 5. 21/FSAR

l !S*-47A

MSH-44/G

95-0042

VT3

NAD

Main Steam B

welded Attachment

05/20/95

IWF

Limited exam

0-tal-47A

M3H-52/D

95-005)

MT

NAD

Main Steam B

Support

05/23/95

IWF

Limited exam

. _ _ _

IR NO. 50 282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A. Page 3 of 21

09non5

-

..

-

.

.

.

,

.

$

.

Preitie Zeland Nuclear Generating

Inservice B ; ntion Report Log

Nort.hern states Power Campany

.

1717 wakoaade Drive

second Interval

Dy Iso / Item

414 Mico11st mall

welch lef 55049

Commercial service Dates December 20, 1974

wi- w polie, let 55401

Iso

Item

Report Number

Method

Results

Systen

Item Description

Exam Date

ASME Sectimum XI Item

2 151-47A

MSH-52/B

95-0052

W3

NAD

Main Steae a

Support

05/23/95

IWF

2 *SI-47A

MSH-55/F

95-0041

YT3

NAS

wa.n Steae 9

Support

05/20/95

IWF

Limited exa.a

,

2 ;5I 47B

MSH-26

95-0023

VT3

NAD

j

.ain Steam B

Support

05/18/95

IWF

w

L;-;5 473

-

MSH 66/M

95-0020

VT3

IND

5

watr. Steam B

Support

05/18/95

IWF

i

Loose nut

. ;5;-4 7B

MSW 66/M

95-0020R1

VT3

NM

!

• nr. Steae 3

Sepport

'06/02/95

IMF

f

Repaired

j

. ;S;-473

-MSH-90/R

'95-0024

VT3

NAD

)

• n , Steam B

Support

'05/18/95

IWF

l

e

f

I

• 3;-4SA

iTh-177AR

g95-0015 (A)

t.Tr4 5

g NAD

i feet ater A

! Reducer /Near".e

j05/16/95

C 5. 31

l

i

}

Limited exa:

l

4

. ;3;-44A

FW-177R

95-0014 (A)

UT45

NAD

l Feedester A

! Pipe / Reduce:

05/16/95

C 5. 21

1

Limited exas-

. 141-45A

TdH 75/I

95-0040

VT3

NAD

}

Feedwater A

Single Spr Sup;crt

05/19/95

IWF / C 3. 20

. ;50-483

FW 57/M

95-0044

MT

NAD

{

Feet.ater A

Support

05/22/95

IWF/,C3. 20

.-!S;-49A

FWW-59/G

95-0039

VT3

NAD

feedeater a

Support

05/19/95

INF

Limited exas

2-IS;-49A

FWH-62/F

95-0038

VT3

NAD

feed.ater B

Support

05/19/95

IWF

Limited exas

J

2 ISI-49A

FWM-63/8

95-0037

VT3

NAD

Feedwater B

Support

05/19/95

IWF

Limited exam

2 ISI-49A

FWH-64/C

95-0035

VT3

NAD

Fee $ water 5

Support

05/19/95

IWF

Limited exam

i

2 1S* 55

. RHRB 37/L

95-0004

VT3

NAD

RXR Pump B Discharge

l Support

05/10/95

IWF

'

2 *S;-55

R/RW-60/8

95-0001

VT3

NAD

F;-2 Pump B Oischaage

Support

05/03/95

IWF

r

2-151-60

lSUPpCRT E

95-0057

Prr

NAD~

!

SI Pump 21 Suction

lHoldtry Lug

02/26/95

C 3. 30 / IWF

1

Limited exam

2-15;-60

l SUPPORT F

95-00$$

KT

NAD

S: Pamp 21 Suction

Holding Lug

05/24/95

C 3. 30 / IWF

Limited exam

2-ISI-60

SUPPORT F

l95-0003

VT3

NAD

j

S: Pump 21 Suction

jHolding Lug

g05/06/95

C 3. 30 / IWF

1

I

i

2-ISI-60

WA

95 0056

MT

NAD

'

Sa'ety Inject Pumps

Pump 21

05/24/95

C 6.

10

<

1 151-69

SUPPORT A

95-0005

PT

NAD

RRR Eeat Exchgr 23

Welded Attachment

05/10/95

C 3. 10 / IWF

limited exam

2-131-69

SUPPORT A

95-0002

VT3

NAD

,

RHR Heat Exchgr 22

Welded Attachment

05/03/95

C 3.

10 / .IWF

2

f

_.

_

I

Du20/,5

IR NO. 50-282/97003(DRS) 50-306/97003(ORS)- ATTACHMENT A. Page 4 of 21

.

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, _ . - . .

-- -

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.-,

. _ . - . _ ,

s

.

.

Prairie Island Nuclear Generating

laservice Inspection Report Log

Northern Statee Power Company

-

1717 wakonada Drive

Seceed Interval

By Zee / Item

414 Nicollet Mall

Welch, set 55049

commercial Service Dates December 20, 1974

Minneapolis, tot 55401

ISO

Item

Report Number

Isethod

Results

system

Item Descripties

Enem Data

ASME Section Z2 Item

2 131-69

SUPPORT B

95-0006

PT

NAD

ILMR Heat Etchgr 22

Walde,d Attachment

05/10/95

C 3.10 / Ivr

Limited exas

J ISI-77

Column 1 Base

95-0077

WO

NAD

SG 21 Support Base

Bottom Pin

06/09/95

IWF

a-ISI-77

Column a Base

95-0067

VT3

NAD

S3 21 Support Base

Bottom Pin

06/09/95

IWF

j

ISI-77

Column 1 Base

95 0078

UTO

HliD

S3 22 Support Base

Bottom Pin

06/09/95

IWF

$

ISI 71

Column 1 Base

95-0068

W3

NAD

IJ 22 Support Sase

Bottom Pin

04/09/95

IWF

i

-ISI-77

Column 2 Base

95-0079

' WO

NAD

33 21 Suppor Sase

Bottom Pin

06/09/95

IWF

i

i

. !$!-17

Column 2 Base

95-0069

VT3

NAD

S3 21 Supp:rt 3ase

fBottomPin

06/09/95

IWF

. ISI 17

l Column 2 Base

'95-0080

Wo

i NAD

I

33 22 Support Base

jBottom Pin

06/09/95

IWF

l

1

i

ISI-77

Co;umn 2 Base

95-0070

VT3

NAD

30 22 Support Base

Bottom Pin

06/09/95

IWF

l

[

.f

2 ;$1-77

Column 3 Base

95 0061

WO

NAD

33 21 Support 9ase

Bottom Pin

06/09/95

IWF

• I

l

.-ISI-77

Column 3 Base

95-0071

W3

NAD

I,3 21 Support Sase

Bottom Pin

06/09/95

IWF

2-151-17

Column 3 Base

95-0082

WO

NAD

SG 22 Support Base

Bottom Pin

06/09/95

IWF

2 ISI-77

Column 3 Base

95 0072

W3

NAD

SG 22 Support Base

Bottom Pin

06/09/95

IWF

2-151-77

Column 4 Base

95 0083

WO

NAD

SG 21 Support 3ase

Bottom Pin

06/09/95

IWF

T-TSI- 77 ~

Column 4 Base

95-0073

VT3

NAD

SG 21 Support 3ase

Bottom Pin

06/09/95

IWF

2 ISI-77

! Coluna 4 Base

95-0084

(P0

NAD

SG 22 !arport Base

!EottomPin

06/09/95

IWT

i

2 ISI 77

Column 4 Base

95-0074

VT3

NAD

SG 22 Support Base

Bottom Pin

06/09/95

IWF

2 ISI-78

' COL 4 TOP CN'T

95 0075

W3

NAD

SG 21 Support Tcp

Top Conn't

06/09/95

IWF

2*ISI-74

COL 4 TCP CN'T

95-0076

W3

NAD

SG 22 Support Top

Top conn't

06/09/95

IWF

l

l

T ISf-85

UP RING HGR 1

95-0007

VT3

NAD

STEAM GENERATOR 21

Girder Spring HGR

05/12/95

IWF

Verified load setting only at

538'r

2-151-85

4UP RING HGR 1

95-0009

W3

NAD

STEAM GENERATOR 22

Girder Spring HOR

05/12/95

IWF

verified load setting only at

f

$3a*F

09/20/95

IR N0. 50*282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A Page 5 of 21

.,

.

.

.

a

.

a

Prairie Island Nuclear Generating

Zaeervice Imepection Report lag

Northern Statee Power Compeay

1717 wahaanda Drive

Second Interval

Dr Ise/ Item

414 Nicollet 38e11

Welch. Ier 55089

comunercial Service Dates December 20, 1974

Minneapolis, MN 55401

Iso

Item

Report Number

method

Resulte

System

Items Deecripties

Enem Date

ASME section II Item

2-ISI-85

UP RING HGR 1

95-0009R1

VT3

IND

S W GENERATOR 22

Girder Spring HGR

05/17/95

IWF

10% out et ?$*F

2 25;-45

UP RIWri HGR 1

95 0007R1

VT3

IND

M M GENERATOR 21

Girder Spring hiGA

05/17/95

TWF

10% out et '5'F

g : ;S*-85

UP RING HGR 1

95-0007R2

VT3

NAD

I S W GENERATOR 21

Girder Spring HGR

06/13/95

IWF

{

Engineering evaluation

. ;3; 95

iUP RING H3R .

95 0009R2

T 3

NAD

lCirderSpssngM1R

06/13/95

aWF

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'UP RING H3R 4

95-0000

VT3

IND

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Girder Spring MOR

05/12/95

IWF

verified Icat setting only at

i

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!

[.11*85

UP RING H3k 2

95-0010

VT3

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$ $TIJ? GENERATOR 42

Girder Spring M3R

05/12/95

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10% out at !!i'T

f

.. L 45

UP RING H3R 2

95-0010R1

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, Girder Sprin; H3R

05/17/95

IWF

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95-0008R1

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Girder Spring N3R

05/17/95

IWF

At 75'F

T ;SO-45

lUPRIrlGHGR2

95-001012

VT3

NAD

STIl# CINTRATOR 22

' Girder Spring E3R

06/13/95

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Engineering evaluation

,' '

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95 0004R2

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06/13/95

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AX ;;06-14

ATWW-74

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A"X FIIDWATER

Daal Spring Ha.ger

05/19/95

IWF

1,oad setting la:orrect

X3 .106-16

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95-0043R1

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Dual 4,pring Hanger

05/30/95

IWF

'

Repaired

1

1

.

' ' ' ' " "

IR NO. 50-282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A Page 6 of 21 5

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,

,

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_,

.

.

__

.

.

_

_

_ __ _.. . _ _

'

NORTHERN STATES POWER

SUMMARY REPORT

,

INSERVICE INSPECTION

PRAIRIE ISLAND UNIT 1.1994

,

APPENDIX A

INTERVAL 2 PERIOD 3 INSPECTIONS BY ISO.

14 Pages

,

.

4

i

.

, , ,

,

,. /

i

.

IR NO. 50 282/97003(DRS); 50 306/97003(DRS)- ATTACHMENT A, Page 7 of 21

-

-

.

,

,

e

.

i

1

Prairie Island Neoloar Generating

Inservioe Iaspect. ion Report Imgr

IIerthern States Power Campany

'

1117 lumheande Drive

Seoemd laterval

Dr Iso /Itama

414 Nioollet hil

.

teoloh, Raf $5889

Commercial servios Date: ' " -- 18, 1913

m=epelis, Mr 55481

l

ISO

Item

Saport 3rumber

Method

Results

System

Iteen Descriptien

Rame Date

AEME Secties XI Themn

IS!- 1A

W-3

94-0033

PT

NAD

1

CHARGIN2 LINE

'8'

EL80W = PIPE

05/10/94

8 9. 21

IS! 18

W1

94-0034

PT

NAD

OMR$1NG LINE

'B'

Valve - P!PE

05/10/94

8 9. 40

6

S:* ~ 3

W7

94-0200

PT

NAD

,' OMAR3:NG LINE *B'

ELBCH - P:PE

06/01/94

8 9. 21

e

S~~ ;E

W-3

94-0124

PT

NAD

Chat *:NG LINE

'8'

4 5 e ELBCW - P1PE

05/20/94

8 9. 21

S*- ;r

5.

94-0061

VT1

NAO

.m AS:NG LINE

'B'

EOLING $ WELO$ *1672

05/13/94

87 50

1

!$ - 2.

F-3 (SIRM-24)

94-0130

PT

IN*

A:7.v . DISCHARGE ' A'

WILDED ATTACHMENT

05/20/94

810. 10

SPOT INDIC2 T * M

1-2

'- 3 (SIRM-24)

94-0069

VT3

Ih;

CT.M. O!$ CHARGE

'A'

SPMNG HAMER

05/13/94

F-A,B,C

!NCORPICT ! F* : O

I

!*-

2

F-3 (SI PJ4-2 4 )

94-0068R1

VT3

NA':

A*LT. O!SCMARGE

'A'

SPMNG HA$~,IR

06/24/94

T-A,8,C

RIWORKED

. *3:- 2

H-3 (SIRH-24)

94-0130R1

PT

WA3

l ATJM. DISCHARGE ' A'

W.I.0ED ATTACHMENT

05/28/94

810. 10

ENGINEP. RING EVALUATION

S-2

$2-6-4

34-0065

VT1

IND

,,,, g

/

in

A nN. DISCHARGE ' A'

Valve Bolting

05/13/94

87 70

(,

LACK OF TH22.A? ENGA*ENENT

S-2

51-6-4

94-00658.1

VT1

NA:

A0%H. DISCERGE ' A'

Valve Bolting

05/27/94

8 7. 70

ENGINEERING CVAL*JAT!OM

ISI- 2

W-3 (W-6)

94-0058

PT

IND

AO*LN. DISCHARGE

'A'

EL334 - PIPE

05/12/94

8 9. 11

LINEAR

ISI- 2

W-3 (W-6)

94-0059

UT45

NAD

A rJM. DISCHARGE

'A'

EL30W - PIPE

05/13/04

8 9. 11

IS:- 2

W-3 (W 6)

94-0058R1

PT

NAD

ACOJM. DISCHARGE

'A'

E:.304 - P2 PE

06/02/94

8 9. 11

MINOR BUFFIN*

ISI- 3A

H-6 (9-RHR-13)

94-0105

VT3

NAD

M A LOOP

'A'

RUP URE RESTRANT

05/19/94

r-A,B,C

S:- 3A

HV32164 1-f702A

94-0106

VT1

s INO

PJ.R LOOP

'A'

Va;ve Bolting

05/19/94

B7 ?0

BORIC ACID RISf0CI

I IS:- 3A

HV3;164 1-8702A

94-0106R1

VT1

NAD

R.*R Lcr.,,P * A '

valve Bolting

06/07/94

B7 70

CLEANED RESIDUE

IS1- 38

H-1 ( RHPJU4-20)

94-0118

VT3

NAD

RHR LOOP ' A'

CCJ3Lt SPR]NG HANGER

05/19/94

F-A,B.C

ISI- 30

H-9 (9-RHR-68)

94-0095

VT3

, N AD

RHR LOOP

• A'

RUPTURE RESTRAINT

05/17/94

f-A,8,C

151* 3C

H-9 ( RHRPJ4-14 )

94-0094

VT3

NAD

RHR LOOP ' A'

RCD MANGER

05/17/94

F-A,8,C

j

ISI. 5A

CV31224 PCV431A

94-0097

VT!

NAD

$ PRAY TO PRES $URjZER

Va:ve Bolting

05/11/94

81 70

!$1- 5A

RC-19-5

94-0096

VT1

NAD

SPPAY TO PRESSURJ2ER

'"ALVE BOLTS

05/17/94

B7 70

1

IR N0. 50-282/97003(DRS): 50 306/97003(DRS) ATTACHMENT A. Page 8 of 21

39/,,,,4

2

-

.

.

,4

.

Prairie Island woolear ceaezating

Inservie Zaepeation Report 14g

nort.hara states Power Camupany

A

1117 1eakaande Drive

seemed Zatarval

Dy 2ee/Iteen

414 Nieellet Mall

Welsh, 28 55489

Communreial Service Dates Deeeminer 18, 1973

m===P=11a, let 55491

ISO

Iteen

Report Weistner

Method

Reesits

systema

Tteam Demariptimo

Emman Date

A.SMR Seettaa XI flein

St. 5A

W 1 (W 6)

94-0062

PT

D.AD

SPRAY TO PRESSUR11ER

Valve - ELBCW

05/13/94

8 9. 21

31- SC

W13 (W-933/29)

94-0064

PT

NAD

,17MY 70 PRISSURIZER

REQUCER - SATE END

05/13/94

8 9. 10

? 031- SC

W13 IW-933/29)

94-0155

UT45

NAD

6

I?MY TO PRISSUMZER

RICUCER - SATE END

05/23/94

8 9. 10

.

.1:- SC

W-14 (W-29A)

94-0082

PT

NAD

177AY TO PRESSUM:ER

SAFE END

05/16/94

8 5. 40

J:- SC

W14 (W-29A)

94-0129

UT45

NAD

JTuY TO PRI55VA!:ER

SATE END

05/21/94

8 5. 40

f;- SC

W-3 (W-20)

94-0081

PT

MAD

IF AAY 73 PMSSUA:"IR

PIPE - EL80W

C5/16/94

8 9. 21

J:- 50

W-4 (W-21)

94-0063

PT

NAD

!P2AY 70 7'233VM :ER

ELBCW - PIPE

05/*3/94

8 9, 21

l

!!!- SD

Cu 1225 PCV43.1

94-0092

VT1

NAD

J7 AAY 70 PMSSU l'ER

VAI.VE BOLTING

05/11/94

81 10

5:- 50

H-3 (RCRH-1)

94-0016

VT3

IND

J7AAT TO PAISSUM ;ER

SPkING HANGER

C5/14/94

F-A,B,C

LOOSE PARTS

i J - 50

H-3 (RCRH-1)

94-0016R1

VT3

NAD

g

i 17AAY TO PAISSVRI:!R

SPRING HANGER

06/08/94

F- A, B, C

i

ENGINEER!NG T.'A' OA7:ON

'

I3:- 50

H-4

94-0015

VT3

NAD

JFRAY TO PPISSUR;;ER

g!ATERAL RESTRA;NT

05/14/94

F-A,B,C

• il- 50

H-J (RCRH-4)

94-0004

VT3

NAD

37AAY TO P72SSUR1:ER

SUPPOAT BRACKIT

05/16/94

F-A,B,C

i

5

- SD

H-9 (RCRH-5)

94-0085

VT3

IND

$74AY To PMSSUM ER

HYDR SNUBBER

05/16/94

F-A;B,C

MIS $!NG PARTS

'

sI- SD

H-9 (RCRH-5)

94-0085R1

vr3

NAD

j

57 RAY TO PRISSUR;ZER

HYDR SNUBBER

06/08/94

F-A,B,C

ENCINEERING EVALUATION

031- 6

RC-2-1 (1-8001A

94-0066

VT1

IND

r;3 gg7ppy

.A.

Valve Botting

05/13/94

81 10

BOR!C ACID P2S!OVE

lJ:- 6

RC-2-1 (1-8001A

94-0066R1

VT1

NAD

PD Rr! URN

'A'

Valve Bolting

05/24/94

a 1. 10

l

PIMOVED RLST M

lJi- 6

W12 (W-R)

94-0041

PT

NAD-

173 PITUFM

'A'

Branch - Pipe

05/11/94

8 9.

32

"I:* 1

H-6 (RPCH-118)

94-0060

VT3

NAD

'T? TAKI Orr

'A'

C".0

LATERAL RISTRAINT

05/13/94

T-A,B,C

e

SI- 8

W-12 (W-14)

94-0070

PT

HAD

ATD TAkT Orr ' A' HOT

PIPE - Valve

05/13/94

B 9. 40

5!- 9

H-1

94-0014

VT3

NAD

3:S HIGH HEAD *A*

3pgggo MApagR

05/09/94

F-A,B,C

j

I$I- 9

H-3

94-0016

VT3

NAD

$!$ HICH HEAD

'A'

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HYDR SNUBBER / CLAMP

05/09/94

F-A 8,C

ISI-10

pc.1-1

94-0190

VT1

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DDe (ON CRQ$50Vgg) A

Va}yg gg[t[ng

05/31/94

87, 70

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n m /9.

IR NO. 50-282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A. Page 9 of 21

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.

.

O

Prairie Island Noelear Generating

Zaaervioe Zaspecties Report Ieg

Northens States Power capany

1117 mhamade Drive

seeend Interval

By Ise/Iteen

414 Wioollet Wall

s

ineloh, w 55089

ccommercial seavios cate: " - 18, 1973

w a== P lis, W 55401

130

Items

Report member

Method

Rossata

S ys t em

Items Descripttwo

Baans Date

ASM Section XI Item

!5!-10

RPCH-13/C

94-0221

VT3

MAD

DRM (CN CRO$$OVER) A

SPRING MANGER

06/08/94

F- A, 8, C

.

$1 11A

RCVCH-904/A

94-0223

VT3

NAD

$!AL INJ (COP

'A'

RIDGIO PA%:!R

06/08/94

F-A,8,C

• 11-118

H-4

94-0027

VT3

NAD

SIAL INJ I40P

'A'

RUPTURE P.Is!PA N-

05/10/94

F-A, 8, C

e

• J:-118

ROVCH-903/3

94-0222

VT3

NA0

stAL INJ LCOP

'A'

LATERAL $;lPMRT

06/08/94

T-A,8,C

3!-118

VC-1-18

94-0029

VT1

IN:

J LC lNJ LOOP ' A '

Valve Sci: ;

05/10/94

87 70

8ORIC ACI* *is t NE

!! *!!8

VC-7-18

94-0029R1

VT1

NA

JLC INJ LCCP

'A'

Valve Bolt.3;

05/24/94

87 70

REMOVED RIJ!ME

• $;-119

VC - 8 - 7

94-0028

VT1

NA

St.C INJ LOOP

'A'

Valve 8o1.. ;

05/10/94

8 7. 10

!!; uD

8-1

94-0056

VT1

NA?

JLC INJ LCCP

'A'

FLANGE 80*73 9a4fAs3

05/12/94

81 50

-

J

-110

H-1 (RCVCM-901)

94-0054

Yr3

NAC

3LC INJ LCCP

'A'

SPRING HAN3tR

05/12/94

F-A,8,C

i

g

J*-11D

H-3 (RCVCH-fb6)

94-0057

VT3

NAO

'

5tAL INJ LOOP

'A'

ANCHOR SUPPORT

05/12/94

F-A,8,C

\\

,

!i!-110

VC-8-5

94-0055

VT1

NAD

JIAL INJ LOOP

'A'

Valve Boltin;

05/12/94

87. 70

,

- *SI-110

W-6

94-0015

PT

NAD

$1AL INJ LOOP

'A'

PIPE - EL80W

05/09/94

8 9. 21

8

!sI-12A

W-3

94-0236

PT

NAD

' PIACTOR COOLANT

'A'

PIPE - PIPE

06/19/94

8 9. 11

!

j :s:-12A

W-3

94-0238

UT45

GEO

' Pl. ACTOR COOLANT ' A'

PIPE - PIPt

06/19/94

8 9. 11

t

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H-2

94-0017

VT3

NAD

' '!! ACTOR COOLANT ' A'

$UPPORF

05/09/94

F-A,8,C

t

31-128 (131-12)

W-1(RCC a-5;

94-0127

PT

NAD

! PIACTOR COOLANT 'A'

NOZZLE /SArt END/P:PI

05/21/94

8 5. 70

!$1-128 (ISI-12)

W-1 (RCC- A- 5 )

94-C209

UT45

NAD

, 81. ACTOR COOIMT ' A'

NO32LE/ SATE IND/P:PE

06/06/94

8 5. 70

.

LIMITED EXAM

l lS!-128 (!$1-12)

W-3A RCC-A '-D3

94-01088L

UT45

NAD

l RIACTOR COOLANT * A '

LONG KEM t; 50W

05/19/94

8 9. 12

I

LIMITED EXAM

!$1-128 (ISI-12)

W-3A RCC-A *-OS

94-00448L

PT

NAD

FIACTOR COOLANT

'A'

LONG SEM E* BOW

05/11/94

8 9. 12

LIMITED EKAM

151-128 (1$1-12)

W-3A RCC-A-7-DS

94-01078L

UTO

HAD

RfACTOR COOLANT ' A'

LONG $EAM ELBOW

05/19/94

8 9.

12

LIMITED EXAM

151-128 (131 12)

W-38 RCC.A-1-DS

94-00458L

PT

NAD

PIACTOR COOLANT

'A'

LONG $EAM WI:,0

05/11/94

8 9.

12

LIMITED EXAM

131-128 (Ist-12)

h-38 RCC-A-1*D$

94-01109L

UT45

NAD

REACTOR COOLANT

'A'

LONG SEAM WILD

05/19/94

8 9.

12

LIMITED EXAM

IR N0. 50 282/97003(DRS): 50 306/97003(DRS)- ATTACHMENT A, Page 10 of 21

3,,2,,,,

2

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e

4

%

Praizie Island Nealear Generating

Za. service Iaspecties Report Lag

Nortbars States Power company

)

'-

Stil hkeaade Drive

Second Intezval

my 2se/2 teen

414 Mioellet nsall

1

melah, net 55088

Cammercial Service Dates h e 16, 1873

Nianeepelia, har 55401

l

l

• 50

Itsen

Sepert h *

h thed

Bass 1ts

.

Sys teun

Items Desertption

Raam Date

A.5NB Feetles XI Iteen

• SI-128 [151-12)

W-38 RCC-A- bDS

94-01098L

UTO

NAD

Pf. ACTOR COOLANT ' A'

14NG SEAM WELD

05/19/94

8 9 12

)

LIMITED EXAM

8 *1 -128 (!$1-12)

W 5A (W-9 DS)

94-003b8L

PT

NAD

tiACTOR COO!JudT ' A'

1DNG SEAM ELBOW

05/11/94

8 9. 12

'

Lt> fred EXAp

.

il-128 (151-121

W-SA (W-9 DS)

94-01128L

UT45

NAD

'LL* TOR COOLANT

'A'

LONG SEAM ELBCW

05/19/94

8 9. 12

j

LIMITED EXAw

-128 (IS!-12)

W5A (W-9 DSI

94-0111BL

UTO

NAD

sIL TOR COOLANT

'A'

LONG SEAM EL8W

05/19/94

8 9. 12

l

LIMITED EXM

1

-128 t!$:-12)

W 59 RCC-A-9-DS

94-00408L

PT

NAD

Q CTOR COC:. ANT

'A'

LONG SEM ELBOW

05/11/94

89, 12

LIMITED EX M

J:-123 (151-;2)

W 58 RCC-A-9-CS

94-01148L

UT45

NAD

• 1b"TOA COO; ANT ' A'

LONG SEAM EL8N

05/18/94

8 9. 12

i

LIMITED EXM

i

lJ"-125 (IS!-12)

W-58 RCC-A-9-CS

94-011381.

UTO

NAD

ta C m COOLANT

'A'

LONG SEAM ELBOW

05/19/94

8 9. 12

j

LIMITED Eu p

j

! -128 (ISI-12)

W-6 (RCC-A-10]

94-0042

PT

NAD

j

2DCTOA COOLANT ' A'

EL80W - PUMP

05/11/94

8 9. 1;

)

,51-128 (151-12)

W-6 (RCC-A-10)

94-0115

UTO

NAD

l *DCTOR COOLANT ' A'

ELBCW - PUMP

05/19/94

8 9. 11

LIMITED EXM

(g { :J: 128 (ISI-12)

W6 (RCC-A-10)

94-0116

UT45

NAD

j ! 32 ACTOR COOLANT

'A'

ELBCW - PUMP

05/18/94

5 9. 11

)

\\../ !

LIM!TED EXM

'

i ;J:-12C (151-12)

W-1 (RCC-A-11)

94-007%

PT

NAD

l 22 ACTOR CCMLMT ' A'

RC PUMP - PIPE

05/13/94

8 9. 11

I

5:-12C (151-12)

W-1 (RCC-A-11)

94-0069

UT45

NAD

FIACTOR COOLANT ' A'

RC PUMP - PIPE

05/13/94

8 9. 11

LIM!?ED EXM

JI-13A (ISI-13)

W-5 (RCC-8-4)

94-0099

PT

NAD

82. ACTOR COOLANT

'B'

ELBOW NO2ZLE

05/17/94

8 5. 10

j

S!-13A (ISI-13)

W-5 (ACC-8-4)

94-0210

UT45

NAD

. DCTOR COO 1. ANT

'B'

EL8OW NO22LE

06/06/94

8 5. 70

LIMITED EXAu

31-138

W-6 (RCC-8-10)

94-0049

PT

NAD

fiA" TOR COOLANT

'B'

ELBCW - NOZZLE

05/12/94

8 9. 11

251-138

W-6 (PCC-8-10)

94-0161

UT45

NAD

PiNCTUR COOLANT 'B '

EL';OW - NO2ZLE

05/25/94

8 9.

11

LIM!TED EXM

15!-138 (ISI-13)

W-3 (RCC-8-7)

94-0046

PT

NAD

c Og OOO ANT

• B'

PIPE - ELBCM

05/12/94

8 9.

11

j

31-138 (151-131

W-3 (RCC-8-1]

94-0158

UT45

NAD

82 ACTOR CCOLANT

'8'

PIPE - ELBOW

05/24/94

8 9. 11

51-138 (151-13)

W-3A RCC-8bDS

94-00728L

PT

NAD

• 1V; TOR COOLANT

'8'

LONG SEM WELD

05/13/94

8 9,

12

LIMITEC EXM

SI-138 (151-13)

W-3A RCC-81-DS

94-00798L

UT45

NAD

RDCTOR COOLANT

'B'

LONG SEM WILD

05/25/94

8 9. 12

LIMITED EXAM

IS!-138 (151-13)

W-3A RCC-87-DS

94-01778L

UTO

HAD

RIACTOR COOLANT * B '

LONG SEAM WELD

05/25/94

8 9. 12

LIMITED ExM

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IR NO. 50-282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A. Page 14 of 21

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06/08/94

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94-0103

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05/10/94

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05/21/94

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05/27/94

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94-0311

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STE AM GENERATOR 612

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05/10/94

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94-0183

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05/27/94

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W-4

94-0219

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06/06/94

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06/01/94

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06/10/94

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ENGINEERING EVALUATION

IR NO. 50-282/97003(DRS): 50 306/97003(DRS)- ATTACHMENT A. Page 15 of 21

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06/10/94

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05/25/94

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W-B

94-0166

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151-431 , ;31- 4 1 '

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05/25/94

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151-43:

H-5 (SOUTH)

94-0023R3

VT3

IND

STEAM GINIRATOR fit

S PRING

06/30/94

F-A, B, C

.

!

ISI-43C

H-5 (SOUTH)

94-0023R4

VT3

NAD

3

\\

STEAM GENERATOR fil

S PRING

06/30/94

F-A,B,C

'

,)

ENGINEERING !VCUATION

)

151-430

H-6 (NORTH)

94-0024

VT3

NAD

STEAM GENERATOR 811

S PRING

05/08/94

F- A, B, C

\\

LOAD VERJF:0A?!ON ONLY

l

151-430

H-6 (NORTH)

94-0024R1

VT3

IND

STEAM CtNIRATOR 811

SPRJNG

05/09/94

F- A, B, C

l

ISI-43C

H-6 (NORTH)94-002 4 R2

VT3

IND

E

STEAM GINZRATOR fil

S PRING

06/08/94

F-A,B,C

J

d

t

ISI-43C

H-6 (NORTH)

94-0024R3

VT3

NAD

4

STEAM GENERATOR 811

SPRING

06/18/94

F-A,B,C

ENGINEERJNG EVCUATION

153-430

H-6 (NORTH)

94-0024R4

VT3

NAD

f

STEAM GINERATOR fil

SPRJNG

06/30/94

F-A,B,C

2

3

IAAD VERIFICA?!ON ONLY

!sI-43C (ISI-59)

COL 4 CONN BLTS

94-0086

VT3

NAD

q

STsAM GENERATOR 811

4 TOP CONNECT BOLTS

05/16/94

F-A,B,C

1

i

i IS!-4 3C 115I-59)

H-18

94-0081

YT3

NAD

STEAM O!NERATOR 811

COLUMN 2 HELICO!L

05/16/94

F-A,B,C

I

j

151-430 (ISI-67)

H-19 COL 3 HELI

94-0090

VT3

NAD

j

STEAM GENERATOR 811

COLUMN 3 HEttCOIL

05/16/94

F A,B,C

151-43D

COL 4 BASE BLTS

94-0215

VT3

NAD

STEAM GENEPATOR 512

8 ANCHOR BOLTS

06/07/94

F-A,B,C

.

J

IS!-43D

H-18

94-0214

VT3

NAD

1

STEAM GENERATOR 112

COLUMN 2 HELICOIL

06/07/94

F- A, B, C

i

]

ISI-43D

H-19

94-0216

VT3

NAD

STEAM GENERATOR 812

COLUMN 3 HELICO!L

06/07/94

F-A,B,C

'

251-43D

H-5 SOUTH

94-0025

VT3

NAD

j

STFht GENERATOR s12

SPRING

05/09/44

F-A,8,C

j

l

LOAD VERIFICATION ONLY

,

IR NO. 50-282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A. Page 16 of 21

. ,,,,,,,,

,

1

1.

._.

_

_

_

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6

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Prairie Island Neoloar Generatlag

Inservice Inspecties Repost Img

Northaza States Power Company

1711 hkeande Drive

Second teterval

Dy 2ee/ Item

414 Nicollet hil

weloh, ler $5609 -

e--elal iavios Datet December 16, 1973

Minneapolis,let $5401

iso

Item

Report Numbar

Method

Results

Systeam

Item Description

Raam Date

A.D48 Section X2 Item

51-43D

H-5 SOUTH

94-0025R1

VT3

IND

$;EM GENERATOR 812

SPMNG

05/09/94

T- A, 8, C

!$1-43D

H-5 SOUTH

94-0025R2

VT3

NAD

JTEM GENERATOR 812

S PRING

06/13/94

F-A,8,C

31-43D

H-5 SOUTH

94-0025R3

VT3

NAD

STEAM GENERATOR 812

SPMNG

06/30/94

T-A,8,C

LOAD VERTT**A!!ON ONLY

SI-43D

H-6 NORTH

94-0026

VT3

IND

STEAM GENERATOR f12

SPRING

05/08/94

T- A, 8, C

LOAD VEPJ P* Tt,T!DN ONLY

!!I-43D

H-6 NOP.TH

94-0026R1

VT3

NAD

3 TEM GENERATOR 612

S PRING

05/09/94

F-A,8,C

$;-43D

H-6 NO C

94-0026R2

VT3

NAD

STEM GENERATOR #12

SPRING

06/13/94

F- A, B, C

$3-43D

H-6 NORTF

94-0026R3

VT3

NAD

STEM GENERATOR 412

SPRING

06/30/94

T-A,8,C

LOAD VERI T!"a"'M 06" Y

!$!-43D

PAD 1 UP R!NG

94-0232

YT3

NAD

STEM GENEPATOR 612

GIRDER SWJ3BER BOLTS

06/13/94

F-A,8,0

$1-43D

PAD 2 UP 3 LING

94-0231

VT3

NAD

JTEM GENERATOR f12

CIMER SWJBBER BOLTS

06/13/94

T-A,8,C

gg

51-43D

PAD 3 UP MNG

94-0230

Vr3

NAD

(

STEAM GENERATOR 612

GIRDER SWJ8BER BOLTS

06/13/94

F-A,B,C

v

,

\\ r

a

51-43D

PAD 4 UP M NG

94-0233

VT3

NAD

STEM GENERATOR 812

GIRDER SWJBBER BOLTS

06/13/94

T- A, 8, C

31-49

W-6

94-0240

UT45

IND

A.V. CLOSURE HEAD

HEAD - F.ANGE

06/26/94

8 1. 40

LINEAR

'S! 49

W-6

94-0241

UT60

IND

R.V. CLOSURE HEAD

HEAD - P ANGE

06/29/94

8 1. 40

LINEAR

31-49

W-6

94-0240R3

UT45

NAD

R.V. CLOSURE HEAD

HEAD - r.M GE

06/27/94

8 1. 40

ENGINEERING EVALUATION

IS!-49

W-6

94-0241R1

UT60

NAD

R.V. CLOSURE HEAD

HEAD - P ANGE

06/27/94

8 1. 40

ENGINEERING EVALUATION

SI-51A

H-9

(MSH-43)*

94-0125

Vf3

N/.D

MIN STEAM ' A'

ANCHOA ELBOW

05/20/94

F-A,8,C

351-!!A

H-9 (MsH-12)

94-0137

VT3

IND

MIN STE%M

'A'

SLAR'G SAAK ASSY

05/20/94

F-A,8,C

LOOSE CONNET"f0M

SI-51A

H-9 (MSH-!2)

94-0137RI

VT3

NAD

MIN STEAM

'A'

BEAR'G 3RAX ASSY

06/09/94

T-A,8,C

PDORK

ISI-51A

W-1 / LS (w3-1)

94-0030

KT

NAD

M!N STEAM

'A'

NQZZLE - P.ED ELBOW

05/11/94

8 9. 12

ISI-51A

W-1 / LS (MS-1)

94-0043

UT45

NAD

MAIN STEAM

'A'

NOZZIE - RED. ELBOW

05/11/94

B 9. 12

LIMITED EKAM

ISI-51A

W-7 /LS (MS-7)

94-0151

KT

NAD

M IN STEAM

'A'

PIPE - ELBOW

05/24/94

C 5. 21

ISI-51A

W-7 /LS (MS-7)

94-0150

UT45

NAD

MIN STEAM

'A'

P!PE - ELBOW

05/24/94

C 5. 21

fIMITED EKAM

-

IR NO. 50-282/97003(DRS): 50-306/97003(DRS) ATTACHMENT A Page 17 of 21

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3

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Prairie Island Weelear Generating

Imrvion Zaspection Report 1,og

leerthera States Power Csepany

'

1717 Wakonada Drive

S*enen Interval

By Ise/Itama

414 Nicollet Idall

welah, ter $54e9

c--M servie. Date December 15, 1973

• =valia, ter 55401

ISO

Item

Report Wember

I bethod

Results

Systems

Ttes Demaription

Esas Date

ASaEB Section XI Iten

IS1418

H-2 (MSR-3)

94-0204

VT1

NAD

MIN STEAM

'A'

RESTRAINT

05/23/94

F-A, B. C

i

sI-518

H1 (MSH-10 9)

94-0203

VT3

MAD

M.'

STEAM

'A'

R2DGID SUPPORT

05/23/94

F-A,B,C

l

3 -51C

H-1 (MSH-38)

94-0157

VT3

NAD

M:N STEAM

'A'

BEAR'G BRAK ASSY

05/24/94

F-A, B,C

I

1:-51C (ISI-SIB)

H-2 (MSH-62)

9'.-0153

VT1

IND

M:N STEAM

'A'

DOUBLE SNUBBER

05/24/94

r- A, B, C

HISALIGNMEV"

l!!:51C (151-518)

H-2 (MSH-E2)

94-0153R3

V"3

NAD

[

i 9;h STEAM

'A'

COUBLE SNUB 1LER

05/29/94

T- A, B, C

I

J

5:C (ISI-518)

H-2 (MSH-62)

94-0153R2

VT3

NAD

!*A:% STEAM

'A'

DOUBLE SNUBBER

06/11/94

T-A,B,C

,

ENG]NEERIN3 EVALUATION

I

! :!:-510 (!SI-518)

H-3 (MS DH-23)

94-0154

VT3

IND

'

l

t:s STEM ' A'

SuePORT

05/24/94

T-A,B,C

EXTRA PARTS

j

i ~3:-51C (151-518)

H-3 (MSDH-23)

94-0154R1

W3

NAD

l

'A N STEM ' A'

SUPPORT

06/01/94

F-A,B,C

-

'

l

h

3: 53D

39W / LS

94-0001

PT

NAD

ENGINEER 3NG EVA:.UA!!ON

j

8.-t SUCTION

'B'

PIPE - REDUCING TEE

05/03/94

C 5. Il

!

-

If:-68A

H-4 (MSH-27)

94-0100

MT

HAD

M:NSTT.AM *B'

BEAR'G BRAK ASSY

05/17/94

C 3, 20

]

{

LIMITED EXAW

'

• '

!J'-6BA

H-6 (MSH-29/r)

94-0189

VT3

NAD

MINSTEAM

'B'

BEAR'G BRAK ASSY

05/31/94

T-A,B,C

LIMITED EXAM

3 -68B

H-1 (MSH-30)

94-0135

Vf3

NAD

I

MNSTEM

'B'

BEAA'G BPAK ASSY

05/21/94

T- A, B, C

l

IS -688

H-1 (MSH-30)

94-0207

MT

HAD

!

"A:NSTEAM

'B'

BEAR'G BRAK ASSY

06/03/94

r- A, B, C

LIMITED EXAM

S;-688

H-2 (MSH-4)

94-0134

VT)

IND

)

i

• AINSTEAM

'B'

CONST SUPPORT

05/21/94

F-A, B, C

l

LIHITED EXAM,

EXTRA PARTS

ISI 68B

H-2 (MSH-4)

94-0134R1

VT3

NAD

"A:NSTEAM

'B'

CONST SUPPORT

06/02/94

F- A,8, C

i

ENGINEERING EVALUATION

f

!

15;-68B

H-3(HSH-59)

94-0136

VT)

NAD

'

PAINSTEAM

'B'

HANGER

05/21/94

F-A,B,C

IS -608

H-4 (H-K)

94-0141

VT3

NAD

MA:vSTEAM

'B'

HEADER RESTRAINT

05/21/94

T- A, B, C

S!-688

H-5 (MSH-90)

94-0142

VT3

HAD

"A NSTEAM

'B'

Support

05/21/94

T-A, C 3. 20

IS:-68C

H-1

94-0140

VT3

NAD

PA:NSTEM

'B'

BEAR'G BRAK ASSY

05/23/94

F- A, B, C

l'

ISI-60C (ISI-69B)

H-2 (MSH-68)

94-0147

VT3

IND

l

PAINSTEAM

'B'

HANGER

D5/23/94

F-A,B,C

i

LACK OF THREAD ENGAGEMENT

ISI-68C (131-688)

H-2 (MSH-68)94-014 7 R3

VT3

NAD

,

i

MA NSTEM ' B '

HANGER

]

m..

06/01/94

T- A, B, C

ENGINEERING EVALUATION

l

ISI-68C ( ! $ 1 -f. 9 9)

H-3 (MSDH-24)

94-0156

Vr3

IND

MAIN $ TEAM

'B'

HANGER

C5/24/94

F-A,B,C

HMGER CONrlCURATION

IR NO. 50 282/97003(DRS): 50 306/97003(DRS)- ATTACHMENT A. Page 18 of 21

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.

.

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Prairie Island Nuolear Generating

Isservios Inspeettee Bayert S,og

Northern States Power ca pany

,

.

11111enkomade Drive

second Zaterval

By Ise/Itua

414 Nicollet taali

teelaA les 55089

Ceumarelal servio Date Deose er 16, 1s73

Minneapolis, net 55401

1

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Item

Bsport Isamber

Method

Bess 1ts

,

system

Itesa Descripties

taass Date

ASME seettee 22 Item

j

!$1-68C (!$3-68B)

H-3 (MSOH-24)

94-0156R1

VT3

NAD

MAINSTEAM

'B'

HANGER

06/14/94

F-A,B,C

4

ENGINEERING EVALUATION

IS!-68C !!$1-688)

W-3/LS (MS-135)

94-0032

MT

IND

MA!NSTEAM

'B'

PIPE - ELBOW

05/10/94

C 5. 11

LINEAR

ISI-68C (1S1-68B)

W-3/LS (MS-135)

94-0035

UT45

GEO

MAINSTEAM

'B'

PIPE - ELBOW

05/10/94

C 5, 11

)

GEOMETRY

'

131-680 (!S!-68B)

W-3/LS (MS-135)

94-0032R3

MT

NAD

,

lMA]NSTEAM

'B'

PIPE - ELBOW

05/25/94

C 5. 11

!

{

MINOR Burr!S

!$1 680 (ISI-688)

W-3/LS (M.5- 13 5 ':

94-0035R3

!TT45

NAD

,

. MAINSTEAM

'B'

PIPE - elbow

05/10/94

C 5. 11

i

!RFILEVAN* :C:TATION

ISI-il (*S!-69Al

H-3 (TWH-35/LL)

94-0196

VT3

NA3

FIENATER LOOP

'B'

SUPPORT

05/31/94

F-A,B,C

LIMITE3 EyH

153-46 (;$I-69A)

H-9 (IMH-33/S)

94-0195

VT3

NAD

TEE * ATER LOOP

'B'

SE!SMIC RESTM:N"

05/31/94

r-A,B,C

ISI-6 9 (!SI-69B)

H-1 TWH-42/K

94-0381

VT3

IN3

FIE: MATER LOOP

'B'

SEISMIC PISTRA:NT

05/27/94

F-A,B,C

,

MISSING PA*'5'

151 69 (ISI-6 98)

H-1 IWH-42/K

94-0181R1

VT3

NAD

TEEDWATER LCCP

'B'

SEISHIC PISTRAINT

07/20/94

F-A,B,C

ENGINEERING EVA*,U AT!ON

t ISI-81

SIH-28/C

94-0010

VT3

IND

.,

l R.W.S.T.D.

SEISMIC RESTRAINT

05/06/94

F-A,B,C

'

LOOSE PAR *S

"

IS!-81

SIH-28/C

94-0010R1

VT3

NAD

R.W.S.T.D.

SEISMIC RISTRAINT

05/26/94

F-A,B,C

e

REWORKED

ISI-82

SIH-10/E

94-0224

VT3

IND

i

S.I. PUMP SUCTION

RIGID SUPPORT

06/09/94

F-A,B,C

NO LCAD ON MANG!R

' ISI-82

31H-10/E

94-0224R1

VT3

NAD

S.I. PUHP SUCTION

R2GID SUPPORT

06/16/94

F-A,B,C

RIWORKED

151-82

SIH-11/D

94-0234

VT3

IND

S. I. PUMP SUCTION

RIGID SUPPORT

06/13/94

r-A,B,C

SUPPROT BINDING

151-82

S!H-11/D

94-0234R1

VT3

NAD

S. I. PUMP SUCTION

RIGID SUPPORT

06/20/94

F-A,B,C

REWORKED

ISI-82

SIH-12/A

94-0228

VT3

NAD

S.I. PUMP SUCTION

RIGID SUPPORT

06/10/94

F-A,B,C

ISI-84

SIM-13/B

94-0003

VT3

NAD

3.1. PUMP SUCTION

RIGID HANGER

05/05/94

T-A,B,C

ISI-82

SIM-8/G

94-0002

VT3

]ND

S. I. PUMP SUCTION

RIGIO SUPPORT

05/05/94

F- A, B, C

LOOSE JAM NUT

SI-82

S!H-8/G

94-0002R1

VT3

NA3

S.1.

PUMP SUCTION

RIGID SUPPORT

05/16/94

r-A,B,C

REWORKED

ISI-82

S!H-9/r

94-0225

VT3

NAD

. 5.1. PUNP SUCTION

ANCHOR

06/09/94

F-A,B,C

t

! ISI-82

SIH-90/L

94-0229

VT3

IND

' S.I.

PUMP SUCTION

HANGER

06/10/94

T-A,B,C,

EXTRA PARTS

-

151-82

5!H-90/L

94-0229RI

VT3

NAD

j S.I.

PUMP SUCTION

HANGER

06/22/94

r-A,B,C,

ENG!NEERING EVALUATION

Sn 9/ 9.

IR NO. 50 282/97003(DRS): 50 306/97003(DRS) ATTACHMENT A, Page 19 of 21

1,

,

t 6

4

4

Prairie Island Waelear Generating

laservice Inspection Report Img

Northern states Power Campany

5

1111 Whenada Drive

seeend Interval

my Ise/ Item

414 Ilioellet Mall

W ich,let 55009

t' - esial Servios Dater h h 16, 1973

"--- r-lia, let 55401

250

Item

papert Number

Method

Restita

system

Ttem Description

Enam Date

ASME secties II Ites

153-82

SIH-91/K

94-0005

VT3

IND

5.1. PWP SUCTION

RIGID SUPPORT

05/05/94

F-A,B,C

1.ACK OF THREA) ENGAGEMENT

IS;-12

SIH-91/K

94-0005R1

YT3

NAD

5.;

8.NP SUCTION

RJGID SUPPORT

05/16/94

F-A, B, C

RENDRKED

ISI-t

$1H-92/J

94-0004

VT3

NAL

5,.

PMP SUCTION

RIGID SUPPORT

05/05/94

T- A, 8, C

! -l:

$1H-93/I

94-0227

VT3

IND

3

??P SVCTION

RIGID SUPPORT

06/10/94

F- A, B, C

NO IAAD ON $*i? PORT

, -1:

SIH-93/I

94 -0221R1

VT3

NAD

!.

5.*P SUCTION

R!GID SUPPORT

06/19/94

T-A,8,C

RIWORKED

• 3:-!:

SIH-94/H

94-0211

VT3

NAD

5..

PWP SUCTION

RESTRAINT

06/08/94

,

F-A, 8, C

T:-i;

SIH-95/C

94-0235

VT3

NAD

3.

??? SUCTION

SWAY STRUT

06/13/94

T-A,8,C

"$ -il

$1H-15/D

94-0006

VT3

NAD

5.

T.HP SUCTION

SPRING MANGER

05/05/94

T-A,B,C

IS -534 (ISI-55)

W-3 (W 35)

94-0013

PT

NAD

bP ? ?P

• A* DISCH

Pipe - Elbow

05/06/94

C 5. 11

7

.

S:-E31 (ISI-93)

SIH-18/H

94-0189

VT3

NAD

e

8 8 PWP

'B'

DISCH

SEISHIC RESTRA!NT

05/31/94

F-A,8,C

. <1 * .-

S -i"

W-15

94-0007

PT

NAD

l C:: C I'h?

'8'

DISCH

PIPE - Valve

05/05/94

C 5. 11

'

LIMITED EXAw

IS -fin

W-21

94-0078

PT

IND

RHR F?P

'A'

DIST

valve , PIPE

05/14/94

C 5. 21

h

SPOT

l IS!-tIA

W21

94-0180

UT45

NAD

! R? A P HP ' A'

DIST

Valve - PIrE

05/21/94

C 5. 21

l

LIHTTED EXAM

i 151-114

W-21

94-0018R1

PT

NAD

l PAR PMP ' A' DPST

Valve - PIPE

06/02/94

C 5. 21

HINOR BURRING

ISI-f1A (ISI-89)

W-29 (1298)

94-0031

PT

NAD

R.iR P'.NP

'A'

DISCH

PIPE - E!.80W

05/10/94

C 5. 21

j IS -tiA !!SI-89)

W-29 (1298)

94-0036

0745

NAD

PN' P'.* P ' A ' DI SCH

PIPE - ELBOW

05/10/94

C 5. 21

'

1

i 15! 854 1351-89)

W30 (1299)

94-0010

PT

NAD

' PWR P.NP ' A' DISCH

ELBOW - PIPE

05/10/94

C 5. 21

1 IS:-fit (ISI-89)

W-30 (1299)

94-0037

UT45

NAD

LPM PMP

'A'

DISCH

ELBOW - PIPE

05/10/94

C 5. 21

!

' "SI-!iB

HV-32066

94-0133

VT3

NAD

' M PW P

'B'

DISCH

VALVE INTERNAL

05/21/94

812, 50

.

IS -91A

H-2

94-0011

Vt3

NAD

RHR M DT EXCH 11

SUPPORT

05/06/94

T-A,8.C

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