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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l U.S. NUCLEAR REGULATORY COMMISSION

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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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r 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

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9703200121 970314

PDR ADOCK 05000282

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Report Details

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II. Maintenance

M1 Conduct of Maintenance l

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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.

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

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

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

3-2SI-15C. l

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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 i

examination. '

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," '

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

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, >

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 i

Authorized Nuclear Inservice Inspector. '

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.

e 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).

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

probe.

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

I (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

l 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 'y not

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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e The decision to perform an ET scope that exceeded Technical Specifications

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

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personnel and techniques.

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M1.2 Comorehensive Unit 2 SG Tube Reoairs

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a. Scone (73753, 73755)

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. i

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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

l susceptible to cracking.

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

testing of individual SG tubes.

l 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 ,

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

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 1

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

leakage implications on the bounding leakage assumed in the qualification reports l

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

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

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 1

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

SG-22 R16C38 0.05-0.11 j

SG-22 R13C46 0.00064

The licensee staff determined that the maximum potentialleak rate under MSLB i

differential pressure conditions could have been 0.53 gallons per minute  !

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

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

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, ,

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

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

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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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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 i

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

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 ~

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 '

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

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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

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• 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.

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The inspector reviewed ISI summary reports for Code examinations performed for l

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

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 '

preventing a complete Code volumetric examination. No documentation could be

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

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

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

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listed in Attachment A) that prevented meeting the ASME Section XI Code 4

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

" 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).

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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, ,

which referred to Westinghouse Report WCAP-10363,

" Handbook on Flaw Evaluation, Prairie Island 1 and 2

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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

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licensee to discuss the licensee's basis for the relief

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request and in response the licensee committed to I

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

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request. ]

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January 7,1997 A Request for Additional Information (RAl) was issued l

by NRR staff to obtain clarification pertaining to the l

licensee's basis for this relief request. I

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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)

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

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

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

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

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

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

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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:

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4.1.1.2 Performance Standards l

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

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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

l

UT Ultrasonic Examination 1

VIO Violation l

VT Visual Examination

s

]

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4

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o

NORTHERN STATES POWER SUMMARY REPORT

INSERVICE INSPECTION PRAIRIE ISLAND UNIT 2.1995

i -

APPENDIX A

INTERVAL 2 PERIOD 3 INSPECTIONS BY ISO

5 Pages '

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

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a I

1

Prairie Islead 3haclear Generating Zaservice Zaspection Beport leg

1

Northerm States Power Company

1117 wakonade Drive second Zaterval By Zoo / Item

solch, set $5089 414 Micollet Mall '

Commercial service Dates December 20, 1974 ulamaapo118, MN 55401

i

j ISO Item Beport Nueber

, Method Results

Byeten Item Descriptico Buem Date (

l

ASMB Section 22 Item l

2 131 1A Flange S W-2 95-0033 VT1 NAD

Seal Injectic,a A Flange / Pipe 05/19/95 B1 50

4

l

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

d

Examined ir place

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

I

l 3; rey Te P*r 3r A Safe End/ Nozzle 05/22/95 8 5. 40

i Limited exa-

!S;- 70 I

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 l

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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Prairie Zeland Nuclear Generating Zaeervice Inspection Report Log

"

1111 Wakemade Drive 3 fort 3nera States Power Campeay

second Interval By Zoo / Item

414 Nicollet Itall

j

t

unich,1st 55069 Ccamercial service Dates December 20, 1974

<

i ulnacepolis, ta8 55401

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

j

I

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

w Seal House 06/07/95 l 8 7. 60

l l Examined D.sasse. bled

. . :3*-43 Bolts Pump & 95 0066 Vr1 NAD

i

P. p 22 SH Bolts Upper Seal Heuse {

{A 06/07/95 B7 60 I

i

. ;J; 43A

,

Examined dis asse eled

W- 1 95-0010BL VT1 NAD 1

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 B 6.180

{05/26/95

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

s . *5*-44 Bolts 1 - 24 95-0063R1 VT1 NAD j

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 .

* 5 * 4 6A MSH 39/F 95 0019 MT IND

IF*dnSteamA Support 05/11/95 C 3. 20 / IW7

Linear Indi:a: ion I

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 VT3 NAD

Main Stear. A l95-0022

Hanger 105/18/95 Iwr .

}

.

1

_ . .2 :5: 469 *r.3H-91/T 95-0025 VT3 NAD j

Maan Steam A l Support 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 . _ _ _

09non5

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

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$

.

. Preitie Zeland Nuclear Generating Inservice B ; ntion Report Log

1717 wakoaade Drive Nort.hern states Power Campany

second Interval Dy Iso / Item

welch lef 55049 Commercial service Dates December 20, 1974 414 Mico11st mall

wi- w polie, let 55401

Iso Item Report Number Method

Systen Item Description Results

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

2 ;5I 47B Limited exa.a

,

MSH-26 95-0023 VT3

j w NAD

.ain Steam B Support 05/18/95 IWF

L;-;5 473

-

MSH 66/M

5

95-0020 VT3 IND

watr. Steam B Support 05/18/95 IWF

i

. ;5;-4 7B

Loose nut

MSW 66/M 95-0020R1 VT3

!

NM

• nr. Steae 3 Sepport '06/02/95 IMF

f

j Repaired

. ;S;-473

-MSH-90/R '95-0024 VT3 NAD

)l *n , Steam B Support '05/18/95 IWF

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

i l

4

. ;3;-44A

} Limited exa: l

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

2-IS;-49A

Limited exas

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

SI Pump 21 Suction

Prr NAD~

! 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 VT3 NAD

j S: Pump 21 Suction l95-0003

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

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I

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

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- Prairie Island Nuclear Generating laservice Inspection Report Log Northern Statee Power Company

1717 wakonada Drive Seceed Interval By Zee / Item

Welch, set 55049

414 Nicollet Mall

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

[ 2 ;$1-77 Column 3 Base 95 0061 WO NAD

.f 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 l

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 I

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 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

., . . .

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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

I mw GENIRATOR 22 lCirderSpssngM1R 06/13/95 aWF

I l Engineering eva*uation

.

. "J;-35 'UP RING H3R 4 95-0000 VT3

~

IND

1 I;# GINTRATOR 21 Girder Spring MOR 05/12/95 IWF

i

verified Icat setting only at

I l 538'r out 10%  !

[.11*85 ;UP RING H3k 2 95-0010 VT3 i IhT ~ <

$ $TIJ? GENERATOR 42 Girder Spring M3R 05/12/95 IWF '

{ Verified 1cas se ting enly

'

10% out at !!i'T f {

.. L 45 UP RING H3R 2 95-0010R1 fr3 IND~~ '

, ITI)? 3ENERATOR 22 , Girder Sprin; H3R 05/17/95 , IWF

, '

! 0%

1 out et "!'T

T *S* 45 UP RING H3R 2 95-0008R1 VT3 NAD

17T).* GENERATOR 21 Girder Spring N3R 05/17/95 IWF

At 75'F

T ;SO-45 95-001012 VT3 NAD

lUPRIrlGHGR2

STIl# CINTRATOR 22 ' Girder Spring E3R 06/13/95 IWF 1

'

,' ' Engineering evaluation

27 !E 85 UP RING HGR 2 95 0004R2 VT3 8 NAD ' j

G M GINERATGR 21 Girder Spring X3R 06/13/95 IWF .

Engineering evaluation

AX ;;06-14 ATWW-74 95 0043 VI) IND ~~

A"X FIIDWATER Daal Spring Ha.ger 05/19/95 IWF

1,oad setting la:orrect I

X3 .106-16 ATWM-74 95-0043R1 VT3 NAD ,

A*JX TIEDWATER Dual 4,pring Hanger 05/30/95 IWF '

Repaired

1

1

l1

1

1

1

.

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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

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Prairie Island Neoloar Generating Inservioe Iaspect. ion Report Imgr IIerthern States Power Campany

1

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.

1117 lumheande Drive Seoemd laterval Dr Iso /Itama

teoloh, Raf $5889 414 Nioollet hil

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

CHARGIN2 LINE '8' EL80W = PIPE 05/10/94 8 9. 21

1

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 l

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

,,,, g S-2 $2-6-4 34-0065 VT1 IND

/ 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

39/,,,,4 IR N0. 50-282/97003(DRS): 50 306/97003(DRS) ATTACHMENT A. Page 8 of 21 2

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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 05/14/94 F-A,B,C

g!ATERAL RESTRA;NT

• 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 l

lJi- 6 W12 (W-R) 94-0041 PT NAD- I

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 I

$!$ HICH HEAD 'A' HYDR SNUBBER / CLAMP 05/09/94 F-A 8,C

%

ISI-10 pc.1-1 94-0190 VT1 NAD

DDe (ON CRQ$50Vgg) A Va}yg gg[t[ng 05/31/94 87, 70

__

n m /9.

IR NO. 50-282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A. Page 9 of 21 2

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O

Prairie Island Noelear Generating Zaaervioe Zaspecties Report Ieg

1117 mhamade Drive Northens States Power capany

s

seeend Interval By Ise/Iteen

414 Wioollet Wall

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

) :31-128 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

3,,2,,,,

IR N0. 50 282/97003(DRS): 50 306/97003(DRS)- ATTACHMENT A, Page 10 of 21 2

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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 l

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' l

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 I

1

-128 t!$:-12) W 59 RCC-A-9-DS 94-00408L PT NAD l

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

S!-13A (ISI-13) W-5 (ACC-8-4) 94-0210 UT45 NAD j

.* DCTOR COO 1. ANT 'B' EL8OW NO22LE 06/06/94 8 5. 70  !

LIMITED EXAu I

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

151-138 (15!-13) W-38 RCC-87-DS 94-0050BL PT NAD

RIACTOR COOLANT 'B' LONG SEAM WELD 05/12/94 8 9, 12 l

LIMITED EXM l

1

un9/94 IR N0. 50 282/97003(DRS): 50 306/97003(DRS)- ATTACHMENT A. Page 11 of 21 *

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j

Prairie Island Weslear comerattag Imeervio. Inspecties 8mport I,og parthern States Power Campany

111114akeande Drive $+oemd Intezval Dy Ise/Itamm 616 Wioellet Idall

teoloh, lef 55888 t h -oial Servioe Dates n-a==e == 16, 1973 W a=aapalia,hef $$481

ISO Itass 8mport Member Method Beaulta

'

systems Itan Description Baann Date ASMB 8eeties XI Ttan

j  !$1-138 {!$1-13) W3B EC-81-DS 94-00808L UT45 NAD

RZACTOR C008Jurf 'B' LONG SEAM rdD 05/24/94 8 9. 12

LIMITED E2A*4

, !51-138 (ISI-13) W 38 RCC-81-OS 94-01648L t/TO NAD

REACTOR CCOLANT 'S' 14HC SEAM rdD 05/25/94 8 9. 12

LIMITCD EJAM

I lS!-138 (151-13) W-5A KC-3-9-OS 94-00518L PT NAD

MACTOR COOLANT 'S' LONG SCAM rd D 05/12/94 8 9. 12

LIMITED 1.8Au

4 :SI-138 1131-13) W-5A PCC-8-9-OS 94-01633L UT45 NAD

'

RIACTOR COOLANT 'B' LONG SEAM We*,7 05/25/94 8 9. 12

I LIMITED DAW

j  ! l$I-133 (ISI 13) W-SA KC-9-9-OS :94-01783L UTO NAD

"

?2.AC-OR COOLANT *B' IONG SEA,*t b*t* : 05/25/94 8 9. 12

{ LIMITED EXAM

, :S;-138 (:51-131 W-58 PCC-8-5-03 94-00528L PT NAD

EA TDR C00LAN- 's LONG SEAM WIL: C5/12/94 8 9. 12

LIMITCO daw

S -;35 (151-131 W-58 E C B-9 OS 94-0162BL UT45 NAD

,

PIA-*0R COOLANT *E LONG SEAM W L 05/25/94 8 9. 12

LIMTTtD ! 9.*

) j 32-133 (151-13) W-58 MC-8-1-;$ 94-0114BL UTO NAD

[ *IAC OR Cool. ANT *s LONG SEAM W

.LO C5/25/94 8 9. 12

• '

'IMITED E:G.*

g 031-14 H-3A 94-0091 VT3 NAD

P M PUMP 11 T!E BACK BOLT t 3 05/16/94 F-A,8,C

.l

s g !SI-14 H-4 94-0061 YT3

NAD

i C PUMP 11 PAD 1 05/16/94 T-A,8,C

,,,5

_ 131-14 PUMP ill 94-0119 MT IND

8

AC PVMP 11 FLYWHEEL PERIPHERT 05/20/94 TS 4.2-1

1 LINEAR

l  !$1-14 PUMP 811 94-0120 MT NAD

C PUMP !! FtY'a14tEL BODY 05/20/94 TS 4.2-1

!$!-14 PUMP 811 94-0123 UTO NAD

j RO PUNP 11 FLWHCtL PERIPHERY 05/20/94 TS 4.2-1

i

, 151-14 PUMP fil 94-0119R1 HT MAD

i RC PUMP 11 FLYWHEtt PERIPHERY 05/20/94 TS 4.2-1

2 ENGINEERIN3 EVAI,UATION

!$1-14 (ISI-61) 8-4 94-0172 VT1 IND

M PUMP 11 UPPER SEAL HOUSING 05/21/94 8 7. 60

"

PITTING

"

152-14 (151-61)  :-4 94-0172R1 VT1 NAD

M PUMP 11 UPPER SEAL HOUSING 05/31/94 81 60

REPLACED 90*,TS

ISI-14 (!$1-615 COLUMN 3 94-0088 VT3 NAD

I *4C PUMP 11 TOP CONNT.CTING BOL*S 05/16/94 F-A,8,e

2

151-14 (15!-64) H-28 94-0102 VT3 NAD

RC PUMP 11 Tit BACK PIN 9 2 05/16/94 F-A,8,C

.i IS!-17 H-3 94-C206 VT3 NAD

'

12* ACCUMULATOR DSCH RUPTURI PISTRAINT 06/02/94 T-A,8,C

I

< ISI-17 $1-6-2 94-0205 VT1 NAD

j 12* ACCUMULATOR DSCH valve Botting 06/02/94 81 70

i

!$!-18 MV-32066 1-8703 94-0136 VT1 NAD

10 RHR RETURN Loop 8 Valve Bolting 05/21/94 81 70

.

!$!-18 W-5 (W-29/5) 94-0146 PT NAD

i 10 PJiR RETUPJ4 LCOP 8 PIPE - 65e EL90W 05/23/94 8 9. 11

1

.,n ,,,4 IR NO. 50-282/97003(DRS): 50 306/97003(DRS)- ATTACHMENT A. Page 12 of 21 5

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Praizie Istnad Nealear Generatlag Zaservice Zampeoties paport I.cf Northara States Power Company

a

g 1717 Wakenado Drive Seocad Zaterval By Zee /Iteen 614 Mioellet Mall

Welch, nas 55089 C - rotal servio. Date: December 16, 1915 Miameepe11a, nas 55401

ISO Itama Report Nummber Method Reasits

Sy s t eun Iteen Desertption Raama Date A3ME Seettoa XT f teen

ISt-19A h-10 (9MR-14/P 94-0160 VT3 NAD

8* MR TAXE Orr 'B' RUPTURE DJ.STRAINT 05/26/94 T-A,8,C

SI-19A HV-32231 187018 94-0187 VT1 NAD

f * RHR TAXI Orr '8' Valve Bolting 05/23/94 87 70

St-19A HV32231 1 87018 94-0159 VT3 NAD

l' RdA TAXI Orr 'S' VALVE INT SURTACES 05/25/94 812. 50

o

! ;SI 19A (!$1-19 8) H-2 1-RHR-10/H 94-0169 W3 NAD

f * RHR TAX 1 Orr 'B' RUPTURE RESTRAINT 05/26/94 T-A,8,C

31-198 H-2 RHRN4-25/C 94-0161 W3 IND

!* RHL TAXI Orr 'S' EOUELE SPRING HANGER 05/26/94 F-A B.C

t HOT LOAD SE*"*** M :a.*2CT

5 -199 W-2 RHRM4-25/C 94-0167R1 VT3 NAD

, f* RNR TAKE Orr '8' EOU8LE SPRING MANGER 06/02/94 r- A, 8, C

!

RDout0

25 -21 W-12 94-0047 PT NAD

2* RTD RETUM W P 5 BRANCH 05/12/94 8 9. 32

S

-21 W6 94-0077 PT NAD

i 3 * RTO RTETUM Loo? 8 P!PE - ELSE*. 05/14/94 8 9. 21

l

5:-22 W1 94-0073 PT NAD

2* RTO TAKE0rr CLC 5 Branch - Pipe 05/14/94 8 9. 32

94-0093 (

(3

,- l:SI-24 (151 20) 31-9-1, 1-88428 Vil NAD

'

} 6 * $15 HIGH HEAD'B' valve Bolting 05/17/94 8 1. 70

%. , / s

23;-24 (ISI-20) W-21 (WR) 94-0074 PT NAD

$* $15 HICH HEAC'8' BRANCH 05/14/94 8 9. 31

ISI-24 (151-20) W-21 (WR) 94-0126 UT45 NAD

6* $12 HIGH HEAD'8' BRANCH 05/21/94 8 9. 31

LIMITED EXAu

ISI-26 14V-428 94-0211 VT1 NAD

2 CVCS LE.%WN 'S' Valve Bolting 06/06/94 8 7. 70

151-278 W-8 94-0021 PT IND

2*-1.5* SEAL .1NJ'8' PIPE - REDUCING TEE 05/09/94 8 9. 21

LINEAR

lSI-278 W-8 94-0021R1 PT NAD

2 *-1. 5 * SEAL IN J '8 ' PIPE - REDUCING TEE 0$/25/94 8 9, 21

MINOR BurFING

151-278 (ISI-27A) N-4 ( ROVC H- 9 * 9 )' 94-0019 VT3 NAD

SEAL INJ'8' SUPPORT BRACKET 05/09/94 F-A,8,C

151-278 !!SI-27A) H-5 RCVCH-1293 94-0018 %T) NAD

SEAL INJ'8' HYR9 SNUBSER 05/E9'94 r- A, 8,C

151-278 (151-27A) W-11 (10851/9A) 94 0022 PT NAD

SEAL INJ'B' Valve - PIPE 05/09/94 8 9. 21

i

51-278 (ISI-27A) W 5 16162/14) 94-0020 PT NAD

'

SEAL INJ'B' EL8N - P!PE 05/09/94 8 9. 21

]

ISt-29A W-1 (1A) 94-0053 PT NAD

PRIS$ SAFETY LINE A NOZ2LE - SAFE END 05/12/94 8 5. 40

IS!-29A W-1 (IA) 94-0173 UT45 NAD

PRESS SAFETY LINE A NO1!LE - $ Art END 05/27/94 8 5. 40

LIMITED EXAM

IS!*2 9A { ! S I-2 9) Rc - 10- 2 1-60108 94-0140 VT) NAD

PRESS SArtTT LINE A TLANCE DOLTING 05/21/94 87 50

,,,,,,, IR NO. 50-282/97003(DRS): 50 306/97003(DRS) ATTACHMENT A, Page 13 of 21 s

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Prairie Island Weelear Generating Zamervios Inspection Report 3,og parthern states Power Casspany

1717 hkeaada Drive sesend Zaterval By Ise/Itama 414 Nicollet Mall

• Wolah, W 55009 P-esial Service' Datei he 18, 1973 Mimasepolis, W 55401

4

IJe Item Report Wed,er Method Resulta

'

system Itema Description E. mass Date A.IME Sectie a XI Items

• S:-30A V-2 94-0128 VT) IND

d

RIA "'OR VESSEL $18 A VALVE INT SUATACiS 05/21/94 B12. 50

l

^

-

DENTS IN SEATING AREA

g

$

DA V-2 94-0129R1 W3 NAD '

j UADR VESSEL SIS A VALVE INT SURTATES 05/21/94 B12, 50

$ ENGINf_ERN EVR,UATION

f :s:-108 W1 94-0231 PT NAD

*D""OR VISSE.L SIS * SAFE END 06/19/94 8 5. 10

l

f: 2:3 W-7 94-0239 UT45 NAD

l

} rD.OR %T.SSEL S!$ B SAFE END 06/19/95 B 5. 10

i

~

t 112-RC-24/B 94-0226 W3 NAD

t .U;ER RELIEF RUPTUPt PISTPA NT 06/08/94 T-A,B,C

I

J: !". CV-31231 * 94-0139 VT1 NAD

7'i3 E U ER RELIEr Valve Sol:1n; 05/21/94 3 7. 10

3 .. CV-31232 (*) 94-0138 VT1 NAD

7:IJ!.C*ER RELIET Valve Bolting 05/21/94 81. 10

1: - !'. W1 94-0083 PT NAD-

7t!JJ.'C ;ER RELIEF NO21LE - SAFE EN: 05/1f/94 8 5. 40

1:-3; W-1 94-0115BL UT45 NAD

Pti!JUR :IR RELIEF NO22LE - SArt EN 05/21/94 B 5. 40

LIMITED EUN

O

k .-

• E: .

P82fiaC*tR RELIEF

W-2

SAFE-END / RI '.**ER

94-0049

05/12/94

PT

B 5.130

NAD

lJ:-3; W-2 94-0114 UT45 NAD

przynt;gR pILIEr SAFE-END / PJ.DUCEn 05/27/94 8 5.130

!$ 12A CV-31329 94-0199 VT1 NAD

AA*;*ARY SPRAY Valve Bolting 06/01/94 B1 10

~

5:-32A H-2 RCVCH-1990 94-0201 VT3 IND

A;'X::, ARY SPRAY SUPPORT BRACKET 06/01/94 T-A,B,C

LACK OF TH#iAD ENGAGEMENT

l8 !2A H-2 RCVCH,1990. 94-0201R1 VT3 NAD

W.*G*.;ARY SPRAY SUPPORT BRACKIT 06/16/94 T-A,B,C

REWOPXED

5 -135 N-1 94-0194 VT3 NAD

• N -IAD RV INJ ' 9 ' SPRING MANGER 05/31/94 T- A, B, C

5

-34 PUMP #12 94-019e UTO NAD

R. O . PWP 'b'rL NtEEL KEYWAY 05/23/94 TS 4.2-1

l3:-34 (151-61) COLT'MN 1 94-0094 VT3 NAD

M 7'HP 12

.

CONNECTION BOLTS (4l 05/16/94 F A,B,C

!

-34 ( $1-61) N-38 94-0009 VT3 NAD

P' **P 12 TIE BACK PIN 43 05/16/94 T-A,B,C

!!:-34 (151-61) PUHP 912 94-0122 MT NAD

R. ~. PJMP ' B ' FT.YWWEEL PERIPHERY 05/20/94 TS 4.2-1

IS -34 f151-61) PUHP 512 94-0121 MT NAD

R 0. PUMP 'B'rLYWHEEL BODY 05/20/94 TS 4.2-1

!$1-34 (153-61) PUMP $12 94-0119 UTO NAD

R 0 PJMP 'B'rLYWHEEL PERIPHERY 05/21/94 TS 4,2-1

ISI-14 (151-611 PUMP 912 94-0191 UTO NAD

R.C PUMP 'B'rLYWHEEL BODY 05/23/94 TS 4.2-1

,,,,,,,, IR NO. 50-282/97003(DRS): 50-306/97003(DRS)- ATTACHMENT A. Page 14 of 21 7 ,

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Prairie Zaland poelear Generating laservice Kaspectica asport 2.eg aparthern States Power Campaar

• .t 17119taheeade Drive Semeed Interval By Zae/2tems 616 alleellet 38a11

welek,ter 5508B Ceemerelal sezvios Dates Deemmber is, 1913 wa - H 8=, les 55401

)

i ISO Item Aspert 3rumber ninthod haas1ts

Systems Ttem Description Enam Date ABS Seettoa XI Item

l 151-34 (151-641 N-3A 94-0101 VT3 NAD

RC PUMP 12 l

<

TIE BACK BOLT e3 05/16/94 F-A B.C

35 -41 (ISt-73) H-1 BASE BOLTS 94-0208 VT1 NAD

'

P7ISSUMIER &% TING BASE /Sr:RT 06/06/94 F- A, B, c  !

l

S:-42 N-1 IR 94-0213BL trTO NAD i

P7ISSURIZER SURGE NCZ2LE 06/01/94 8 3.120

S:-42 lk-2 IR 94-01938L UT70 NAD

P 23SURI:ER l SPRAY NO22LE 05/31/94 8 3.120

1

S* 42 h-1 IR 94-0145BL UTO NAD

782SSURIZER FIL!ET NO::LE 05/10/94 8 3.120

S*-42 I

h 4 A IR 94-0152BL UTO NAD

3

PPISSURJ2&R  ! ATETY NO:2LE 05/10/94 8 3.120 l

!! -42 N-48 1R 94-0144BL UTO NAD

• • IS3UR22ER 55TETY N;;;*! 05/18/94 8 3.120

S!-41A (151-43) OJT:,ET 1-:( 94-0182 NT NAD

STEM GENERATOR 111 PJNdAY BO:,TS 05/27/94 8 1. 30

S:-43A (151-43) W.A 94-0131 UTO NAD

STEM GENERATOR f11 T'.it SHEET / HEAD 05/21/94 8 2. 40  !

LIHf7ED EJ M

g :S -43A (151-431 W-A 94-0132 UT45 NAD

g STEM GENERATOR 811 TURE SHEET / HEA3 05/21/94 8 2. 40

(, LIMITED EXA'4

,

l

lS:-4 3A (151-4 3) WA 94-0143 UT60 IND

STEAM GENERATOR fit -;11 SHEET / MEAS 05/23/94 8 2. 40 l

LIMITED EXAM, LINEAR j

ISI-43A (181-43) W-A 94-0143R1 UT60 NAD  ;

STEAM GENERATOR fil TU3E SHEET / H!,AD 06/08/94 B 2. 40 1

ENGINEERING ! VALUATION i

ISI-438 TV RING / SUPPORT 94-0104 VT1 NAD I

STEAM GENERATOR 812 N-! TW NOZ3EL SUPT 05/18/94 IN

151-438 W-T UPPER 94-0103 VT1 NAD

]

STEAM GENERATOR 612  !!MSITION - SHELL 05/10/94 IN j

15!-438 IIS1-4 3) I CET 1-16 94-0184 MT NAD

j

STEAM GENERATOR fil PJX4AY BOLTS 05/21/94 8 1. 30

ISI-438 (131-43) ICET 1-16 e4-0125 NT NAD

STEAM GENERATC:t $12 "J# DAY BOLTS 05/27/94 8 1. 30

151-439 (ISI-43) N . / 1R 94-0311 MT NAD

STE AM GENERATOR 612 N;;;LE INNER RADIUS 05/10/94 C 2. 22

LIMITED EXM

151-4 3B (151-4 3) OJTLET 1-16 94-0183 MT NAD

STEM GENERATOR 612 "AWAY BC:,TS 05/27/94 8 7. 30

l

15!-438 (ISI-43) W-4 94-0219 UTO NAD

STEAM GENERATOR 812 "J3! SHEET / HEAD 06/06/94 8 2. 40

LIMIP*D EXM i

151-43B {ISI-43) W-A 94-0218 UT45 IND I

STEAM GENERATOR 112 TU3E SHEET / HEAD 06/07/94 8 2. 40

LIMITED EA/.M. LI N EAR

15!-438 (151-43) W-4 94-0220 UT60 IND i

STEAM CENERATOR 112 T*,BE SJEET / HEAD 06/01/94 8 2. 40 I

LIMITED EXAM, LINEAR

151-438 (ISI-43) W-A 9 4 -0218 R3 UT45 NAD i

STEAM GENERATOR 812 TLBE SWEET / HEAD 06/10/94 8 2. 40 j

ENGINEERING EVALUATION  !

l

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

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4

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j Prairie Island Weslear Generating Immervioe Zampesties hepert I,og

5 Northern states power Camgmar

1111 m heaade Drive seemed Zaterval Dy Ise/ Item

3  % 1eh,ner $5B09 414 Nieellet les.11

Ceumercial Servios Date Decamener 16, 1973 Minneapolia,lef $54B1

i

a ISO Item Report Number 34sthed

systems

Resulta

} Items baseripties Emass Date ASMS Seaties XI Items

!$1-439 (131-43) W-A 94-0220R1 UT60 NAD

j STt.AM CENERATOR ft2 TUBE SHEET / HEAD 06/10/94 8 2. 40

,

ENGINEERIN.i TVALUATION

j IS!-438 (ISI-43) W-B 94-0165 UTO NAD

STEAM GENERATOR 812 TUBESHEET .- SHELL 05/25/94 C 1. 30

LtHITED EJA*

1 152-438 !!SI-43) W-B 94-0166 UT45 NAD

f STEAM GINERATOR 812 TUBESMEET - SHELL 05/25/94 C 1. 30

j *

LIMITED EXA*

, 151-431 , ;31- 4 1 ' W-B 94-0168 UT60 NAD

STEAM GENERATOF #12 TUBESHEET * SHELL 05/25/94 C 1. 30

LIMITED E7A"

1$! 43; COL 4 BASE B~~TS 94-0212 VT3 NAD j

$*EA* 31NIRATOR 811 B ANCHOR BOLTS 06/07/94 F-A,B,C

i

Is!-43: H-5 (SOUTH) 94-0023 VT3 IND

j $*EM GENERATOR 111 S PRING 05/08/94 F-A,B,C

j NO LOAD

IS ;- 4 3.* H-5 (SOUTH) 94 -002 3R.1 VT3 NAD

STIA* SINI8ATOR 111 SPRING C5/09/94 F- A, B,C

f ISi-43; H-5 (SOUTH) 94 -002 3 R2 VT3 NAD

} STEA* GINIRATOR fil SPRJNG 06/08/94 F- A, B, C

j 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

2

STEAM GINERATOR fil SPRJNG 06/30/94 F-A,B,C

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

,

. ,,,,,,,,

1

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

1. ._. _ _

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

-

3 ,,,,,, IR NO. 50-282/97003(DRS): 50-306/97003(DRS) ATTACHMENT A Page 17 of 21 3

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~ . ~. -. . - - . - - - - -. . . ~. -- - . . -- -=

I 9

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4

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Prairie Island Weelear Generating Imrvion Zaspection Report 1,og

1717 Wakonada Drive leerthera States Power Csepany

S*enen Interval By Ise/Itama

welah, ter $54e9 414 Nicollet Idall

c--M servie. Date December 15, 1973 *=valia, ter 55401

ISO Item Report Wember I bethod

Systems Ttes Demaription Results

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

l

05/23/94 F-A,B,C

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

M:N STEAM 'A' IND

DOUBLE SNUBBER 05/24/94 r- A, B, C

HISALIGNMEV"

l!!:51C (151-518) H-2 (MSH-E2) 94-0153R3 V"3

i 9;h STEAM 'A' NAD

[

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 '

l t:s STEM ' A' IND

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

'

l F-A,B,C

h 3: 53D ENGINEER 3NG EVA:.UA!!ON

39W / LS 94-0001 PT NAD

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)

I 94-0135 Vf3 NAD

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

S;-688 LIMITED EXAM

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

! 15;-68B

H-3(HSH-59) f

' 94-0136 VT) NAD

PAINSTEAM 'B' HANGER 05/21/94 F-A,B,C

IS -608 H-4 (H-K) 94-0141

l

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

i NAD

MA NSTEM ' B ' HANGER 06/01/94 T- A, B, C

] m..

l ENGINEERING EVALUATION

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

,/2 ,/,4

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

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. _ , . . . - . - _ ..- . . . _=_ - m. . .

• I

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, Prairie Island Nuolear Generating Isservios Inspeettee Bayert S,og

11111enkomade Drive Northern States Power ca pany

.

second Zaterval By Ise/Itua 414 Nicollet taali

teelaA les 55089 Ceumarelal servio Date Deose er 16, 1s73 Minneapolis, net 55401

1

q Zso 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

4

06/14/94 F-A,B,C

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 I

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

e R.W.S.T.D. SEISMIC RISTRAINT 05/26/94 F-A,B,C

REWORKED

i ISI-82 SIH-10/E 94-0224 VT3 IND

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,

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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

e . :S:-E31 (ISI-93) SIH-18/H 94-0189 VT3 NAD

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

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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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ISI- 9 3 A (15!-93) H-2 (g) 94-0012 PT NAD '

PHR "UT EXCH 11 SUPPORT 05/06/94 C 3. 10

IS!-913 H - .1 94-0009 VT3 NAD

PMR "MT EXCH 12 SUPPORT 05/06/94 F-A,B,C

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Systems item Descriptica Exass Date ASMR Secties C item

, 15!=938 H-2 94-0000 VT3 NAD

MA HEAT EXCH 12 SUPPORT 05/06/94 F-A,8,C

j 151-938 W-1 94-0171 UT45 NAD

l RHR h!AT EXCH 12 HEAD - SHELL 05/26/94 C 1. 20 I

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l 151-938 W-2 94-0110 UT45 NAD l

i M4 dIAT EXCH 12 SHELL - FLANGE 05/26/94 C 1. 10

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IS**l39 W-4 94-0202 PT NAD

MR NtAT EXCH 12 NO,IZLE 06/01/94 C 2. 31

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