IR 05000220/1979008

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IE Insp Rept 50-220/79-08 on 790308-09,20-23 & 27-30.No Noncompliance Noted.Major Areas Inspected:Torus Mod Activities,Emergency Condenser Nozzle safe-end Replacement, Actions Relative to LER 78-07 & Inservice Insps
ML17053A851
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/16/1979
From: Jernigan E, Mcbrearty R, Lester Tripp
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17053A850 List:
References
50-220-79-08, 50-220-79-8, NUDOCS 7907270381
Download: ML17053A851 (24)


Text

U.S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Repor t No.

50-220/79-08 Docket No.

License No.

DPR-63 Priority Licensee:

Niagara Mohawk Power Cor oration 300 Erie Boulevard >fest Category Syracuse, New York 13202 Facility Name:

Nine Mile P Inspection at:

Scriba, Hew York I'nspection conducted:

3/8-9/79, 3/20-23/79, 3/27-30/79 Inspectors:

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R. A. McBrearty, Reac or Inspector

.gQc E.

P. Jernigan, Reac or Inspector seer)

date signed Xtb Z date signed Approved by: -'" >>9 P L. E. Tripp, Chief, Engineering Support Section No. 1, RCSES Branch date signed

~/icosi'ate signed Ins ection Summar

Ins ection on March 8-9 1979 March 20-23 1979 and March 27-30 1979 Re ort No. 50-220 79-08

~AI d:

R i, d i p ti f

h diff'i actsvstses, emergency condenser nozzle safe end replacement, actions relative to LER 78-07, core spray sparger inspection and the licensee's inservice inspection activities. This included review of NDE procedures, observation of NDE in progress and review of ISI data.

The,inspection involved 61 inspector-hours onsite by two regional based NRC inspectors.

Results:

No items of noncompliance were identified.

Region I Form 12 (Rev. April 77)

DETAILS 1.

Persons Contacted Nia ara Mohawk Power Cor oration C.

8'F AAA'G M.

PAR

'AT W. Crittenden - Nuclear Staff Engineer Gerber - Rad Waste Operations Coordinator A. Hawksley - ISI Coordinator R.

Leskiw -

NDE Level III-Meehan - Technical Assistant to Superintendent 0. Norrix - g.

C. Engineer Perkins - Plant Superintendent Chica o Brid e and Iron Com an G. Czapnik - Project Welding & gA Supervisor General Electric Com an R. Wiese - Field Representative Nucl ear Ener Servi ces Inc.

E. Anderson - PT Level III F. Carr -

NDE Level III Factor Mutual En ineerin 2.

F. Stelter - Authorized'uclear Inspector

"denotes those present at the meeting on March 23, 1979 and at the exit interview on March 30, 1979

""denotes. those present at the meeting on March 23, 1979

'I

"""denotes those present at the exit interview on March 30, 1979

= Li uid Waste Sur e Tank Corrosion Licensee Event Report No. 78-07 was submitted to NRC: I on March 1, 1978.

The report describes pinhole leaks in the 50,000 gallon aluminum liquid waste surge tank at Nine Mile Point, Unit 1.

The report states that an inspection during steady state operation

found several pinhole leaks.

The report further states that there weve no measurable losses of liquid but leaks could be identified by dried deposit tracks on the side of the tank.

The condition was attributed to welding and grinding during assembly which reduced the wall thickness in spots to half of the 0.1875 inch nominal thickness and apparently resulted in pinhole leaks.

The inspector reviewed the following records associated with repair of the liquid waste surge tank:

Work Request (WR} No. 7350 dated 2/27/78 Quality Control Inspection Report (QCIR) No.78-039 dated 3/1/78 Memo to File dated 6/1/78 downgrading System 85 (Radwaste System} to non safety related per DP 020 - Niagara Mohawk Engineering Design Procedure for Classification of Materials

&

Components-The inspector noted that WR 7350 was closed out 3/29/79 after repairs to the liquid waste surge tank-were completed.

The repair work was completed in Janauavy, 1979 by filling in the pinholes with Yelodour compound.

The licensee informed the inspector that a tank liner ov complete replacement of the tank are being considered as a permanent solution, but until a final decision is reached, use of the tank is limited and controlled.

The inspector stated that the corrective actions taken to date were acceptable and the inspector had no further questions at this time.

3.

Emer enc Condenser Safe End Re air The licensee reported to the NRC that during a scheduled ultrasonic examination of the Safe End to elbow weld in the emergency condenser system at nozzle NRB, cracks were detected in the weld heat affected zone.

The examination was done as part of the augmented inspection program fov the examination of furnance sensitized stainless steel.

The inspector was informed by the licensee that the sensitized Safe End and 90o elbow past nozzle N5B will be removed and replaced with non sensitized materia General Electric Company I&SE personnel will do the work and provide gA/gC coverage.

The work was not started at the time of this inspection, but is experted to be completed during the ongoing refueling outage.

The the inspector advised the licensee that activities associated with repair would be examined during a subsequent NRC inspection.

4.

Inservi ce Ins ection ISI Activities a ~

ISI Pro ram The inspector ascertained that the scope of the specified inspection during the ongoing refueling outage for each component complies with the Nine Mile Point Unit 1 Technical Specification, and the procedures and acceptance criteria meet the requirements ou'tlined in Section Xl, ASME B&PV Code 1974 Edition, including the Summer 1974 Addenda.

'

b.

The inspector noted that the Nine Mile Point Unit

was designed and constructed prior to the adoption of the ASME 'B&PV,Section XI. Code.

As a result, certain examinations stipulated by that code cannot be performed completely since the plant design does not permit access to portions of certain examination areas.

In addition, components in high radiation areas or which are covered by non-removable insulation have been considered inaccessible as indicated in the Nine Mile Point Unit 1 Technical Specification, Paragraph 4.2.6.

Personnel performing nondestructive examinations are required to be qualified in accordance with ASNT-TC-lA as stipulated in Subarticle IWA-2300 of Section XI.

Im lementin Nondestructive Examination NDE Procedures The inspector selected the following NDE procedures for review, to ascertain technical adequacy:

(1}

80A0835, Revision 0 - Ultrasonic examination procedure for austenitic piping and safe-end welds with augmented ISI requirements (2}

80A2310, Revision 0 - Liquid penetrant examination procedure

(3)

80A2311, Revision 2 - Visual examination procedure (4)

80A2319, Revision 1 - Ultrasonic 'examination procedure for piping butt welds and longitudinal welds (5)

80A2321, Revision 0 - Ultrasonic examination procedures for nozzle to safe-end welds The inspector's review included, but was not limited to, the parameters listed below for the ultrasonic and liquid penetrant examination techniques.

Ultrasonic Examination

,r'a)

The type of apparatus including frequency'range is "specified (b)

The extent of coverage including beam angles and scanning surface is specified (c)

Calibration requirements including frequency and size of transducer and calibration reflectors are, specified

'nd consistent with the applicable ASME Code (d)

The reference level for monitoring discontinuities is defined and the scanning level is specified and consistent with the applicable ASME Code (e)

Acceptance limits are specified or referenced and are consistent with the applicable ASME Code Li uid Penetrant Examination (a)

The examination method is consistent with ASME Code requirements (b)

Penetrant materials used for nickel base alloys and austenitic stainless steel are required to be analyzed for compliance with allowable residual sulfur and halogen content (c)

Examination surface requirements, including temperature limitations, are specified and consistent with ASME Code requirements

(d)

Methods for removal of solvent removable penetrant are specified and consistent with the applicable ASME Code (e)

A technique for evaluation of indications is specified, acceptance standards are referenced, and are consistent with the applicable ASME Code No items of noncompliance were identified.

c.

NDE Personnel uglification The inspector examined records associated with the qualification and certification of NDE personnel performing examinations at Nine Mile Point Unit 1 during the ongoing refuel.ing outage.

The records identified the examination method and level of qualification to which each individual was certified.

In addition to the above, visual acuity records were reviewed for each individual and found to be current and complete.

The inspector found that the applicable requirements of the governing document, SNT-TC-1A, were met.

No items of noncompliance were identified.

d.

Observation of NDE in Pro ress (1)

The inspector observed the ultrasonic examination of the following welds in the turbine by-pass system:

Weld 8P-03-7-W, 16" diameter pipe to ell weld Weld //P-03-7F-W, 16" diameter ell to pipe weld The examinations were done in accordance with procedure 80 A, 2319 by individuals certified to NDE Level I and Level II.

Equipment'sed for the examination included a Sonic Mark-I flaw detector, serial number 783106, and Aerotech Gamma series, 1/2" X 1", 2.25 MHZ transducer, serial number B-12496 fitted with a wedge to produce a 45 entry angle in steel.

The examination system was calibrated utilizing the reference reflectors in calibration block PIR-1.5-e

(2)

The inspector observed a portion of the remote visual examination of the core spray spargers.

The examination was done from the refueling floor using a remote controlled underwater television camera.

The inspector noted that the viewing equipment exhibited a sharply defined, well lighted view of the examination area.

An NDE Level II individual performed the examination.

All observed surface conditions were reported in accordance with applicable code and procedure requirements.

(3)

The inspector witnessed the liquid penetrant examination of main steam pipe support weld number P-03-H15-S.

The examination was done in accordance with liquid penetrant procedure

A 2310 using solvent removable, visible dye penetrant by an individual qualified to NDE Level II in the liquid penetrant method.

The inspector found that the above listed examinations were done in accordance with the applicable NDE procedure by personnel properly qualified to the required level of expertise.

No items of noncompliance were identified.

Data Review The inspector reviewed NDE data associated with the following welds:

Pipe hanger weld ¹P-02-H15-S Emergency (isolation) condenser welds P-39-SW 31-w, P-39-10A-W and P-39-10A-MU Core spray piping welds P-40-9-M, P-40-10-M, P-40-11-M, P-40-49-BM and P-40-49A-M Weld P-02-H15-S was examined using the liquid penetrant examination method and the remaining welds were ultrasonically examined.

The 'inspector's review included examination data sheets, equipment calibration records and test result evaluation documentatio 'P

Two penetrant examinations of hanger weld P-02-H15-S were conducted by the licensee's ISI contractor.

Data sheet 82310-25 and 2310-27 document the two examin-ations and are identified by the level III examiner as preliminary data.

Data sheet 2310-25, which represents the initial examination, witnessed by the inspector, indicates that further evaluation is necessary.

The inspector observed that numerous indications were detected and a portion of the surface was masked by heavy dye pigmentation.

The second examination, as documented by data sheet 2310-27, again revealed penetrant indications.

The recommendation for surface conditioning prior to penetrant examination is included in the evaluation.

I Penetrant procedure 80 A2310 requires that components or parts must liave a surface finish which will permit proper interpretation of developed indications.

The procedure states that any indications believed to be nonrelevant shall be regarded as an unacceptable surface defect and shall be reexamined to verify whether actual defects are present.

It further states that surface.

conditioning may precede the reexamination.

The ASMf BSPV Code,Section V, Article 6 states that surface preparation may be necessary where surface irregularities could otherwise mask indications of unacceptable discontinuities.

At the exit meeting on March 30, 1979, the inspector stated that the adequacy of the examination surface is considered questionable as evidenced by the penetrant indications which were revealed and assumed to be due to examination surface condition.

This item is considered unresolved pending licensee action to provide the surface condition necessary to perform the surface examination required by the ASME Code,Section XI and the facility Technical Specification.

(220-79-08-01)

Data sheet 40835-72 documents that no back reflection was obtained throughout the complete longitudinal beam ultrasonic examination of emergency condenser weld PP-39-SN31-W.

This item is considered unresolved pending verification that ultrasonic penetration through the weld"material was achieved.

(220/79-08-02)

5.

Torus Modificati ons j

As a result of the BWR Mark I Containment Program which was initiated in response to Nuclear Regulatory Commission concerns related to relief valve blowdown and loss of coolant accident events~modifications to the Nine Mile Point Unit 1 torus are being made.

The work is planned to be completed during the ongoing refueling outage and will include the following:

Installation of Y-guenchers and supports in the safety relief valve (SRV) discharge lines Installation of vent header deflectors and supports Installation of downcomer tie straps In addition to the above, the catwalk inside the torus was removed and a monorail/removable personnel carrier system is being installed.

The monorail installation necessitated rerouting a segment of the torus spray piping system.

The licensee's contractor for the modifications is the Chicago Bridge and Iron Company (CB8I) who has the gA/gC responsibility for the work.

The inspector made a walk through inspection of the torus and observed work in progress including monorail installation and fit-up of the Y-quenchers on SRV-16-3.

The inspector observed that the root pass of weld SRV-12-3 was completed and awaiting radiographic examination and that the weld joint preparati'on on SRV-12 was completed and awaiting fit-up and welding of the 14" diameter Y"

quencher piping.

The joint preparation was made by a weld metal build-up and machining operation.

No items of noncompliance were identified.

a 0 Nondestructive Examination NDE Procedures The inspector selected the following CB8I NDE procedures for review:

MT 3X, Revision 1 - procedure for magnetic particle examination by the continuous, yoke method using dry, visible particles

MT 4X, Revision 1 - procedure for magnetic particle examination by the continuous, yoke/prod method using dry, visible particles PT 10X, Revision 1 - liquid penetrant examination procedure for class MC v'essels The review was done in order to ascertain licensee approval of the procedures, procedural compliance with the applicable ASME BSPV Code and, in addition, for technical adequacy.

P The inspector's review included, but was not limited to, the parameters listed below for the magnetic particle examination technique and the parameters listed in paragraph 4b for the liquid penetrant examination method.

Ma netic Particle Examination (a}

The examination is to be done by the continuous method (b}

The dry particle color provides good contrast with back-ground (c}

The examination is conducted with sufficient overlap to achieve 1005 coverage (d)

Yoke lifting power is specified and consistent with applicable ASME Code requirements (e}

The magnetizing current for the prod method is specified and is consistent with the applicable ASME Code requirements No items of noncompliance were identified.

b.

NDE Personnel Qualification The inspector examined records associated with the qualification of CB8I personnel responsible for radiographic examination of welds in the torus.

The inspector found that the records were current and complete.

The qualifications were in compliance with CBSI requirements and the applicable requirements of SNT-TC-lA.

No items of noncompliance were identifie Weldin Activities The inspector reviewed welding procedure specifications, welding procedure qualification records and welder qualification records associated with the torus modification activities.

The review was done to ascertain conformance with the ASME B8PV Code,Section IX and licensee commitments.

The following were included in the inspector's review:

Welding Procedure Specification (WPS)

E 70S-2/E7018, Revision 0 for carbon steel pipe'elds using the GTAW and SMAW process WPS-E 7018 kl Revision 0 for carbon steel new components N

WPS-E 7018 82, Revision 0 for stainless steel pipe welds using the GTAW and SMAW process Procedure qualification records for the above mentioned procedures Welder qualification records for three welders including one welding supervisor The inspector found that the welding procedures were qualified in accordance with Section IX of the ASME code and that Vee-notch impact test data were included in procedure qualification records.

Welder qualification records included the material thickness range and procedures to which each individual was qualified.

The inspector interviewed licensee contractor personnel and inspected the welding material storage and disbursement area and found that the applicable requirements of procedure ECSC, revision 0 were met.

The procedure provides requirements for the purchase, storage, conditioning and handling of welding materials.

No items of noncompliance were identifie ~

6.

Unresolved Items Unresolved items are items about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations.

Two unresolved items disclosed during this inspection are discussed in paragraph 4e.

7.

Exit Interview The inspector met with the licensee representatives (denoted in paragraph 1) on March 23, 1979 and at the conclusion of the inspection on March 30, 1979.

The inspector summarized the purpose and scope of the inspection and the finding I/

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