IR 05000387/1978018

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IE Insp Repts 50-387/78-18 & 50-388/78-17 on 781004-13. No Noncompliance Noted.Major Areas Inspected:Piping & Piping Support Storage,Maint, & Installation
ML17138A460
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 11/02/1978
From: Durr J, Ebneter S, Fasano A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML17138A459 List:
References
50-387-78-18, 50-388-78-17, NUDOCS 7901040186
Download: ML17138A460 (10)


Text

U.S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I 50-387/78-18 R

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50-387 R

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CPPR-101

N.~R-R Priority Category A

Licensee:

Pennsylvania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 Facility Name:

Susquehanna Units 1 and

Inspection at:

Ber4ick, Pennsylvania Inspection conducted:

October 4-13, 1978 Inspectors:

.

P. Durr, Reactor Inspector rzw da e signed sano, eac or nspec or date signed Approved b

ne er, upport Section 1, ie

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ngineering

&ES Branch date signed date signed Ins ection Summar

Unit 1 Ins ection on October 4-13 1978 Re ort No. 50-387 78-18

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inspection of piping and piping support storage, maintenance, and installation activities.

The inspection involved 50 inspector-hours onsite by two NRC regional based inspectors.

Results:

No items of noncompliance were identified in the three areas inspected.

Unit 2 Ins ection on October 4-13 1978 Re ort No. 50-388 78-17

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inspection of piping storage, maintenance, and installation activities.

The inspection involved three inspector-hours by one NRC inspector.

ults:

No items of noncompliance were identified in the areas inspected.

egeoy040 lpga Region I Form 12 (Rev. April 77)

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DETAILS Persons Contacted Penns lvania Power and Li ht Com an L. Ballard, Site QAE T. Clymer, Senior NQA Analyst

  • J.

D. Green, Resident QAE

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R. Sabol, Manager Nuclear Quality Assurance Bechtel Cor oration M.

K. Boone, Lead Welding Engineer

  • M. A. Drucker, Lead QAE G. Gellinas, Lead Piping Q.C.E.

J.

Khandhar, QAE

  • H. F. Lilligh, Project QAE
  • J. O'ullivan, Assistant Project Engineer B. Ott, Lead Q.C.E. Welding
  • S. Schoenenberger, Field Construction Manager T. Seymour, Q.C.E.

Storage and Maintenance

  • G. Shrader, Project Field Q.C.E.
  • K. G. Stout, Assistant Project Field Q.C.E.

F. Wallick, Q.C.E.

Receiving General Electric Com an

  • T. M.

Le Vasseur, Site Q.C. Representative

"R. Pulsifer, NED Site Engineer

  • denotes those persons present at the exit interview.

Licensee Action on Previous Ins ection Findin s

(Closed)

Unresolved item (387/78-01-06):

Weld contour requirements.

The licensee issued Nonconformance Report Nos.

2300 and 2342 des-cribing the conditions and providing engineering dispositions.

The apparent overground condition on the valve to pipe weld joint HBC-101-1 was ultrasonically measured and verified to meet the minimum wall requirements of the ASME-III Code, paragraph NB-3542.

A visual examination by the NRC inspector disclosed that the outside diameter has been rewelded and now meets the requirement The weld transition of the joint GBB-109-2-FW3 was shown to have equal wall thicknesses at the weld preparation area and, therefore, the weld transition requirement of Specification M-204 is not applicable.

Visual examination of this weld revealed that it has been ground smooth for in-service inspection.

This item is considered resolved.

(Closed)

Noncompliance (387/78-12-05):

Failure to issue the proper welding documentation for a reactor coolant pressure boundary weld.

The inspector verified that a form WR-5 was issued for weld buildup DLA-102-01-FW7 and that a piping isometric drawing review was accom-plished as per Bechtel letter gAL 560, dated September 21, 1978.

This item is considered closed.

(Closed)

Unresolved item (387/388/78-08-01):

Definition,of acceptance criteria for angular offset tolerances and thread engagement.

The

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specification C-72 was reviewed.

This specification has been revised

. to include an allowable offset of 10 to the baseplate (Reference C-72, paragraph 4.1.9).

The thread engagement for the lock nut was addressed on a one to one basis.

The particular support GBB 115-H13 was cor-rected. by staking the anchor threads. 'E. Inspection Report No.

78-08, paragraph 4.d, seventh line should be changed to read GBB-115-H13.

This item is considered closed.

(Closed)

Unresolved item (387/78-12-02):

Combination of pin studs and bolts for pipe clamps.

The inspector examined correspondence between ITT Grinnell and the licensee (letter dated August 11, 1978)

and Supplier Deviation Disposition Request, SDDR, P3-025.

The documen-tation allows the freedom to interchange studs and bolts as long as it is done so that the nominal diameters match and the material is as

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specified on the hanger detail drawing.

This item is considered closed.

3.

Plant Tour The inspectors toured the Unit 1 and 2 reactor buildings and contain-ments observing in progress work activities.

Specific note was taken

'f the in-place storage of equipment, area cleanliness, the handling of components, and quality control activities.

No items of noncompliance were identifie.

Reactor Coolant Pressure Boundar and Safet Related Pi e Weldin Observation of Work The following listed activities were observed and verified to be in accordance with the ASME III and IX codes, the quality Assurance Manual ASME Section III, Specification M-198, and regulatory requirements:

Unit

Observed the intermediate weld passes on the 24" diameter, nuclear class 1 pipe joint DCA-102-01-FW7.

Verified the weld identification, proper weld procedure, the welders qualification, the interpass temperature, the weld materials, appearance of the weld deposit, and evidence of quality control checks.

Unit

Observed the fitup and alignment of the 4" diameter, nuclear class 1, reactor water cleanup pipe joint, DCA-103-1-FW28.

Verified the weld joint identification, joint alignment, and condition of the tack welds.

Although the joint alignment was acceptable, the licensee quality control inspector rejected the joint due to a lack of evidence that the joint internal cleanliness had been verified.

Unit

Observed the completion of the root pass welding of the 12" diameter.

nuclear class 3 pipe joint GBC-101-9-FW-l.

Verified the weld identification, the welders qualification, the proper welding procedure, and the weld deposit appearance.

Unit 2 Observed. the fitup and alignment of the 12" diameter, nuclear class 3 pipe joint HRC-201-1-FW-.13.

Verified the joint identification and observed the quality control inspector perform the fitup hold point inspection.

The joint was rejected for the backing ring '

clearance and water leaking into the weld area.

Units 1 and

The control of welding filler metal was observed.

The inspector examined the weld rod issue stations for handling, storage, and issue practices.

No items of noncompliance were observe Reactor Coolant Pressure Boundar Pi in

- Observation of Work Unit

The inspector observed the ultrasonic thickness measurement and the liquid penetrant testing of the weld buildup of the pi'pe weld joint preparation DLA-104-1-FW-1.

He verified that the liquid penetrant test was performed in accordance with the Peabody Test Procedure IPPT-300-39-03, Revision D, Amendment 2 and that the test technicians were qualified.

No items of noncompliance were identified.

Reactor Coolant Pressure Boundar Pi in

- Review of Stora e and Maintenance Units 1 and

'he inspector examined the reactor coolant pressure boundary pipe storage area and verified that the stainless steel piping is being stored in accordance with the Field Procedure for Storage, Protection, Maintenance, and Layup, FP-G-ll, Revision 15.

He reviewed the "Equip-ment Maintenance Requirements and Records" for austenitic stainless steel piping.

There does not appear to be any records f'r the in-plant storage inspection of M-1 (GE supplied) stainless steel pipe.

However, interviews with the storage and maintenance inspectors dis-close that all in-plant stainless steel pipe was inspected regardless of the P-1 or M-1 designation.

The licensee is currently evaluating the cause of previously identified items of noncompliance in the storage and maintenance program (reference:

Bechtel gA Program - Management Corrective Action Report No. 1-26).

This item is unresolved pending the com-pletion of the foregoing CAR. (387/78-17-01 and 388/78-18-01):

The licensee stated that the CAR would be completed on or about November 15, 1978.

Safet Related Pi e Su ort and Restraint S stems - Work Activities Unit

The inspector examined installed mechanical pipe arrestors (snubber)

and component pipe supports.

The criteria for the inspection was based on Specification M-209, Pipe Hangers, Supports and Restraints; Specification M-213, Installation, Inspection, and Documentation of Pipe Supports, Hangers and Restraints; Specification C-72, Furnishing and Installation of Expansion Type Anchors, Weld Procedure Pl-A-Lh; and ASME Section I a.

Mechanical Pi e Arrestors The inspector. examined ten pipe arrestors of at least three different load classifications and at various degrees of access-ability.

The inspector, by visual examination, examined the pipe arrestors for deterioration, corrosion, deformed or loose com-ponents, secure fasteners, and protection from foreign material.

The inspector also sample checked the installations against their respective current drawings.

The following mechanical pipe arrestors were examined:

Identification No.

Revision Tvye Load-Pounds DCA-106-H5 DCA-106-H7 DCA-103-H5 GBC-101-H126 GBC-101-H128 GBC-101-H141 GBC-101-H112 GBC-101-H188

,GBC-101-H156 GBC-101-H105 2/F3 PSA>~

500 2/F2 PSN; 330 4/F5 PSA3 3,000 1/Fl PSA35 30,000 1/Fl PSA35 30,000 0/Fl PSA35 30,000

PSA35 30,000

PSA35 30,000 1/F2 PSA35 30,000

PSA35 30,000 The first two mechanical pipe arrestors have been final inspected and accepted by gC.

The remaining eight systems are in the process of being installed, the completed installation and final inspection remains to be completed by the licensee.

The cold settings were checked for seven of the above units and found to be within tolerance as specified in Specification M-213 paragraph 4.9.f.

Mechanical pipe arrestors GBC-101-H128, H156 were checked for plate bearing surface'o the containment wall.

Also, GBC-101-128 was found to lack clearance between the pipe clamp to arrestor rear cylinder.

The licensee has taken action to rework (In-Process Rework Notice 2690) the bearing plates and the pipe clamp.

The inspector had no further questions at this time.

Discussion with the licensee and review of SDDR P-3-025 indicate that an inspection item with respect to studs or bolts in pure shear should be checked to assure that threads are not located

in the bearing part of the shank.

Specific acceptance criteria and inspection sequence remains to be specified.

This is an unresolved item pending clarification of criteria and inspection sequence.

(387/78-18-02)

b.

Com onent Pi e Su orts The inspector examined six component pipe supports.

The supports are in process of being installed.

Final inspection by the licensee remains to be completed.

The component pipe supports were examined to their respective drawings for location, acceptable welds, lubricants, material certification and bolting.

The six examined are identified by the following: HBB-111-H19, Revision 2/F3; HRC-104-H4, Revision 2/F2; HRC-103-Hl, Revision 0/F4; HRC-104-H1, Revision 0/F3; HRC-123-H3, Revision 2/F2 and HRC-124-H2, Revision 0.

The inspector reviewed documentation for support HBB-111-H19 for traceable material and welder qualification.

The material was traced to Heat No. 94651-21, Phoenix Steel Corporation test report, 4/24/73.

Welder performance qualification was also checked.

A similar trace was made for support HRC-104-H4.

The Heat No. was 154108 and traced to ARMCO test report, 12/18/75.

The welder performance record was checked.

Clearance checks for HRC-123-H3 and HRC-124-H2 varied from the value of 1/16" specified on the respective drawings.

Measurement indicates a value of 0.068 and 0.040 inches.

Documentation was not available specifying a tolerance for these clearances.

This is an unresolved item pending documentation clarifying acceptable tolerances.

(387/78-18-03 )

8.

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

Unresolved items disclosed during the in-spection are discussed in parag'raphs 6 and 7.

9.

Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on October 13, 1978.

They sumnarized the purpose, scope, and findings of the inspection.