IR 05000311/1978043

IE Insp Rept 50-311/78-43 on 781108-09. No Noncompliance Noted.Major Areas Inspected:Preoperational Test of Pipe Supports & Restraints & Thermal Expansion Program

ML18078A566
Person / Time
Site:	Salem
Issue date:	11/22/1978
From:	Caphton D, Foley T, Higgins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18078A565	List: IR 05000311/1978043 ML18078A564
References
50-311-78-43, NUDOCS 7901020075
Download: ML18078A566 (5)

Text

Report N U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I

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Docket No. ---'5.._.0._-..... 3....... 11..___

License N CPPR-53

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Priority ------

Category C

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Licensee:

Public Service Electric and Gas Company 80 Park Place Newark, New Jersey 07101 Facility Name:

Salem Nuclear Generating Station, Unit 2 Hancocks Bridge, New Jersey Inspection at:

Inspection Inspectors:

Approved by:

Inspection Summary:

November 8-9, 1978 Nuclear Support Branch Inspection on November 8-9, 1978 (Report No. 50-311/78-43)

/( /.J, /) v date signed

/{,/J.,/11 date signed date signed 11/22/1~

1 date signed Areas Inspected:

Routine, unannounced inspection by regional based inspectors of preoperational testing of pipe supports and restraints and thermal expansion progra The inspection involved 22 inspector-hours on site by two NRC regional based inspector Results:

No items of noncompliance were identifie. Region I Form 12 (Rev. April 77)

• DETAILS 1. Persons Contacted L. Bonardel, Senior Mechanical Designer R. Brandt, Senior Engineer

• S. Chawaga, Project QC Engineer

• R. Griffith, Senior Staff Engineer - QA C. Johnson, Startup Engineer W. Kittle, QA Engineer

• R. Kirk, Senior Engineer

• R. Mccoppin, Lead Electrical Startup Engineer, UE&C

• E. Meyer, Project QA Engineer

• R. Phelps, Superintendent, Field QC, UE&C

• P. String, QA/QC Coordinator UE&C - United Engineers and Constructors The inspector also talked with and interviewed several members of the QA and QC staffs, construction personnel and test/startup per-sonne * den.ates those present at the exit interview Thermal Expansion The inspector reviewed the hot functional test procedure 11Reactor Coolant System Thermal Expansion, 11 SUP 50.1, Revision O, dated September 19, 1978 for proper format, conformance with regulatory requirements and technical adequac The procedure details the steps used to verify that the Reactor Coolant System and its associated auxiliary piping properly expands and contracts on heatup and cool-dow The inspector also reviewed various data sheets, calculated expansion readings, data recorded for the cold and 150°F plateaus and problem summary sheets. The inspector observed that the admin-istrative tracking of identified problems appeared to lack organi-zatio Prior to the completion of the inspection the licensee re-vised his method of tracking these problems to improve the tracking of discrepancies and corrective action taken. *

The inspector accompanied licensee personnel during data taking for the 450°F hot functional test plateau on the pressurizer and verified that readings taken were accurate and personnel were properly qualified for their tasks. The inspector had no further questions in this area at this tim,

Preservi ce Inspection * General The inspector reviewed the following documents relating to the licensee's preservice inspection progra *

11Preservice Examination of Supports, 11 SUP 50.19, Revision O, dated November 4, 1978 Public Ser~ice General Procedure 77-6144, Preservice Examina-tion Administrative Plan; Unit 2, Salem NGS Public Service Detail Specification No. 78-6212 - Visual Exam-ina~ion of Supports on Nuclear Class 1, 2 and 3 Components, Salem NGS These documents describe the licensee's program for performing the preservice inspection requirements for pipe supports and hangers of Section XI to the ASME Boiler and Pressure Vessel Code (Section XI).

With the exception of the below item, the inspector ~ad. no further questions at this tim /.

Insulation Removal The licensee's general preservice and inservice inspection plans provide for insulation removal when required; however, for the visual inspection of bolted supports (covered by Categories B-K-2 and C-E-2 of ASME Section XI), insulation removal is not required by licensee procedure Step 6.0(c) of Detail Specification 78-*

6212 exempts the portion of the support covered by insulatio This exemption is contrary to the inspection requirements of Section XI as given in Category B-K-2 and C-E-2 and in paragraph IWA.-150 The licensee's representative stated that a new Subsection IWF of Section XI on Component Supports, which is currently in draft form, was used to model their procedure since it discusses in greater detail the inspection of supports. This permits the insulation to remain in place for the Categories in questio This item 1s unresolved pending further NRC review (311/78-43-01).

4 Hydraulic Snubbers General The inspector examined Steam Generator and Main Steam Isolation Valve Hydraulic Snubbers, fluid reservoirs and associated piping for the following:

type of hydraulic fluid being used; correct fluid level in hydraulic fluid reservoirs; hydraulic fluid leakage; deteri-oration, corrosion and defo.rmation not evident; and, type of seals in use The inspector made measurements of the installed components and compared these to the PSE&G field installation drawings to verify correct installation of the snubbers and reservoir Except as noted belo~, the inspector had no further questions in this are Thread Engagement During examination of the Steam Generators (S/G) snubb~rs, the amou.nt of thread exposure to the piston shaft connecting to the eye bolt on the S/G varied between approximately one inch and four tnches indicating a large variance in thread engagement The design drawings ~id not provide the required amounts of engagement or exposur The licensee stated that he would research this to determine the proper amoun Coating on Snubber Pistons Inspection of S/G snubber piston shafts indicated a hard crusty substance on a few shafts, which could potentially damage the hydraulic seals. This substance was removed by the license *

5 Hydraulic Fluid Leakage Inspection of the reservoirs, p1p1ng and fittings revealed fluid leakage at two locations, several loose fittings and a bolt on the-valve assembly of one snubber which was not

• installed in accordance with the d~sign ~rawin The items were collectively designated as Unresolved Item ( 311 /78-43-02).

5.. *unresolved Items Items about which more information is required to determine ac-ceptability are considered unresolve Paragraphs 3.b and 4 of this report contain unresolved item.

Exit Interview At the inspection's end the inspectors held a meeting (see Detail l for attendees) to djscuss the inspection scope*and finding The unresolved items were identified.