IR 05000155/1979001

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IE Insp Rept 50-155/79-01 on 790214-16 & 0403.No Noncompliance Noted.Major Areas inspected:safety-related Hangers & Mechanical Snubbers,Observation of Installation Conditions & Review of Previous License Surveillance
ML19269D960
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 04/16/1979
From: Danielson D, Yin I
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML19269D958 List:
References
50-155-79-01, 50-155-79-1, NUDOCS 7906210334
Download: ML19269D960 (4)


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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-155/19-01 Docket No. 50-155 License No. DPR-6 Licensee:

Consumers Power Company 212 West Michigan Avenue Jackson, MI 59201 Facility Name: Big Rock Point Nuclear Plant Inspection At:

Big Rock Site, Charlevoix, Michigan Inspection Conducted: February 14-16 and April 3, 1979 Y N [f

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Approved By:

. H. Danielson, Chief Engineering Support Section 2 Inspection Summary Inspection on February 14-16 and April 3, 1979 (Repor* No. 50-155/79-01)

Ar_eas Inspected:

Inspection of safety related hangers and mechanical r

snubbers including procedure review, observation of installation conditions, testing of two snubbers, and review of previous licen2ee surveillance records.

Results: No items of noncompliance or deviations were identified.

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DETAILS Persons Contacted Censumers Power Company (CP)

  • C J. Hartman, Plant Superintendent D. E. Demoor, General Technical Engineer J. S. Rang, Operation and Maintenance Superintendent
  • M.

J. Bielinski, Plant ISI Coordinator

  • J. Jandovitz, Plant ISI Coordinator
  • R.

E. Schrader, Technical Superintendent

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  • G. D. Gilbody, Quality Assurance Engineer
  • Denotes those attending the management exit meeting.

Functional or Program Areas Inspected 1.

Review of Procedures and Specifications The plant hanger and restraint inspection program is based on the 1971 ASME Code,Section XI, " Rules for Inservice Inspaction of Nuclear Reactor Coolant Systems." The inspector reviewed the following applicable procedures and specifications:

a.

Southwest Research Institute (SWRI) Procedure 17-4455, "Long-Tern Inservice Examination Plant for Class 1 Components and High Energy Piping," dated September, 1976.

b.

SWRI-NDT-900-4, " Nuclear Projects Operating Procedure,"

Rev. 18, dated August, 1978.

This procedure replaced Procedure 17-4456 above.

In Paragraph 7.0, " Examination Areas," the support settings of constant and variable spring type hangers, snubbers and shock absorbers were required to be recorded; c.

CP Procedure NDT-VT-01, " Direct Visual Examination," Rev. O, dated April 29, 1977.

d.

CP Program Manual for Nuclear Power Plants, Volume III -

Procedure for Operations, issued on July 24, 1978. Specific procedures reviewed included Procedure 5-51, " Development of Documents Controlling Quality-Related Activities During Operations," Rev. O, dated May 15, 1975.

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c.

SUNTAC Nuclear Corporation 3449-1805-1001, " Specification for Mechanical Shock Arrestors," dated July 1, 1975.

No items of noncomplianan or deviations had been identified as a resul+. of the review.

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2.

Observation and Test of Mechanical Snubbers a.

During 1976, the Reactor Depressurization System (RDS) was re-analyzed in accordance with ASME Code,Section III, require-ments, and as a result, 23 Pacific Scientific Company (PSC)

mechanical sunbbers were installed into the system. The quantity and size of these snubbers included three (3)

PSA-1/4's, six (6) PSA-1/2's, and fourteen (14) PSA-3's.

b.

The inspector observed four PSA-3's inside the steam drum room area on the 12" RDS line, and others on 10" and 2" RDS lines outside the room, all were within the reactor containment.

In addition, the inspector tested one (1)

PSA-3 and one (1) PSA-1/4 snubber and observed that the surface condition and the functionability of the tested snubbers appeared to be good, c.

However, during observation, opproximately ten (10) of the snubbers were without spherical ball bushings at the connections between the structure and the snubber unit.

The gaps between the snubber extension connecting hole and the pin of the pipe clamp (or lug) were observed to be 'l/8" to 3/16". The described condition was not in accordance with PSC installation requirements where spherical ball bushings were shown on both ends of the connections. Further, this condition was not in accordance with SUNTAC specification 34490-1805-1001, dated July 1. 1975, where Paragraph 5.2.2 stated that, "The shock arrestors shall meet the following requirement when exposed to cyclic loading of 3 to 33 Hertz:

The total excursion during cyclic loading shall include lost motion and structural deflection and shall not exceed + 0.060 inch at any load up to rated load."

Subsequent to the inspection, the licensee elephoned RIII and stated that corrections will be made prior to plant startup. This is an unresolved item.

(155/79-01-01)

d.

While observing installed PSC snubbers the inspector noted safety wires or tack welds were not installed on bolts connecting the snubber enits to the extension spools. Further, no records existed verifying how much torque had been applied to the connecting bolts. The specific bolt c.orque requirement and safety wiring of bolts (or tack welding) cre part of PSC " Field Assembly Instructions, Transition Tube Kits" requirements shown on PSC Drawing No. 18015b3-01, dated May 27, 1976.

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Subsequent to the inspection, the licensee telephoned RIII and stated that corrections will be made prior to plant startup. This is an unresolved item.

(155/79-01-02)

No items of noncompliance or deviations were identified.

3.

Review of Hanger and Snubber Inspection Records The subject inspection records for 1978 and earlier years were reviewed by the inspector.

The inspector commented that the licensee hanger surveillance for 1978 based on the revised SWRI-NDT-900-4 procedure had shown significant improvements in observation requirements and documentation details.

No items of noncompliance or deviations were identified.

Unresolved Items Unresolved items are matters 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 the inspection are discussed in Paragraphs 2.c and 2.d.

Exit Interview The inspector met with licensee representatives (denoted in the Persons Contacted paragraph) at the conclusion of the inspection of April 3, 1979.

The inspector summarized the purpose and findings of the inspection.

The licensee acknowledged the findings reported herein.

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