IR 05000315/1979008

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IE Insp Rept 50-315/79-08 on 790501-02.No Noncompliance Noted.Major Areas Inspected:Licensee Action on Previously Identified item,safety-related Snubber Insp Program Provisions,Records & Installation Conditions
ML17317B310
Person / Time
Site: Cook American Electric Power icon.png
Issue date: 05/16/1979
From: Danielson D, Yin I
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML17317B309 List:
References
50-315-79-08, 50-315-79-8, NUDOCS 7907130354
Download: ML17317B310 (8)


Text

U.S.

NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT

REGION III

Report No. 50-315/79-08 Docket No. 50-315 License No. DPR-58 Licensee:

American Electric Power Service Corporation Indiana and Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:

Donald C.

Cook Nuclear Plant, Unit

Inspection At:

Donald C.

Cook Site, Bridgman, Michigan Inspection Conducted:

May 1-2, 1979 dvaN Inspector:

. T. Yin Approved By:

D. H. Danielson, Chief Engineering Support Section

Ins ection Summar Ins ection on Ma 1-2 1979 (Re ort No. 50-315/79-08)

Areas Ins ected:

Licensee action on a previously identified item.

Safety related snubber inspection program provisions, records re-view, and observation of installation conditions.

The inspection involved a total of 10 inspector-hours onsite by one NRC inspector.

Results:

No items of noncompliance or deviations were identified.

>9071SO+5f

DETAILS Persons Contacted Indiana and Michi an Power Com an (IMPCo)

  • D. V. Shaller, Plant Manager

"R. H. Dudding, Maintenance Superintendent

  • W. D. Connell, Maintenance Engineer USNRC - RIII
  • R. E. Masse, Resident Inspector
  • Denotes some of those attending the exit interview.

Licensee Action on Previousl Identified Items (Closed) Unresolved Item (316/78-08-02):

Procedural requirement on maintenance of ITT-G snubber fluid levels.

The inspector reviewed IMPCo Procedure No.

MHP 4030.STP.004, Revision 8, dated January 16, 1979, and considers the provisions adequate.

'unctional or Pro ram Areas Ins ected 1.

Reviews of Technical S ecification (TS) and Ins ection Procedures a

~

The safety related hydraulic snubber limiting condition for operation, surveillance requirements, and the basis of requirements are listed in TS Section 3/4.7.8.

The list of the total 95 snubbers (16 large steam generator snubbers inclusive) are contained in TS Table 3.7-4.

b.

IMPCo Procedure No.

MHP 4030.STP.003,

"Maintenance Sur-veillance Test Procedure for Inspection of Steam Generator Hydraulic Shock and Sway Suppressors (Snubbers)".,

Revision 0, dated April 9, 1975.

C.

IMPCo Procedure No.

MHP 4030.STP.004,

"Inspection or Test of ITT Grinnell Hydraulic Shock and Sway Suppressor (Snubbers)",

Revision 8, dated January 16, 1979.

d.

IMPCo Procedure No.

MHP 5021.001.028,

"Maintenance Procedure for Repair and Test of ITT Grinnell Hydraulic

Shock and Sway Suppressors (Snubbers).",

Revision 2, dated July ll, 1978.

The inspector stated that he had no questions regarding items b

and d as a result of the review.

In regard to items a and c, TS Paragraph 4.7.8.1.3 states, in part, that "Snubbers identified as either "Especially Difficult to Remove" or in "High Radiation Zones" may be exempted from functional testing, provided these snubbers were demonstrated OPERABLE during previous functional tests."

TS Table 3.7-4,

"Safety Related Hydraulic Snubbers" and the snubber tables in the item c procedure list all 63 ITT-G pipe snubbers inside the containment to be in the "High Radiation Zone" and most of them to be "Especially Difficultto Remove",

as a result all these snubbers are exempted from functional testing.

The inspector stated that he did not agree that the containment area remained a high radiation area during a cold shutdown plant refueling outage and questioned the definition of snubbers that are especially difficult to remove.

Further discussion of the subject matter with the AEPCo management is planned.

This is an unresolved item.

(315/79-08-01).

No items of noncompliance or deviations were identified 2.

Review of Previous Ins ection and Test Records for Safet Related Snubbers a

~

Inspection records dated March 1, 1979, and February 13, 1978, for the 16 large hydraulic snubbers installed on the four steam generators'.

Records show that 100'f, test, repair, and adjustment on ITT-Grinnell (ITT-G) TS Snubbers had been performed in March 1978, at the site.

c ~

The ITT-G TS snubber reservoir mounting positions, and the actual snubber cold position settings were inspected, then evaluated by AEPCo engineers.

The inspection data was shown in File No. GF-STP-.004, dated May 24, 1978.

d.

Inspection records of all inaccessible ITT-G TS snubbers, dated December 7,

1978.

e.

Inspection records of accessible ITT-G TS snubbers, dated March 1, 1979.

"3-

f.

Functional test records of accessible ITT-G TS snubbers, dated March 1, 1979.

No items of noncompliance or deviations were identified as a

result of the review.

3.

Observations of Installations Safety related snubbers installed on Component Cooling Water and Containment Spray Systems were observed by the inspector.

The following findings were disclosed:

a Snubber 2 GCCW-S844:

The position of the reservoir vent hole was not at the highest point of the unit.

The licensee stated that corrective action will be initiated.

This is an unresolved item (315/79"08-02).

b.

Snubber 1 GCCW-278:

The vent plug with air filter unit was not installed.

A solid plug with a drilled hole was put in instead.

The licensee will order and install the proper plug.

This is an unresolved item.

(315/79-08-03).

c

~

Snubbers 12 GCCW-5841, 12 GCCW-S842, and 1GCCW-S309:

The stiffness of the structure to which the snubber is welded was questionable.

The first two snubbers were attached to cantilever beams without bracing, and the third snubber was welded to the web of a long I-beam.

The licensee agreed to review this matter.

This is an unresolved item.

(315/79-08-04).

d.

Snubbers l GCTS-S161 (two units)

and 1 GCTS-S73 (two units):

The snubber tension and compression chambers were connected by tubing on S73 but not on S161.

The inspector questioned the design difference.

Further, some of the expansion anchor bolts for both S73 and S161 were installed approximately 1.5 inch away from the embedded Uni-Strut channels.

The inspector questioned whether or not the bolt load capacity will be affected.

The licensee agreed to review this matter.

This is an unresolved item.

(315/79-08<<05).

e.

Snubber 1 GCTS-S71:

The inspector observed that four (4)

expansion type concrete anchor bolts had been cut off.

The exact embedment length of the bolts was uncertain.

In addition, two of the six anchor bolts are fastened onto the embedded Uni-Strut.

The inspector questioned the

soundness of such installation.

The licensee agreed to review this matter.

This is an unresolved item.

(315/79-08-06).

The inspector requested that the licensee obtain detail drawings for the areas associated with items c, d, and e above.

No items of noncompliance or deviations were identified in the areas reviewed.

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

Unresolved items disclosed during this inspection are discussed in Paragraphs 1, 3.a, 3.b, 3.c, 3.d, and 3.e of this report.

Exit Interview The inspector met with site representatives (denoted in the Persons Contacted Paragraph)

at the conclusion of the inspection on May 2, 1979.

The inspector summarized the scope and findings of the inspection noted in this report.