IR 05000245/1979015
| ML19254D875 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/08/1979 |
| From: | Caphton D, Durr J, Foley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19254D862 | List: |
| References | |
| 50-245-79-15, NUDOCS 7910300279 | |
| Download: ML19254D875 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I
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Report No. 79-15 Docket No.
050-245 License No.
DPR-21 Priority:
Category: C
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Licensee:
Northeast Nuclear Energy Co PO Box 270 Hartford, CT Facility Name:
Millstone Nuclear Power Staticn, Unit 1 Inspection at:
Waterford, CT Inspection conducted:
June 6-8 19 9 Inspectors:
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T Foley, Reactor Inspectori dat4s/gnef
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ju Durr ReactopInspector date signed g
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Approved by':
,1, D. L. Cap'titon, Chief, Nuclear Support date signed Section No. 1, RO&NS Branch Inspection Summary:
Insoection on June 6-8, 1979 (Report No. 50-245/79-15)
Areas Inspected:
Routine, unannounced inspection by regional based inspectors of ?" veillance of pipe support and restraint systems, licensee act. ion on previous inspection findings and follow up on IE Bulletin 79-02 activities.
The inspection involved 38 inspector-hours on site by two NRC regional based inspectors.
Results:
Of tha three areas inspected, no items of noncompliance were found in two areas and one item of noncompliance was found in the third area (Deficiency - Failure to follow procedure, Paragraph 4a(2)(b)).
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-2-Details 1.
Persons Contacted NNECO F. Dacimo, Quality Assurance Supervisor
- R. J. Herbert, Unit No. 1 Superintendent J. Leason, Engineer J. Opeka, Plant Superintendent
- R.
J. Palmieri, Engineer
- V. Papadopoli, Engineer
- P. J. Przekop, Engineering Supervisor
- W. D. Romberg, Operations Supervisor
- K. B. Thomas, :ngineer NUCSO W. Axt, Engineer R. Factora, Senior Engineer S. Shea, Engineer Bechtel H. Kassel, Project Engineer W. Oliver, Field Lead Engineer EBASCO M. Seminatore, Leading Engineer The in;pector also talked with and interviewed several other licensee employees during the inspection.
They included health physic technicians, maintenance and quality control personnel.
- Denotes those who attended the exit interview.
2.
Previous Inspection Items a.
Ite.,s Closed (Closed) Unresolved Item (245/77-32-01):
The licensee's functional test procedures have been combined and revised to incorporate specific acceptance criteria for lockup and bleed rates to verify snubber operability in accordance with design specifications.
The licensee has also included a precaution to preclude the entrapment of air during removal and installa-tion of snubbers.
This item is closed.
(Closed) Unresolved Item (245/78-13-01):
The licensee has recently sent to Wyle Laboratories all hydraulic snubbers for replacement 1238 035
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-3-of seals with ethylene propylene type meterial and subse-quently has reinstalled those snubbers.
This itee is closed.
(Closed) Unresolved Item (245/77-32-02):
The licensec has completed an evaluation of how the lockup and bleed rates are affected by the different temperatures, hence different fluid viscosities during functional testing, operating conditions and during thermal transient conditions.
As a result of this analysis, the licensee has sent all hydraulic snubbers to Wyle Laboratories to be rebuilt, reset and tested to new acceptance criteria which accounts for this thermal discrep-ancy.
These snubbers are presently being installed after being functionally tested by Wyle Laboratories.
This item is closed.
b.
Items 9emaining Open (0 pen) Unresolved Item (245/78-17-05):
The licensee is in process of revising TES Drawing No. A4498.
The TES drawing has not yet been corrected. sThis item remains open.
(Ope:0 Unresolved Item (245/78-17-07):
The four mechanical snubbers recently installed on the IC system have not been added to the Technical Specifications (T/5) Table 3.6.1.
The licensee maintains that mecnanical sndobers are not required to be added to (T/S) Table 3.6.1.
TLis item will receive further NRC review and remains open.
(0 pen) Unresolved Item (245/77-32-03):
The licensee's repre-sentative statad that the Procedure for Visual Examination of Piping Restraints and Supports will be revised to incorporate a snubber setting and provide acceptance criteria for snubber settings by December 1980.
This item remains open.
3.
Review of Bulletin 79-02 Activit y a.
The licensee has decided to replace all seismic Category I shell type concrete expansion anchors with the wedge type.
This will eliminate any testing and verification of installed anchors reccmmended by the Bulletin.
The anchor replacement involves approximately 425 supports out of a total of 580.
There have been approximately 155 supports identified as being loaded only in compression and, therefore, do not require anchor bolt replacement.
b.
The removal and installation of the concrete anchor bolts is controlled by Procedure 79-1-24, Revision 1, titled "Installa-tion of Concrete Fasteners." A review of the procedure disclosed the following discrepancies:
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-4-(1) Paragraph 7.1.5 " Field Changes" does not appear to provide a formal, controlled system to assure adequate pr) cessing of reinforcing steel cutting documentation.
(2) The torque values given on the " Concrete Fastener Instal-lation Record" are not substantiated by manufacturers or site specific test data.
The Hilti manual, page 4, paragraph 8, implies that actual testing should be performed.
These items are unresolved pending disposition by the licensee and review ty the NRC (245/79-15-01).
c.
The inspector visually examined the as installed condition of the replacement anchor bolts and work in progress.
He made selected bolt measurements to verify proper bolt embedment depth.
He discussed the technical aspects of the anchor bolt replacement program with the working craftsmen, quality control inspectors, supervisors, and engineers.
No items of noncompliance were identified.
d.
During the foregoing anchor bolt inspection, the inspector observed that the foundation pedestal for the
"C" Reactor Building Closed Loop Cooling Water Heat Exchanger was cracked and spalling.
The licensee issued Maintenance Request No.
1563-79 requesting an engineering inve, igation and disposi-tion.
This item is unresolved pending the engineering dispo-sition and NRC review (245/79-15-02).
4.
Pipe Support and Restraint Surveillance a.
Review of Progran and Procedures (1) The inspector reviewed the following documents to deter-mine whether the licensee's procedures and program are technically adequate and are in accordance with Technical Specifications.
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Procedure 739.1, Hydraulic Shack Suppressor and Sway Arrestor Repair and Te=>ang, Rev. 3, August 2, 1979.
(b) Procedure 673.2, Inspection of Hydraulic Snubbers, Rev. 2, February 5, 1979.
(c)
Procedure 781.1, Hydraulic Snubber Functional Test, Rev. 1, January 19, 1978.
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-5-(d)
Inte-Office Memo MP-1, from T. Manson to R. Palmeri, J
,, '979.
se, Proceuare.iU-VT-1, Pt v.edure for Visual Examination, Rev. 1, January 17, 13/9 and Change 1, May 10, 1979.
(f)
Inservice Inspection Ten Year Program for Northeast Utilities, Millstone Point Unit No. 1, Rev. 1, Volume 1, June 1, 1977.
(g)
Invoice to:
Northeast Nuclear Energy Co., Purchase Order No. 607502 from Wyle Laboratories, May 7, 1979.
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'1 (2) With the exception of the items listed belew,. the inspec-tor identified no significant problems.
(a)
The licensee's procedure SP-673.2, Inspection of Hydraulic Snubbers, does not contain specific acceptance criteria for piston rod extension, which would be used to determine that the snubber has sufficient piston stroke for thermal expansion or contraction, and thereby aid in determining the total snubber operability.
This item is unresolved pending inclusion of acceptance criteria for piston rod extension into Procedure SP-673.2 and is desig-nated (245/79-15-03).
(b) The licensee's procedure SP-781.1, Hydraulic Snubber Functional Test, requires that functional testing be performed in accordance with Procedure MP-739.1, Hydraulic Shock Suppressor and Sway Arrestor Repair and Testing. A review of the Hydraulic Snubber Functional Test data sheets completed May 1, 1979, revealed that the fluid levels for Giinnel and Bergen-Paterson snubbers were not recorded as required by Step 5.1 of MP-739.1.
This failure to follow procedure is contrary to TS 6.8.1 and is an item of noncompliance at the deficiency leuel.
(245/79-15-04l.
(c)
1.
The licensee's procedure NU-VT 1, Procedure for Visual Examination, has incorporated Change 1 dated May 10, 1979, which deletes the req > ire-ment tc cecord load settings required by Paragraph F.3.5 for mechanical variable supports, but does not modify the requirement 1238 038
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-6-to record hanger settings for support compo-nents as specified in 8.3.0(d) of the same procedure.
2.
It was noted that the completed data sheet for NU-VT-1, not yet reviewed by the station repre-sentative, indicated the following:
Hanger load settings were not recorded as required by B.3.0(d).
Examination results were not always recorded as required by 6.5.
Portions of data sheets not applicable were not recorded as N/A as required by 6.10.
The inspector also noted anchor bolt replace-ment work in progress.
The licensee's repre-sentative stated that all supports associated with the ancher bolt replacement would be inspected and discrepancies dispositioned prior to start up.
This item is unresolved pending reinspection and disposition of supports associated with the anchor bolt replacement and review, correction and dis-
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position of NU-VT-1 data sheets.
This un-resolved item is designated (245/79-15-05).
b.
Observation The inspector accompanied the licensee into the drywell and torus area for a visual inspection of snubbers and other variable supports. Several snubber installations and hangers were noted to be dismantled due to outage work in progress.
The licensee's representative stated that the Nuclear Quality Control inspection will take place upon completion of the anchor bolt replacement.
Discrepancies will be identified and dispositioned at that time.
The inspector verified numerous fixed pipe supports to be in accordance with design drawings on the Low Pressure Coolant Injection cross connec-tion, Main Steam Relief Lines and Isolation Condenser Lines.
The inspector had no further questions at this time.
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P-7-5.
Unresolved Items Items about which mere information is required to determine accept-ability are considered unresolved.
Unresolved items are identified in Paragraphs 3 and 4 of this report.
6.
Exit Interview The inspector met with licensee representatives (denoted in Para-graph 1) on June 8, 1979.
The inspector summarized the findings cd the inspection.
The licensee representatives acknowledged the item of noncompliance and unresolved items disclosed in this report.
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