IR 05000155/1987007
| ML20212A850 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/20/1987 |
| From: | Danielson D, James Gavula NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20212A817 | List: |
| References | |
| 50-155-87-07, 50-155-87-7, NUDOCS 8703030424 | |
| Download: ML20212A850 (4) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-155/87007(DRS)
Docket No. 50-155 License No. DPR-6 Licensee: Censumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Narr.e: Big Rock Point Nuclear Plant Inspection At: Big Rock Point site, Charlevoix, Michigan Jackson Laboratory, Jackson, Michigan (Lab)
Inspection Conducted: February 5, 1987, at the Lab February 6, 1987, at Big Rock Point W
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L/ E0/ P7 Inspector:
J. A. Gavula
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Approved By:
D. H. Danielson, Chief Materials and Prccesses Section Date Inspection Sunnary
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Inspection on February 5-6, 1987 JReportpo. 50-155/87007(DRS)) licensee's
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Areas Inspected: Routine unannounced safety inspection of the Snubber Surveillance and Functional Testing Program (70370) and Training (41400).
Results: No violations or deviations were identified.
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DETAILS 1.
Persons Contacted Consumers Power Ccapany (CPC)
J. D. Gratz, Engineering Analyst D. A. DesNoyer, Supervisory Engineer T. L. Briningstool, Ruality Assurance Administrator
- M. Acker, Inservice Inspection Coordinator
- G. Withrow, Engineering and Maintenance Supervisor
- Denotes those attending the exit meeting.
2.
Inservice Tests for Snubbers a.
Background The Big Rock Point Nuclear Plant has a total of 13 snubbers in the entire plant. All of these are mechanical snubbers and are installed on the Reactor Depressurization System (RDS). The Technical Specification regarding the RDS (Section 4.1.5) has two requirements concerning the snubbers in the system:
(1) Perform a Visual Examination of 10% of the snubbers (VT-3 and VT-4);
(2) Perform a functional Test of 10% of the snubbers based cn specified vendor drag and acceleration acceptance criteria.
The Inservice Inspection (ISI) Program which controls the above examinations is based on Section XI of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, 1977 Editicn with surrer of 1978 Addendum. Section IWF-5400 of the Code requires that if a snubber fails c functional test, another sample of 10% will be tested until all units within the sample pass.
b.
Functional Te_stino_o_f_ Snubbers The snubber functional tests were performed by CPC's Laboratory and Field Technical Services in Jackscn, Michigan. While at the lab, the following procedures were reviewed:
" Big Rcck Point Depressurization System Mechanical Snubber
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Certified Functional Testing" Procedure No. 5-4, Revision 4, dated June 18, 1985.
" Control of Measuring and Test Equipment" Procedure No. LFTS-13, Revision 0, dated February 21, 1986.
The NRC trade the following observations:
The drag force and acceleraticn acceptance criteria were adequately delineated.
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The testing apparatus and equipment configuration were well
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The calibration requirements for all compcnents were included.
- The calibration for the X-Y Recorder used for the functional test was verified during the NRC Inspection. The Hewlett-Packard Time Base Module ID No. 3745-00464 was previously calibrated on April 16, 1986, and is due for calibration on April 16, 1987. During the last calibration period no adjustments were required.
The training and experience level of the test personnel were
adequately specified.
The certification record of the test technician was checked during this inspection. The records for the technician indicated that he was certified as a Level III test technician.
(The procedure required only a Level II).
In addition his visual examination records, qualification records and training records were reviewed. All of
these appeared in good order.
During the current functional tests, one of the initial two 3 kip
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snubbers exceeded the allowable drag force of 30 pounds by 10 pounds.
As a result of this failure, a second set of two snubbers was tested. One of these 3 kip snubbers exceeded the drag force criteria by 15 pounds.
As a result of this failure two additional snubbers were tested.
The NRC inspector witnessed a ducenstration of snubber testing procedure for snubbers PS 115 A and FS 115 B.
Although the final documentation was not issued yet, the results indicated that both snubbers had met the acceleraticn and drag criteria. Based on this information ne further snubber testing would be required during this outage.
c.
On-site Review The Snubber Surveillance Plan for Big Rock Point is currently being ircplemented under the " Forty Year Inservice Inspection (ISI) Plan" Revision 5.
The " Augmented Tables" list all 13 snubbers and their sequence for testing. Records from the lab indicated that the proper sequence of snubber testing had been followed for this
outage.
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The following support detail drawings were reviewed to determine snubber settings:
A-18501 Revision F Dated April 15, 1980 A-18502 Revision E Dated October 12, 1978
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A-18504 Revision C Dated June 1, 1978 I
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O Due to radiological restrictions only four snubbers were observed in the plant. Snubbers PS-116A, PS-116B, PS-109A and PS-109B all appeared clean with all hardware and bolts intact. The tie wires for the snubber to extension spools were all in place. The snubber setting for snubbers PS-109A and PS-109B were within range. No adverse corisents were made relative to the condition of the observed snubbers.
The following procedure was reviewed by the fiRC inspector:
" Visual Exarr.ination" Procedure No. hDT-VT-01, Revision 4 Issued
December 2, 1986.
This procedure gives the requirements for the VT-3 and VT-4 visual examinations required by Technical Specifications.
No adverse cur.cnts were made by the ilRC inspector.
Discussicns with the ISI coordinator indicated that the cause of the current snubber failures would not be determined until Pacific Scientific (PSA) (The maker of the snubbers) examined the units.
Also, the evaluation of the effect on the RDS will be perfomed in the near future. However, in the cpinion of the NRC inspector, an additional 15 pounds of drag force on 12 inch diameter line will be inconsequential and the matter is considered closed.
During further discussions with plant personnel, changes to the current acceptance criteria for snubber acceleration and drag force were censidered. The current criteria utilities the same criteria as PSA for just-assembled units. To expect this same performance after several years of operation is not necessary if an increase in criteria can be analytically justified. This aspect of the snubber testing program will be pursued by the plant personnel in conjunction with PSA and the piping analysts.
3.
E_xit Interview The inspector met with the licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on February 6, 1987.
The inspector sumarized the purpose and findings of the inspection. The licensee representatives acknowledged this information. The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed during the inspection.
The licensee representatives did not identify any such documents cr processes as proprietary.
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