IR 05000269/1978033
| ML15223A394 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/26/1978 |
| From: | Brooks E, Andrea Johnson, Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15223A390 | List: |
| References | |
| 50-269-78-33, 50-270-78-31, 50-287-78-33, NUDOCS 7901170401 | |
| Download: ML15223A394 (10) | |
Text
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(qUNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
a101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos.:
50-269/78-33, 50-270/78-31 and 50-287/78-33 Docket Nos.:
50-269, 50-270 and 50-287 License Nos.: DPR-38, DPR-47 and DPR-55 Licensee:
Duke Power Company Post Office Box 2178 422 Church Street Charlotte, North Carolina 28242 Facility Name:
Oconee Units 1, 2 and 3 Inspection at:
Oconee Site, Seneca, South Carolina Inspection conducted:
November 27 -
December 1, 1978 Inspectors: A. H. Johnson E. H. Brooks Accompanying Personne * None Approved by:
'11t R. D. Martin, Chief
/bat Nuclear Support Section No. 1 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on November 27 - December 1, 1978 (Report No /78-33, 50-270/78-31 and 50-287/78-33)
Areas Inspected:
Routine, unannounced inspection of plant surveillance program of pipe support and restraint systems and plant maintenance program. The inspection involved 68 inspector-hours on-site by 2 NRC inspector Results:
In the areas inspected, no items of noncompliance or deviations were identifie o401
RII Rpt. Nos. 50-269/78-33, 50-270/78-31,and 50-287/78-33 I-1 DETAILS I Prepared by:
/__
_-_2_
E. H. Brooks, Reactor Inspector Date Nuclear Support Section No. I Reactor Operations and Nuclear Support Branch A. H. John 4, Reactor Inspector Date Nuclear Suport Section No. 1 Reactor Operations and Nuclear Support Branch Dates of Inspection: Nvember 27 - December 1, 1978 Reviewed by:_
___4,
___
R. D. Martin, Chief
"Date Nuclear Support Section No. I Reactor Operations and Nuclear Support Branch Persons Contacted
- J. E. Smith, Manager
- S. Baldwin, Jr., Engineer
- R. T. Bond, Licensing and Projects Engineer
- D. J. Vito, Licensing Engineer
- D. M. Thompson, Mechanical Maintenance Engineer
- J. M. Davis, Superintendent of Maintenance
- R. J. Brackett, Quality Assurance
- B. W. Carney, Assistant Engineer, Maintenance
- Denotes those present at exit intervie.
Licensee Action on Previous Inspection Findings Not Applicable Unresolved Items Unresolved items are matter about which more information is required in order to ascertain whether they are acceptable items, items of noncom pliance or deviation An unresolved item disclosed during the inspection is discussed in paragraph RII Rpt. Nos. 50-269/78-33, 50-270/78-31,and 50-287/78-33 1-2 Exit Interview The inspectors met with the licensee representatives (denoted in para graph 1) at the conclusion of the inspection on December 1, 197 All items presented in these details were discusse With regard to the unresolved item, the committments and agreements as stated by the licensee are identified and discussed in paragraph.
Inspection of Pipe Support and Restraint Systems The inspectors reviewed the licensee's surveillance and maintenance procedures for safety-related hydraulic supports and restraint Subsequent to review of the procedures, visual inspections were conducted of both accessible and inaccessible (within the reactor building) restraints installed in Unit 2, which was in a refueling outag Accessible restraints were inspected on units I and Procedures were reviewed, and inspections conducted as follows: Procedures Reviewed MP/2/A/3000/12 -
Inspection of Inaccessible Hydraulic Suppressors on Unit 2 MP/0/A/3000/12 -
Functional Testing of Hydraulic Suppressors MP/1/A/3000/12B -
Inspection of Accessible Hydraulic Suppressors on Unit I MP/2/A/3000/12B -
Inspection of Accessible Hydraulic Suppressors on Unit 2 MP/3/A/3000/12 -
Inspection of Inaccessible Hydraulic Suppressors on Unit 3 MP/3/A/3000/12B -
Inspection of Accessible Hydraulic Suppressors on Unit 3 MP/0/A/3000/24 -
Removal, Reinstallation and Repair of Structural Connections MP/0/A/3000/26 -
Repair and Functional Test of Hydraulic Suppressors (Miller Cylinder Design)
NP/0/A/3000/27 -
(Tompkins - Johnson Cylinder Design)
MP/0/A/3000/28 -
(Lynair Cylinder Design)
RII Rpt. Nos. 50-269/78-33,
50-270/78-31,and 50-287/78-33 1-3 MP/0/A/3000/29 -
Calibration of Suppressor Test Machine MP/0/A/3000/30 -
Repair of Snubber Valve and Function Test of Hydraulic Suppressor MP/0/A/3000/34 -
Inoperative Suppressor Records Review of the above documents confirm that the licensee is in compliance with surveillance requirements for hydraulic snubbers as stated in the Technical Specifications as regards inspection interval and functional testing requirements. The documents confirm that acceptance criteria is identified for lockup rate, bleed rate and reservoir fluid level, and that corrective action is taken to repair or replace inoperable snubber Following is a summary of the visual inspections documented by the licensee:
Unit I -
Accessible Snubbers Date Inoperable Snubbers Next Inspection 12/20/76
6/20/77
+/-
25%
08/8/77
8/08/78
+/-
25%
09/10/77
9/10/78
+/-
25%
02/15/78
9/10/78
+/-
25%
(Unplanned Inspection)
05/5/78
5/05/79
+/-
25%
Unit I -
Inaccessible Snubbers 12/20/76
4/21/77
+/-
25%
03/3/77
7/03/77
+/-
25%
8/11/77
2/11/78
+/-
25%
9/19/77
3/20/78
+/-
25%
05/1/78
5/1/79
+/-
25%
SRII Rpt. Nos. 50-269/78-33, 50-270/78-31,and 50-287/78-33 1-4 Unit 2 - Accessible Snubbers Date Inoperable Snubbers Next Inspection 12/20/76
12/20/77 +/-
25%
06/9/77
6/09/78
+/-
25%
7/18/77
7/18/78
+/-
25%
09/6/77
7/18/78
+/-
25%
(Unplanned Inspection)
05/4/78
5/4/79
+/-
25%
Unit 2 -
Inaccessible Snubbers 12/20/76
04/21/77 +/-
25%
06/8/77
12/8/77
+/-
25%
7/19/77
1/19/78
+/-
25%
11/8/77
5/9/78
+/-
25%
01/5/78
01/5/79
+/-
25%
11/8/78
5/9/80
+
25%
Unit 3 - Accessible Snubbers Date Inoperable Snubbers Next Inspection 8/11/77
9/9/78
+/-
25%
10/24/77
4/24/79
+/-
25%
11/22/77
5/23/79
+/-
25%
11/20/78
5/23/79
+/-
25%
(Unplanned Inspection)
Unit 3 - Inaccessible Snubbers 2/16/77
8/17/77
+/-
25%
RII Rpt. Nos. 50-269/78-33, 50-270/78-31,and 50-287/78-33 I-5 7/19/77
7/19/78
+/-
25%
10/26/77
10/26/78 +/-
25%
11/3/77
10/26/78 +/-
25%
(Unplanned Inspection)
11/25/77
11/25/78 +/-
25%
06/28/78
06/28/79 +/-
25%
Cursory review of functional testing of hydraulic snubbers for Units 1, 2, and 3 provided assurance that tests were being performed in accordance with the licensees Technical Specifications and maintenance procedure Inspections Conducted The inspectors, accompanied by the resident reactor inspector, examined inaccessible hydraulic snubbers in the Unit 2 reactor building. During the inspection several snubbers were found to have low levels in the fluid reservoir Reexamination of the licensees documentation of visual inspection for unit 2 showed that during the most recent inspection performed November 11, 1978, no inoperable snubbers were identifie On the basis of these findings, it was decided to conduct an inspection on as many accessible snubbers as physically possible on units 1, 2 and 3 and inacces sible snubbers on unit 2 in addition to those already inspecte The results of these inspections provided the following findings:
Unit 2
-
Inaccessible safety related snubbers:
5 snubbers with empty integral reservoirs, 3 snubbers with empty remote reservoirs and loose nuts and clevis on several snubbers Unit 2
-
Accessible safety related snubbers:
2 snubbers with inverted integral fluid reservoirs, I snubber with possible seal deterioration (identified as snubber # H-43)
Unit I
-
Accessible safety related snubbers:
I snubber with possible seal deterioration (identified as # H-40),
and loose nuts and clevis on several snubbers Unit 3
-
Accessible safety related snubbers:
loose nuts and clevis' on several snubbers
RII Rpt. Nos. 50-269/78-33, 50-270/78-3land 50-287/78-33 1-6 c. Additional Items Discussed In addition to the above findings the following items were brought to the attention of the licensee:
1) A general condition of what appeared to be seal deterioration or contamination was observed on non-safety related snubber ) Guidelines are not included in the snubber procedures for selection of snubbers for testin ) Temperature correction factors are not utilized during functional testing of snubber The licensee confirmed that these items would be given further consideratio d. Unresolved Item Unresolved Item: The matter of inoperable snubbers in unit 2 as identified by the NRC inspectors, as compared to the licensee recent (November 11, 1978)
inspection documentation presents a conflicting inspection status and is considered to be an unresolved item subject to subsequent review of the following items by NRC (50-270/78-01).
The licensee agreed to:
1) Provide a report to NRC Region II concerning inoperable snubbers as required by the Technical Specification ) Conduct a 100% inspection of all snubbers on Unit ) Provide assurance that snubbers in units 1 and 3 are not similarly affected (as in unit 2).
4) Submit confirmation that all safety related snubbers are equipped with ethylene propylene seal )
Provide assurance that seals on unit I snubber # H-40 and unit 2 snubber # H-43 have not deteriorate Subsequent Telephone Communication On December 4, 1978 the licensee provided by telephone conversation the following information:
RI Rpt. Nos. 50-269/78-33, 50-270/78-31,and 50-287/78-33 1-7 1) During December 2 and 3 a 100% inspection of all snubbers on unit 2 was conducted. 5 snubbers were declared inoperable due to reservoir damage and fluid leakage due to maintenance activities during the refueling outag The 3 snubbers with remote reservoirs were low on fluid but were considered operable and were refille The 5 inoperable snubbers were removed, refilled with fluid, functionaLLy tested and dissassembled to check the seals. All 5 units were tested successfully and the seals were found to be acceptabl Spare units were installed in unit 2 in place of those remove ) During December 2 and 3 a 100% inspection of units 1 and 3 accessible snubbers was performe No inoperable snubbers were identifie Attempts to view by remote camera, the inaccessible snubbers in unit 3, showed 9 snubbers properly installed, but fluid level in the reservoirs could not be determined. The licensee will perform a 100% inspection of the inaccessible snubbers during the next outag ) The licensee will revise the snubber inspection schedule on unit 2 in accordance with the technicat specifications such that the inaccessible snubbers will be on a 2 months schedule, and the accessible snubbers will be on a 12 month schedul ) The licensee will remove, disassemble and inspect the snubber seal for deterioration on unit 2 snubber # H-4 ) The licensee will remove and test for operability the inverted snubber in which the reservoir outlet hole was uncovere Discussion between the licensee and snubber vendor indicates that inverted snubbers are operable only if the reservoir outlet hole is covered with flui ) During subsequent refueling outages when snubber inspections are scheduled the licensee will perform visual inspections after plant shutdown and again prior to startu. Maintenance Activities The inspectors conducted a
review of the following maintenance activities:
a. Work Request Title 50149 Repair of Suppressor 1-O1A-0-550-R2 Support Plate
RII Rpt. Nos. 50-269/78-33, 50-270/78-31,and 50-287/78-33 1-8 55026A Perform Preventive Maintenance on all Hydraulic Suppressors and Restraints 52463 Perform 10% Inspection of Hydraulic Suppressors 51935 Inspect all safety related Hydraulic Suppressors 51439 Inspect Inaccessible Hydraulic Suppressors 50143 Inspect Accessible Hydraulic Suppressors Procedure Title TM/l/A/6000/2 Repair of Suppressor 1-OlA-0-550-R2 Support MP/0/A/3000/34 Inoperative Suppressor Records MP/0/A/3000/24 Removal, Reinstallation and Repair or Structural Connections MP/2/A/3000/12B Inspection of Accessible Hydraulic Suppressors on Unit 2 MP/2/A/3000/12 Inspection of Inaccessible Hydraulic Suppressors on Unit 2 MP/0/A/3000/12 Functional Testing of Hydraulic Suppressors MP/0/A/3000/30 Repair of Snubber Valve and Functional Test of Hydraulic Suppressor Maintenance Activity Reviews and Acceptance Criteria The maintenance activities of 6.a and 6.b above were reviewed by the inspectors to verify that:
-
The maintenance activities were accomplished using approved procedures by qualified personne SRII Rpt. Nos. 50-269/78-33, 50-270/78-3l,and 50-287/78-33 1-9
-
The required administrative approvals were obtained prior to initiating maintenance activitie The maintenance activities were inspected in accordance with the licensee's requirement Provisions for assuring that system valves, breakers, etc.,
are aligned for normal servic Provisions for testing equipment following maintenanc The inspector used one or more of the following acceptance criteria for the above items:
-
Technical Specifications
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Final Safety Analysis Report
-
-
Nuclear Station Directives 3.3.5, 3.3.15, and 3.1 Administrative Policy Manual, Section 3.3, 4.2, and d. Findings Findings were acceptable with the exception of items addressed in Section 5 of this repor