IR 05000302/1981022
| ML20039B485 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/02/1981 |
| From: | Conlon T, Lenahan J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20039B474 | List: |
| References | |
| 50-302-81-22, IEC-78-08, IEC-78-8, NUDOCS 8112230107 | |
| Download: ML20039B485 (5) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION.
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a REGION 11
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101 MARIETTA ST., N.W., SUITE 3100 o,%
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ATLANTA, GEORGIA 30303
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Report No.- 50-302/81-22 Licensee:
Florida Power Corporation 320134th Street, South St. Petersburg, Florida 33733 Facility Name: Crystal River Docket No. 50-302 License No. DPR-72 Inspection at Crystal River, ite near Crystal River, Florida Inspector:
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J. J. Lenahan //[ '
Date Signed Approved by: M w
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T. E. Conlon, Section Chief Date Signed Engineering Inspection Branch Engineering and Technical Inspection Division
SUMMARY Inspection on October 13-16, 1981
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Areas Inspected This routine, unannounced inspection involved 23 inspector-hours on site in the areas of reactor building tendon surveillance, previously identified inspector followup items, and IE Circular 78-08.
Results Of the three areas inspected, no violations or deviations were identified in two areas; one violation was found in one area (Inadequate Training of QC Inspector -
Paragraph 5).
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REPORT DETAILS 1.
Persons Contacted licensee Employees S. Johnson, Maintenance Staff Engineer
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- J.~ D. Martin, Nuclear Maintenance Engineer i
D. C. Poole, Nuclear Plant Manager
- J. Cooper, Nuclear QA/QC Compliance Manager D. Campbell, Project Engineer
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- G. Boldt, Technical Services Supervisor
- G. Williams, QC Supervisor Other Organizations
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J. B. Bond, Superintendent, VSL Corporation 0. Wright, Foreman, VSL Corporation R. McCrossen, Quality Program Supervisor, VSL Corporation J. Jencik, QC Specialist, Catalytic, Inc.
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J. Rossiter, QC Specialist, Catalytic, Inc.
- NRC Resident Inspector
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- T. Stetka, Senior Resident Inspector
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- B.. Smith, Resident Inspector.
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- Attended exit interview 2.
Exit Interview
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The inspection scope and findings were summarized on-0ctober l'6, 1981 with l
those persons indicated in paragraph I above. The violation described in
paragraph 5 ~was discussed.
3.
Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items
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. Unresolved items were not identified during this inspection.
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5.
Containment Building Tendon Surveillance, Unit 3 The inspector examined procedures, we.rr. activities, - and quality records relating to the Unit 3 tendon surveillance. Details of the inspection are as follows:
a.
Review of Tc..Lo Surveillance Procedure The inspector examined FPC Surveillance Procedure SP-182, Revision 4,
" Reactor Building Structural Integrity Tendon Surveillance Program."-
This procedure specifies the requirements for inspection, testing, analysis and data reporting for the containment building post-tensioning system.
Acceptance criteria examined by the inspector appear in Technical Specification 4.6.1.6 and NRC Regulatory Guide 1.35.
b.
Observation of Tendon Surveillance Work Activities The inspector witne, sed stressing operations for verification of the lift-off forces in horizontal tendon numbers 51H26, 42H2O and 42H40.
These operations.were performed in accordance with the requirements stated in procedure SP-182.
The inspector-examined the anchorage assemblies on terdon number 51H26, 51H45, 4cH20, and 42H40 and verifiad that inspection of the anchorage assemblies was conducted and documented in accordance with the procedure.. The inspector witnessed sampling of the tendon void filler material.(grease) from the ends of the 4 tendons listed above.
c.
Review of Quality Records Relating to Tendon Surveillance Activities The inspector examined the following records relating to tendon surveillance activities:
(1) Stressing ram calibration records for ram numbers 1000-12-5 and 1000-12-7 (2) Prestress force confirmation test (lift-off) results for vertical tendon numbers 12V1,12V20, 34V6, 34V19, 45V16, 56V11 and 61V5 (3) Records of amcunt of bulk filler grease removed during surveil-lance inspection from vertical tendons listed above
(4) Records for anchorage assembly surveillance inspection for vertical tendon listed above (5) Prestress force confirmation test (lift-off)
results for.
horizontal tendon numbers 51H26, 51H45, 42H20, and 42H40
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(6)~. Partially completed inspection check-off lists for tendon numbers
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51H26,-51H45, 42H2O and 42H40.
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Review of' the above-records disclosed the following -violation: The
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inspector. noted.during review of the inspection check-off lists for tendon numbers-42H20 and 51H25.that a licensee NQA/QC inspector had
' signed off hold points signifying that he had witnessed and inspected the anchorage _ inspection and lift-off force confirmation test for these tendons. The inspector who signed off the check-off list had not been present during (and therefore.had not witnessed) this portion of the surveillance inspection for these tendons. However, these surveillance inspection activities had been inspected and witnessed by the surveil-lance inspection contractor's (VSL Corporation) QC inspector in the presence of the NRC inspector..The NRC _ inspector discussed the function of FPC NQA/QC inspector in the tendon surveillance inspection with both the inspector and licensee QC supervisory personnel. Discus-sion with licensee QC supervisory personnel disclosed that the function of the FPC NQA/QC inspector is to verify that the VSL QC inspector is accomplishing the tendon surveillance in accordance with the survell-lance procedure.
The acceptance and inspection of the tendon surveillance work is done by the VSL QC inspector. Discussions with the NQA/QC inspector disclosed that he was not cognizant of his function in. the tendon surveillance inspection and was not properly
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trained for performance of his inspection duties. The inspector was not aware that by signing-off the tendon inspection check list he was
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documenting that he had witnessed the tendon surveillance inspection activities.
Failure to adequately train the NQA/QC inspector as required by 10 CFR 50, Appendix B, Criterion II for inspection of the tendon surveillance activities was identified to the licensee as violation item 302/81-22-01, " Inadequate Training of QC Inspectors."
No deviations were id' entified.
6.
Previously Identified Inspector Followup Item (0 pen) Inspector Followup Item. (302/81-15-04):
Review the licensee's progress in modifying the cable spreading room floor to increase floor loading capacity. During an engineering investigation for a fire protection modification to the cable spreading room, the licensee's A-E, Gilbert Associates Incorporate (GAI), determined that concrete embedments in the walls which provided support to the cable spreading room were inadequate.
The licensee reported this item to NRC Region II as LER 91-51 on August 14, 1981. GAI developed a modification to the floor support system by installa-tion of grout pads on top of reinforced concrete walls which had previously extended to within one inch of the bottom of the steel beams supporting the cable spreading room floor.
These steel beams were supported by the embedments in the walls. This modification did not provide adequate support for the entire cable spreading room. The f.loor loading has been restricted
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in a portion of the cable spreading room for this reason. Tha inspector examined the cable spreading room and noted that the two areas affected by the reduced ' loading requirements have been > clearly designated.
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inspector noted that personnel working in the cable spreading room were complying with the reduced loading requirement.
.The inspector discussed the cable spreading room modifications with the licensee's project engineer responsible for this work. These discussions disclosed the cable spreading room floor is presently capable of supporting a live load of 35 psf. coincident with the ~ structure dead load and design seismic load in all ~ areas except those where the live loading has been restricted. In these areas (the two where' loadirg has been restricted) the allowable live load is 171s psf. The original design criteria specified. an allowable design live load of 60 psf.
The licensee will justify the.
reduction of the live load from 60 psf to 35 psf -in the final design analysis. Due to the reduction in the allowable live load in the cable -
speeding room, access to the cable spreading room is controlled by the shift supervisor and is restricted to comply with the reduced loading require-ments. GAI has completed design.for modifications'to upgrade the allowable
live loading or the entire cable spreading room floor to 35 psf. This modification is currently being -reviewed by the licensee prior to its implementation. This inspector followup. tem remains open pending comple-
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tion of the design analyses and completion of the modification to the cable i
spreading room floor.
No violation or deviations were identified.
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(Closed) IE Circular 78-08:
Enviromental Qualification of Safety-Related
Electrical Equipment at Nuclear Power Plants. This circular was superseded j
by.IE Bulletin 79-01 B.
This circular is closed.
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