IR 05000302/1980002
| ML19309C885 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 02/20/1980 |
| From: | Herdt A, Modenos L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19309C883 | List: |
| References | |
| 50-302-80-02, 50-302-80-2, IEB-79-14, NUDOCS 8004090355 | |
| Download: ML19309C885 (5) | |
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UNITED STATES
NUCLEAR REGULATORY COMMISSION o
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101 MARIETT A ST., N.W., SUITE 3100 o
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g" ATLANTA, GEORGIA 30303
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FEB 2 i 1980
Report No. 50-302/80-02 Licensee: Florida Power Corporation 3201 34th Street, South St. Petersburg, Florida 33733 Facility Name: Crystal River
Docket No. 50-302 License No. DPR-72 Inspection at Crystal River near Crystal River, Florida (January 16-18, 1980)
Gilbert Associates, Inc.,,near Reading, Pennsylvania (January 24-25, 1980)
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Inspector:
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J'ND/S A. R. lierdt, Section Chief, RCES Branch Date' Signed SUMMARY Inspection on January 16-18, and 24-25, 1980 Areas Inspected This special, announced inspection involved 24 inspector-hours on site and Gilbert Associates, Inc., Offices in the areas of seismic analysis for as-built safety-related piping systems (IE Bulletin 79-14) and of concrete expansion anchor installation (IE Bulletin 79-02).
Results
.Of the two areas inspected, no items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees
- D. Poole, Plant Manager
- R. W. Kennedy, Nuclear Compliance Supervisor
- R. C. Widell, Project Engineer
- T. C. Lutkehause, Technical Services Supervisor
- J. Cooper, Jr., Nuclear, QA/QC Compliance Manager
- J. L. Bufe, Nuclear Compliance Auditor
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Other Organizations
- F. J. Tomajic, Project Manager, Gilbert Associates, Inc. (GAI)
- R. C. llolzwarth, QA Project Manager (GAI)
- 11. R. Wardrop, Project Structural Engineer (GAI)
- K. Ilodland, Section Manager (GAI)
- C Chen, Section Manager (GAI)
- J. E. Lisney, Structural Engineer (GAI)
- W. D. Thomas, Supervisor (GAI)
- Attended exit interview at Crystal River.
- Attended exit interview at GAI.
2.
Exit Interview The inspection scope and findings were summarized on January 18, 1980, at the Crystal River site and on January 25, 1980, at the GAI offices with those persons indicated in paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
(Open) 1E Bulletin 79-02 - Concrete Expansion Anchors The following Licensee Event Reports (LERs) identified by Florida Power Corporation (FPC) to the NRC were reviewed by the inspector during the inspection at the site on January 16-18, 1980:
LER 79-061 (Closed)
187 Supports with a Factor of Safety (FS) less than 4.
7 Supports with a FS less than 2.
LER 79-087-0 (0 pen)
19 Service Water Supports with a FS less than 2.
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-2-LER 79-087-1 (Closed)
Horizontal Support placed as a Vertical Support LER 79-082-2 (0 pen)
47 Supports with a FS less than 4 LER 79-082-3 (0 pen)
Pipe stress at reducer exceeding allowable stresses LER 79-082-4 (0 pen)
7 Service Water supports with a FS less than 2 A total of six LERs were identified.
Two LERs have been closed out with repair work completed. Four LERs remain open with 28 supports remaining to be repaired by the next refueling outage scheduled for April 1980.
The inspector selected the following supports identified under LER 79-061 with a FS less than two and reviewed the repair work documentation arrd inspected them in the field to verify their installation:
FWil - 140 FTal - 141 FWii - 162 SWil - 30A CIDI - 22 SFR - 25 SWR - 515 FpC Procedure No. QC-1700 Rev. O, dated December 13, 1979, " Review and
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Control of Quality Work Documentation" was reviewed by the inspector. This procedure is to assure future modifications to the plant are handled efficiently.
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During the inspection on January 24-25, 1980 of the GAI in Reading, Pennsylvania, the inspector was given a description on how the FS was calculated and used for anchor bolts with base plate supports. All support loads were recalculated due to the fact that GAI did not have the original design loads. All plates were assumed to be rigid.
If the FS was less than eight, then GAI analyzed the plate as a flexible plate.
If the FS was less.than four, GAI automatically redesigned the support. A loading of 2 times the OBE was used in the analysis design.
Inspections of oversize holes were not conducted because Wej-Its were primarily used throughout the
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plant. During the inspection of the Wej-Its it was not required to remove the bolt and washer for inspection, therefore, FPC could not inspect for oversize bolt holes. During construction installation of Wej-Its the holes were drilled thru the plate, therefore, oversize holes should not appear.
The calculations on the FS for supports FWM-140, FWH-141 and SWR-515 which were inspected at the site on January 16-18, 1980, were reviewed and cross-checked with the data obtained at the field.
Calculations for supports BSil-536 and SWH-403 were also reviewe.
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3-IE Bulletin 79-02 remains open until all inspections and evaluations are completed and subsequently reviewed by the NRC.
No items of noncompliance or dev ions were identified.
6.
(0 pen) IE Bulletin 79-14 - Seisimic A.nalysis for As-Built Safety-Related Piping Systems The inspection of Januar, 25, 1980, of GAI Design Engineering Offices was to verify licensee compliance with requirements of IE Bulletin 79-14.
The inspector reviewed surveillance packages and stress analysis of the following isometrics (ISO):
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a.
CR-114
" Nuclear Services Close Cycle Couling", Revision B b.
CR-46
" Emergency Feedwater from No. 3A Emergency Feedwater Pump Inside Intermediate Building", Revision C A description of the method used to follow the requirements of IE Bulletin 79-14 was provided by GAI engineers. Nonconformances were selected by the inspector and a review of pipe stress analysts performed as such that valve weights and proper codes were being checked and followed.
The inspector noted that material properties and valve type were not verified.
FPC agreed that these items could be verified by QC documentation and would respond to the builetins requirements accordingly. During the inspection of the reanalysis it was revealed that new suppor.t loadings for concrete expansion anchors had not been done.
The inspector pointed out to the licensee and the AE that this was one of the main requirements of the bulletin. FPC and GAI agreed that all supports requiring a reanalysis would be completed by February 15, 1980. The inspector reminded the licensee that all reanalysis and all upgrading of FS to a minimum of four would have to be accomplished by the end of the next refueling outage in April 1980.
The licensee concurred.
Verification of proper response spectrum curves was accomplished by the review of the following documents:
a.
CR-53
" Decay Heat Closed Cycle Cooling from Pump 3B to Make-up R. B. Spray and Decay Heat Removal Pumps" PI-305-837, Revision E b.
" Crystal River Unit No. 3 FPC Response Spectra for Equipment Stress Analysis" dated August 15, 1973.
c.
" Design Review Certification" dated July 23, 1969 The design review certification identifies the response spectrum curve as CROS which is the ground floor response spectrum curve at elevation 95 feet.
ISO CR-53 has elevations ranging from 75 feet to 199 feet. Any
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depth under 95 feet in this case does not change the response spectrum curve; however, above 95 feet the response spectrum curve would be different.
Therefore, the response spectrum curved used was not correct.
GAI stated it is a general practice to use the higher curves due to its
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higher frequency for conservative design.
However, it is apparent from this example that a review needs to be conducted by GAI of the response spectrum curves used and to assure that the right curves were employed for a particular ISO.
GAI and FPC agreed that they will respond to this problem.
Discussion with GAI QA personnel revealed that no QA audits had been conducted
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for either Bulletins 79-14 or 79-02.
It was agreed upon by the project
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management that GAI will conduct an internal QA audit for both bulletins.
In summary, the following items remain to be addressed by the licensee:
j a.
Verification of material properties
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b.
Verification of valve type
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New support loadings will be calculated for re-analyzed lines d.
Verification of response spectrum curves This IE Bulletin 79-14 remains open until all inspections and evaluations are completed and subsequently reviewed by NRC.
No items of noncompliance or deviations were identified.
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