IR 05000395/1980041
| ML19350A386 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 02/05/1981 |
| From: | Falconer D, Quick D, Whitener H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19350A384 | List: |
| References | |
| 50-395-80-41, NUDOCS 8103130678 | |
| Download: ML19350A386 (3) | |
Text
{{#Wiki_filter:, . d' 'o UNITED STATES '
' ~,, NUCLEAR REGULATORY COMMISSION , g g ae REGION 11
[[ 101 MARIETTA ST., N.W., SUITE 3100 o, ATLANTA, GEORGIA 30303 % o..... Report No. 50-395/80-41 Licensee: South Carolina Electric and Gas Company Columbia, SC 29218 Facility Name: Summer Docket Nos. 50-395 License No. CPPR-94 Inspection at Summer Site near Winnsboro, South Carolina 2/ / ['/ Inspector: /h ~ Oate' Signed j~ H. L'. Whitener
$YY D. P. Falcone ~bs-2lSlfl ' ww Dite Signed ~~ .[. C.
2/II8/ Approved by: 0. R. Qufck, Section CWYef, RONS Branch Date Signed SUYPARY Inspection on December 8' 2, 1980 Areas Inspected This routine, announced inspection involved 63 inspector-hours onsite in the areas of preoperational procedure and program review.
Results 'Of the areas inspected, no violations or deviations were identified.
, ! . 8103130678 - ' - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
. . DETAILS 1.
Persons Contacted Licensee Employees
- 0. S. Bradham, Plant Manager
- S. Smith, Maintenance Supervisor
- A. R. Koon, Nuclear Operations, Technical Gilbert Associates
- D. A. Boward, Lead Startup Engineer
- H. B. Thickman, ILRT Test Supervisor Westinghouse B. Poirier, Test Engineer J. Munford, Test Engineer NRC Resident Inspector
- J. Skolds, Senior Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 12,1980, with-those persons indicated in Paragraph 1 above.
' ' 3.
Licensee Action on Previous Inspection Findings , Not inspected.
4.
Unresolved Items l Unresolved items were not identifed during this inspection.
a 5.
Integrated Leak Rate Test Procedure The inspector reviewed the procedure for the integrated leak rate test (LR-3 dated May 20, 1980) to ensure that the requirements of Appendix J to 10CFR50, ANSI 45.4, Section 6.2 and 14.1 of the FSAR and Regulatory Guide 1.68 were included.
The inspection included - review of penetration valve alignments; system venting and draining alignments; inspection of certain penetrations; review of test conditions including instrumentation, pressure and acceptance criteria; and, discussion of NRC interpretations and requirements.
The inspector concluded that the procedure was technically acceptable.
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6.
Preoperational Test Program The preoperational test program was compared to NRC requi rement s and licensee commitments, ensuring that a test procedure has been written, reviewed and approved for each of the required systems set forth in Regulatory Guide 1.68 and applicable portions of the FSAR.
No violations were identified.
7.
Refueling Procedures The inspector reviewed the following refueling related procedures: - GOP-10, Preparation for Refueling, Rev. 3, cated July 30, 1980 - GOP-11, Plant Recovery from Refueling and Return to Cold Shutcown, Rev.1, dated June 27, 1980.
- EOP-7, Refueling Emergency, Rev. O, dated December 3,1980 As a result of this review, three open items were identified as discussed in paragraphs 7.a, 7.b and 7.c below, a.
GOP-10 and GOP-11, steps 4.6 and 4.3 respectively, caution that while the reactor vessel closure head is removed, Technical Specification requirements of Section 3.9 must be observed.
These requirements are applicable in Mode 6, but Table 1.1 of the Technical Specifications, in part, defines Mode 6 as the vessel head closure studs being less than fully tensioned.
As stated, steps 4.6 and 4.3 do not adequately reflect the Mode 6 definition in the Technical Specifications. This is identified as an open item pending correction (395/80-41-01).
b.
GOP-10, step 6.6, does not adequately incorporate Technical Specification 3.9.2.
As stated, the requirement that one source range detector be audible in the control room is not included. GOP-10 also references the wrong procedures as exemplified in steps 5.5.6, 5.5.7 and 5.5.8.
This is identified as an open item pending correction (395/80-41-02), c.
E0P-7, step 3.1.4A does not reference a procedure for aligning the RWST to the Refueling Cavity via the Spent Fuel Cooling System. Step 3.1.4A d also references GOP-10 as the procedure for aligning the RWST to the Refueling Cavity via the Residual Heat Removal System although SOP-115 is the procedure that accomplishes this alignment. This is identified as an open item pending correction (395/80-41-03). }}