IR 05000395/1990007
| ML20042D732 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 03/15/1990 |
| From: | Wright R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20042D731 | List: |
| References | |
| 50-395-90-07, 50-395-90-7, NUDOCS 9004050199 | |
| Download: ML20042D732 (8) | |
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Report No.:
50-395/90-07
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licensee:
South Carolina Electric & Gas Company Columbia, SC 29218
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Docket No.:
50-395 License No.:
NPF-12 Facility Name:
V. C. Sumer
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Inspection Conducted:
February 26-March 2,1990 Inspector:
'h M
.3 //f /'/0 R. W. Wright d
Date Signed
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Approved by:
/Id.u OW 8//7/[0-
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F. Jape, Section Chief Quality Performance Section (/ /
Date Signed s
Operations Branch
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Division of Reactor Safety t
SUMMARY Scope:
i This routine unannounced inspection was conducted in the areas of design control, design changes and modifications.
Results:
The plant design engineering authority is preparing and implementing design changes and modifications in accordance with their TS, FSAR,10 CFR 50.59 requirements, and their site approved control procedures.
These design
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changes and modifications appear to be both technically and administratively
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acceptable, in the areas inspected no violations or deviations were
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identified.
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REPORT DETAILS l
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Persons Contacted l
Licensee Employees I
- 0. Bradham, Vice President, Nuclear Opertaions
- R. Campbell, Senior Engineer, ISEG
- R. Clary, Manager, Design Engineering
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- H. Donnelly, Senior Engineer, Nuclear Licensing
- J. Fuller Facilities and Administration L
- G. Hall, Associate Manager Health Physics i
- S. Hunt, Manager. Quality Systems i
- A. Koon, Manager, Nuclear Licensing D. Malkmus, Lead Mechanical Engineer, Systems & Performance Engineering
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'G. Moffatt, Manager, Maintenance Services
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- D Moore, General Manager, Engineering f
- K. Nettles, General Manager, Safety
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- C Price, Manager, Technical Oversight
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- J. Skolds, General Manager, Nuclear Plant Operations i
K. Steffy, Lead Mechanical Engineer, Design Engineering j
- G. Taylor, Manager, Operations J. Todd. Lead Structural / Civil Engineer. Design Engineering
R. Waselus, Associate Manager Design Engineering
G. Williams, Lead Mechanical Engineer. Design Engineering-i
- M. Williams, General Manager Adminstrative & Support Service
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S. Zumbrunnen QC Inspector
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I Other licensee employees contacted during this inspection included'
craftsmen, engineers, operators, mechanics, security force members.
- technicians, and administrative personnel.
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Other Organizations f
H. Gorawski, Foreman, Precision Surveillance Corporation
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C. Brooks. QC Supervisor, Precison Surveillance Corporation
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NRC Resident Inspectors
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- R. Presette, Senior Resident Inspector I
- L. Modenos, Resident Inspector
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Other licensee employees contacted during this inspection included engineers, technicians, and administrative personnel.
- Attended exit intervicw l
Acronyms and initialisms used throughout this report are listed in the i
last paragraph.
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Modification Control Program (37700)
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The inspector reviewed the following MRTs to determine the adequacy of the evaluations to meet 10 CFR 50.59 requirements; that appropriate
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design input considerations were made for seismic, environmental. ALARA l
and Appendix R requirementst verify that the MRFs were prepared and installed (for those physically inspectable) with design engineering
program requirements and applicable industry codes and standardst verify i
that the MRFs were reviewed and approved in accordance with TS and
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administrative controls; ensure that aoplicable plant operating documents
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(drawings, plant procedures, FSAR, TS, etc.) were revised to reflect the subject modifications; and post modification test requirements were specified and adequate testing was or is scheduled to be performed as l
necessary.
l To accomplish the above objectives the inspector selected four nuclear
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safety-related MRFs for review.
Two were completed during RF04, one was
currently underway and one is scheduled for installation during RF05
which is scheduled to begin March 23, 1990, t
a.
MRF-32130 and MCN-A, and B, Redesign of Chilled Water Subpiping
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This MRF corrected a deficiency identified by Nonconformance Notice
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2130. Chilled water valves 16365 and 16374 were used for leak
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testing of chilled water active valves 6410 A,B and 6489A,B.
Valves 16365 and 16374 were designed normally closed, safety related valves
and met the requirements of ANSI 18.2 safety to non-safety class l
break isolation, j
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A previous modification, MRF-10868, added additional pipe to the outlet of 16365 and 16374 and isolation valves to move the test connection to a more accessible location. These new isolation valves
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added, 6522 and 6523 were classified non-safety related as was the i
associated piping, j
I MRF-10868 changed the designation of valve 16365 and 16374 to normally open, consequently isolation of that portion of the chilled
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water system was now dependent on valves 6522 and 6523 which was not i
in agreement with ANS! 18.2 design criteria.
This modification removed the non-safety related MRF-10868 piping and valves and i
subsequently redesigned, procured, installed and tested new l
safety-related (ASME Class 3 Service) piping and valves as a l
suitable replacement.
i MCN-A, and B were written to correct three minor drawing dimensional
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errors discovered when checking as-built conditions in the field, i
The inspector conducted discussions with and queried the lead
engineer concerning the redesign, the functional aspects of the
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subject modification, and the supporting documentation contained in the modification package.
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t All work was performed by ten MWRs under existing approved l
procedures.
No prerequisite or hold points (in addition to existing
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procedural hold points) were added.
Procedure GTP-304 was used to i
perform satisfactory VT-2 leak testing of the system.
The new
safety class piping is seismically supported and routed in an area
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that does not contain high energy piping.
Per this MRF the safety j
class boundary of the system is physically relocated to the
discharge of the new valves 6522 and 6523, but is not changed on a functional basis.
The consequences of an accident evaluated in the
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FSAR will not change since this modification does not affect any l
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plant or operator responses to postulated accidents.
l Also the probability of a malfunction of equipment important to
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safety does not change since active equipment is not affected by i
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this modification, t
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i Nonconformance Notice 2130 received appropriate evaluation for j
reportablity under 10 CFR 21 requirements and was determined to be
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not reportable.
The inspector verified that required revisions to
the FSAR, and essential drawings located in the control room had
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been completed per the MRF.
Necessary procedural revisions and
personnel training to these revisions due to this MRF were
accomplished.
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PSRC Meeting No. 88-40, dated October 28, 1988, documented that the
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subject MRF was reviewed and approved per Section 6.5 of the TS and
Station Administrative Procedure SAP-120.
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b.
MRF-20884, Installation of New Core Exit Thermocouple Nozzle
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Assembly Joints (CETNA)
This MRF was for a changeout of the existin core exit thermocouple nozzel assembly joints with a new design w ich can be assembled /
t disassembled in 1/8 of the original time resulting in a substantial i
savings in a critical path time and radiation exposure.
Combustion Engineering technicians performed the work on all four f
columns per Vendor Technical Manual IMS-948-1205 and Work Request No. 20884-001.
CE certified the personnel qualifications of their
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installation and QA personnel selected to perform the work.
The field work was performed in two phases.
Phase I was done with the i
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reactor vessel head on the stand, installing the male flange and make-up clamp on the bottom joint per Appendix A, technical I
instructions.
The bottom joints were successfully hydostatically tested per Appendix B of the subject technical manual.
Phase 2 was
done with the head reinstalled on the vessel. During this phase the
top joint per Section 6 of the technical manual was assembled on all
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four columns.
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As mentioned above, installation verification was performed by CE QA
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personnel with the exception of leak testing which was conducted by
SCE&G QC.
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All joints on the four columns were required to have zero visible leakage af ter repressurizing the reactor coolant system.
All unreviewed safety questions were answered No".
The function of the
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new design is the same as the function of the old design which is to
" seal" the CETNA.
The design change is a replacement in kind and no
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previously unanalyzed malfunction could be created by this changeout.
The 10 CFR 50.59 evaluation performed was found adequate. CE issued new as-built drawings depicting the CETNA modification, voiding or superceding prior existing ones.
CE Design Report No. MISC-ME-DR-004, Revision 0 CETNA ' for V. C. Summer Nuclear Station was verified to have been revised to reflect the sukiect modification.
The MRF did not require any applicable sections at the FSAR, FPER or plant TS to be changed.
PSRC Meeting No. 89-27, dated May 31, 1989, documented in its meeting
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minutes that the subject MRF was reviewed and approved in accordance with Section 6.5 of the TS and Station Administrative Procedure SAP-120, c.
MRF-21562 and MCN-A, and B. Vertical Tendon Retensioning This MRF was generated to restress the vertical. tendons on the exterior reactor building shell.
This restress is necessary due to greater-than-expected relaxation in the tendon wire.
Based on available data from the first three surveillances, the reactor building vertical tendons were not anticipated to go below their minimum design values until 1993.
This MRF should restore a sufficient force margin over the minimum required' TS value for the remainder of the plant life.
The work is currently ongoing, being performed by PSC utilizing their procedures and some SCE&G/QC personnel working for a PSC QC supervisor.
Any changes during the course of work which affect design or specification documents by G/C require an MCN ' > processing.
To date the following minor MCNs have been writte (or the following reasons:
MCN-A This change notice was generated to include several procedural changes that relate to the tendon retensioning and surveillarce work.
MCN-B Written to accomplish additional procedural changes that increased efficiency and quality of the tendon work.
The restress work is approximately 75 percent complete. The inspector observed the lift-off forces developed and restressing of vertical tendons V-27 and V-29.
Their existing lift-off forces of 1214 and 1198 kips respectively exceeded the TS minimum required average tendon force level of 1160 kips which is to be maintained throughout the life of the plant.
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l Observation of the work in progress; discussions with the lead engineer, PSC foreman, and QC inspectors; and review of the subject t
tendon stressing records indicates the work is being managed properly i
and satisfactorily implemented.
It appears that most of the vertical tendon restressing will be done while the plant is at power with the possiblity that some work may extend over into RF05 beginning
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March 23, 1990.
To date only one surveillance tendon has failed to meet the minimal
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tensile force of 1160 kips and this incident was identified February 6,1990, as Nonconformance Notice NCN 3674, which was evaluated by design, examined for reportability, and appropriately
dispositioned.
It was determined by additional testing and design i
evaluation that the vertical tendon group could still meet the minimum 1160 kip average force.
Therefore the TS margin of safety i
was not affected.
The 10 CrR 50.59 safety analyses appeared adequate.
There is no adverse impact for tendon work at power provided the limitations on detensioning of tendons given in the MRF are followed.
Likewise, there is no increase in accident potential nor does it decrease the
marg N of safety of the TS.
The SCE&G Procurement Technical Requirements, PTR-SC-33, Revision 0, Vertical Tendon Retensioning is part of the MRF package since it is
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nuclear safety related and contains design information for
restressing.
This PTR was reviewed by the inspector along with the remaining MRF package documentation which included; Appendix R and t
load change reviews, other discipline interface review responses,
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technical work records, engineering prerequistes/ hold points and the preliminary TS Operability / Return to Service System record.
The package was prepared in accordance with approved Engineering Services Procedure ES-416, Design Modification Change Process and Control.
No post modification testing nor revision to the TS is required as a result of this MRF.
Discussions with the lead engineer disclosed.
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that Section 3.8 of the FSAR will be revised to briefly discuss the
altered initial tendon design created by restressing the vertical tendons, d.
MRF-21309, Replacement of XVG-503, A, B & C 1 BD Isolation Valves This modification involves three changes to reduce system start-up transient loadings to an acceptable level, two of which are
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non-safety related and were not examined by the inspector and the third which involved replacement the above nuclear-safety related valves.
Existing steam generator blowdown isolation valves XVG-503 A, B & C are flexible-wedge gate valves that are susceptible to thermal binding when they are closed for blowdown isolation.
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This thermal binding problem requires excessive maintenance time and use of extreme procedures such as heating the valve to reopen it.
This MRF replaces the flexible-wedge gate valves with the double-disc (split wedge), parallel seat configuration gate valves which are
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designed to minimize the occurrence of thermal binding.
Also, the
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MRF recommends the existing air operators be replaced with a more
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compact design (with enclosed spring) which requires 1/3 less thrust
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force to operate the double-disc parallel seat configuration gate i
valves.
The active safety function of the exitting valves is to close and isolate the flow from the steam generator and provide containment isolation.
The active function of the replacement valves remains unchanged.
Thus the probability and consequences of previously evaluated occurrences are not increaseo.
The revised loadings, due to valve mass change, have been evaluated to assure the ' existing blowdown system's design stresses are not exceeded in the piping or supports, ho new possibilities of an accident or malfunction of equipment imiortant to safety previously evaluated or different from any already evaluated are increased or created respectively.
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The modification does not involve or affect an Appendix R related system, nor are electrical system loading changes involved.
The engineering instructions to implement installation are clear, the 10 CFR 50.59 assessment is adequate and the post modification testing specified as enhanced by Quality Assurance's Review Coments appears satisfactory.
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This modification is scheduled to be installed during RF0-5 beginning March 23, 1990, and upon completion specific FSAR plant changes, training and procedural revisions and as-built drawing revisions have been designated to reflect the MRF.
The modification does not effect any porticns of the existing systems covered by the TS.
Inspection of the four above mentioned modifications to the review criteria specified resulted in no violations or deviations being identified.
The inspector concluded from this sampling of modification packages that the plants design authority is preparing and implementing design modifications in accordance with the sites approved control procedures and these modifications appear to be both technically and administrative 1y acceptable.
3.
Exit Interview The inspection scope and results were summarized on March 2,1990, with those persons indicated in paragraph 1.
The inspector described the areas inspected and discussed in detail the inspection results listed above.
Proprietary information is not contained in this report.
Dissenting comments were not received from the licensee.
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Acronyms and initialisms ALARA As Low as Reasonably Achievable ANSI American National Standards Institute ASME American Society of Mechanical Engineers CE Combustion Engineering CETNA Core Exit Themonuclear Nozzle Assembly FPER Fire Protection Evaluation Report FSAR Final Safety Analysis Report G/C Gilbert /Coninonwealth Engineers and Consultants Kips 1000 Pounds Force MCN Modification Change Notice MRF Modification Request Fom MWR Maintenance Work Request PTR Procurement Technical Requirements PSC Precision Surveillance Corporation PSRC Plant Safety Review Committee QA Quality Assurance QC Quality Control RF0 Refueling Outage SCE&G South Carolina Electric and Gas TS Technical Specifications
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