ML20133G265
| ML20133G265 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 12/31/1996 |
| From: | Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9701150270 | |
| Download: ML20133G265 (15) | |
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South Carillna Electric & G:s C:mpany Gary J.Trylor P.O. Box 88 Vics Pr:sident i
Jenkinsville. SC 29065 Nuclear Operations i
(803) 345-4344 l
SCFAG ennumamwr December 31,1996 Document Control Desk i
U.S Nuclear Regulatory Commission Washington, DC 20555 3
Gentlemen:
i
Subject:
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)
DOCKET NO. 50/395 l
OPERATING LICENSE NO. NPF-12 h
10 CFR 50.54(a)(3) /10 CFR 50.59(b)(2) ANNUAL REPORT South Carolina Electric & Gas Company (SCE&G), is submitting the thirteenth Annual l
Report pursuant to 10 CFR 50.59(b) and 10 CFR 50.54(a) for Virgil C. Summer Nuclear Station.
1 This report contains a brief description of changes and modifications made to the i
facility or to the quality assurance program, as described in the Final Safety Analysis Report (FSAR) and the Fire Protection Evaluation Report (FPER), as well as a summary of the safety evaluations performed to evaluate these changes.
Non-Conformance Notices (identified by their Non-Conformance Notice [NCN] numoers),
procedure changes (identified by their procedure numbers), Bypass Authorization Requests (identified by the Bypass Authorization Request [BAR] numbers),
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Modification Changes (identified by the Modification Request Form [MRF], and j
Modification Change Notice [MCN] numbers) were completed during the time frame of one year prior to August 6,1995, which ended the thirteenth year following the issuance of the VCSNS Operating License.
i Should you have any questions concerning this issue, please call Mr. Michael J.
l Zaccone at (803) 345-4328.
i Very trulyyurs, i
Ty/o a
i MJZ/GJT/nkk 150039 i
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Enclosure c.
J. L. Skolds NRC Resident inspector 2hl i
W. F. Corway J. B. Knotts, Jr.
j R. R. Mahan RTS (ANN 800)
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. R. J. White File (318.02-8)
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S. D. Ebneter DMS (RC-96-0286) h, A.R. Johnson j
9701150b 0 961231 i
PDR ADOCK 05000395 R
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i THIRTEENTH ANNUAL 10CFR50.59 REPORT 4
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VIRGIL C. SUMMER NUCLEAR STATION j
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j Acronyms and abbreviations used throughout this report are listed on the last page, i
i identification No.
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BAR 94-10 This bypass authorization jumpered out the Pressurizer / Wide Range RCS Pressure Interlocks with SSPS in test to allow opening of the 3 train RHR suction valves. These interlocks are described in FSAR I
Section 7.6.2.1. The reactor vessel head was removed, removing the potential for the RHR piping to be overpressurized. This temporary l
change involved no unreviewed safety questions.
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BAR 95-01 This bypass authorization jumpered out the low pressure purge l
isolation of the VCT. This alarm was replaced with an Operations j
Critical Alarm on the In-Plant Computer System to ensure attention should the VCT pressure decrease toward a vacuum condition.
Normal RCS hydrogen concentration was maintained during this activity. This change affected FSAR Sections 9.3.4.2 and 5.2.3.4 and j
FSAR Table 5.2-10. This BAR does not involve any unreviewed j
safety questions.
i FSAR RN 93-13 This FSAR change removes detailed information from the FSAR 1
concerning implementation of Regulatory Guide 1.97 and maintains j
the information in the Design Basis Document. Neither programs nor existing instrumentation was changed. This change does not involve j
any unreviewed safety questions.
FSAR RN 94-20 This FSAR change revises the ratio of anion to cation resin in the Nuclear Blowdown System domineralizers to provide for a more effective utilization of the resins. This change does not involve any unreviewed safety questions.
FSAR RN 94-25 This change provided a drain line and valve in a temporary spool piece of the Waste Processing System. Based upon this change, FSAR figure 11.2-2 (Sheet 1) was revised. This change does not involve any unreviewed safety questions.
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FSAR RN 94-26 This change involves incorporation of revised material properties and MRF 22552 allowable loads for new and redesigned concrete anchors into the specifications and the FSAR. This change does not involve any unreviewed safety questions.
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FSAR RN 94-29 This FSAR change provides clarification to FSAR Section 12.2.4.2 NCN 4970 concerning the origination of the loss of flow alarm for RMA-4. This change does not involve an unreviewed safety question.
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l FSAR RN 94-32 This change installed a new chiller and circulating pumps to provide t
MRF 34054 chilled water to Non nuclear Safety Related cooling coils, Non-safety i
Related loads were removed from the Safety Related chillers. The 4
FSAR RN added a new Section,9.4.7.2.12, to the FSAR. This change does not involve any unreviewed safety questions.
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i FSAR RN 94-33 This FSAR change removes reference to solidified waste storage pad i
and fencing in Section 11.5.6, since this area is no longer used to store this type of waste. This change does not involve an unreviewed j
safety question.
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FSAR RN 94-37 This change installed additional emergency lighting fixtures in the l
MRF 22357 East and West penetration areas. The RN revised the FSAR and q
section 3.6 of the FPER to address these changes. These changes i
do not involve an unreviewed safety question.
1 FSAR RN 94-38 This change revised the normal design pressure flag on FSAR Figure NCN 4903 6.2-46 for a small portior, of piping upstream of XPS-67-SP to agree with the original design calculations and line specifications. This change does not involve an unreviewed safety question.
FSAR RN 95-01 This change added two test connections to the CVCS alternate MRF 21504 charging line. The RN revised FSAR Figure 9.3-16 (Sheet 10) to incorporate this change. These changes do not involve an unreviewed safety question.
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i FSAR RN 95-03 This change modified the Nuclear Blowdown System to prevent resin MRF 21537 intrusion to the Condensate System and to improve overall system l
performance. This change does not involve an unreviewed safety j
question.
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FSAR RN 95-06 This change introduces an organic biocide treatment for the Service i
MRF 20629 Water System to reduce microbiologically induced corrosion (MIC).
l This change does not involve an unreviewed safety question.
s FSAR RN 95-11 This FSAR change is editorial in that Sections of 3A were revised to 3
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provide the correct reference to Technical Specifications. These j
changes were required based upon recent Technical Specification i
l changes which resulted in renumbering the sections. This change does not involve any unreviewed safety questions.
i FSAR RN 95-13 This change uprated design pressure for the diesel generator air start
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MRF 22519 receiver tanks and raised the relief valve pressure settings. The FSAR RN revised FSAR Figure 9.5-11. This change does not involve j
an unreviewed safety question.
FSAR RN 95-17 This modification relocates the chlorine ejector from within the Waste j
t MRF 21654 Treatment Building to the Chlorine Shed and replaces the automatic l
chlorine switchover module with a three way manual switchover valve. The FSAR RN revised FSAR Figure 9.2-8. This change does i
not involve any unreviewed safety questions.
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FSAR RN 95-19 This modification replaces the existing Target Rock valves with MRF 21611 solenoid gate valves for the Reactor Coolant pressurizer liquid
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MCNI sample and sample isolation valves. These replacement valves have i
maintained the original ASME design basis. This change does not involve any unreviewed safety questions.
FPER RN 94-24 This FPER change provides clarifications to SCE&G's position relative to control of combustible materials as required by Appendix A of BTP 9.5-1. These changes more accurately reflect the fire protection
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j program in effect at V. C. Summer. This change does not involve any unreviewed safety questions.
i FPER RN 94-23 This FPER change revised the description of the RCP Motor Oil i
Collection System to reflect as-built conditions. This change does not involve any unreviewed safety questions.
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l MRF 20951 This modification installs a new fire detection control system which AOP-509.8 supports fire detection devices located throughout the site. This Rev. 0-C modification includes:
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i AOP-509.9 l
Rev.0
- 1. New local control panels and control room graphic display j
AOP-509.17 monitor.
j Rev. 0-D,E
- 2. New conduit and cable, including fiber optic cable.
STP-128.319
- 3. New fire detection devices and replacement of existing devices.
Rev. 3-A
- 4. Rework of existing equipment.
STP-128.320
- 5. Installation of remote addressable modules to monitor position j
Rev.1-A of dry contact devices.
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- 6. New manual alarms, audible appliances and pressure switches.
- 7. Procedure changes to test and reflect these modifications.
These changes do not involve any unreviewed safety questions.
MRF 21632 This MRF provided upgrades to the control room and local panel human factors considerations. This change affected FSAR Figure 9.2-2. These changes do not involve any unreviewed safety questions.
MRF 21934 Drawing D-302-301 (FSAR Figure 10.2-5) was revised to show MRFA correct valve position for the valves associated with generator hydrogen. These changes do not involve any unreviewed safety questions.
MRF 22114 This MRF installed a new expansion tank, vent valves, flow balancing c
orifices and miscellaneous instrumentation changes to the safety related chilled water system. These changes affected FSAR Figures 9.4-22,9.4-23, and 9.2-24. This MRF is being coordinated with MRF
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22594 and 34054. These changes do not involve any unreviewed safety questions.
l MRF 22305 This MRF removes radiation monitors RMA - 5A/B from the plant. The required FSAR revisions were conducted under FSAR RN 95-45 to accommodate the radiation monitor removal. This change affected FSAR Chapter 9. These changes do not involve any unreviewed safety questions.
MRF 22308 Provided the Reload Safety Evaluation for Cycle 8. This was the first MCN A transition core from Vantage 5 to Vantage Plus fuel assemblies. A Reload Safety Evaluation (50.59) was performed. The Reload Safety evaluation includes RCCA reoositioning. MCN A was written to evaluate the addition of a reconstituted assembly in J-64.
A Technical Specification change was made to Section 5. The NRC issued Amendment 105 to the Operating License October 22,1991 regarding operation with Vantage Plus fuel. The identified changes reflect changes to the mechanical, nuclear and thermal hydraulic conditions supporting the Vantage Plus fuel. FSAR Chapter 4 changes to include the use of Vantage Plus fuel have been included with other changes required for MRF-90010, supporting Steam Generator Replacement. These changes do not involve any j
unreviewed safety questions.
MRF 22337 This MRF replaces the main transformer with the spare main transformer. FSAR Figures 1.2-21,8.2-2D, and 9.5-1 are affected by this modification. These changes do not involve any unreviewed j
safety questions.
MRF 22362 This MRF installs new motor operators on valves which are associated with the RBCUs and makes logic changes to other valves to prevent lifting of the relief valves on the RBCU cooling water lines. This change affects FSAR Section 6.2, and Figures 9.2-2 and 9.2-6. STP 223.002A was utilized for post modification retest. These changes do not involve any unreviewed safety questions.
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j MRF 22593 Provides the Reload Safety Evaluation for Cycle 9. This was the first j
MCN A transition core utilizing Performance Plus features. The 50.59 Screening Process worksheet states that the FSAR changes to reflect j
the presence of Vantage Plus fuel are made under MRF-90010.
i MCN A was written to provide the results of the analyses relating to i
j incore tilt issues and the increase of F-delta-H limit. This change is a mark-up to changes already made in FSAR RN-95-22. These
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changes do not involve any unreviewed safety questions.
1 MRF 22594 Switched the cooling water supply for the charging pumps lube oil l
MCN A-D,F coolers and the CCW motor coolers from the safety related chilled water system to the CCW System. Also, the charging pump gear dnve lobe oil coolers were replaced and Appendix R modifications were made to the electrical power supply to the cooling water isolation valves. FSAR Sections 6.3.2, 9.2.2, 9.3.4, 9.4.7, FSAR Table j
3.9.-8, 9.2-3 through 9.2-10, and FSAR Figures 9.2-4,9.2-7,9.4-22
- l through 9.2-24 were affected by these modifications. FPER Sections l
3.2.1,3.3.1,4.2.1,4.4.25,4.5, FPER Table 3.2-1, 3.2-4, 3.2-6, 3.2-7, l
3.4-2, 4.4-3, and FPER Drawing E-023-007 were also affected. These changes do not involve any unreviewed safety questions.
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MRF 22657 This MRF installed backflow preventers on the water treatment and filtered water systems to meet DHEC concerns. This change affected l
FSAR Figures 9.2-8 and 9.2-9A. These changes do not involve any l
unreviewed safety questions.
I MRF 22741 This MRF removes an unused battery charger [previously used for microwave communication power] and reconnects an interfacing power circuit. These changes affected FSAR Figures 1.2-16 and 12.1-19A. These changes do not involve any unreviewed safety questions.
MRF 22746 This MRF provides a computer input for ILT7403-SF on the IPCS plant computer. This change affected FSAR Figure 9.1-3. These changes do not involve any unreviewed safety questions.
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Page 8 of 14 MRF 22749 This MRF removes the Throttle Pressure Limiter circuit in the GE EHC i
system. This change affected FSAR Section 10.2.2.2. These j
changes do not involve any unreviewed safety questions.
MRF 22765 This MRF implemented changes being made for the postulated pressure locking of the RHR/SI sump recirculation valves during a postulated design basis LOCA. This change was performed to i
address NRC IN 95-14 and affected FSAR Section 6.3. STP 105.003 4
was utilized as the post-modification test. These changes do not involve any unreviewed safety questions.
MRF 22766 This MRF provides the direction for the installation of a bypass line around RCDT LGV01003-WL. The function of this bypass line is to insure that containment isolation valve XVD07170-WL can close when both LOVD01003-WL and XVD07136-WL are closed. This change affected FSAR Figure 11.2-2(1). These changes do not involve any unreviewed safety questions.
MRF 34889 This MRF revises plant documentation and performs tests necessary NCN 4889 to increase the design pressure of portions of the CVCS and Si systems to reflect the actual operating conditions in the plant. These changes provide a final disposition to NCN 4889, which addresses replacement of the B charging pump impeller. This MRF also includes upgrade of the design pressure of the charging pump suction piping.
These changes affected FSAR Tables 6.3-1,8.3-3,9.3 5, FSAR Figures 6.3-1, 6.3-4, 9.3-16. These changes do not involve any unreviewed safety questions.
MRF 90001 This change discusses the steam generator replacement activities MCN A,D,U within containment including the actual separation of all piping attached to the generator, in addition to the requirements for fitup of the replacement steam generators and the rewelding of the piping previously separated to the new steam generators.
During the Steam Generator Replacement outage (Refuel 8), all activities that involved the cutting or replacement of components or supports which could have resulted.in the potential for a heavy load to be dropped either onto the fuel or damage a reactor coolant system boundary, was
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conducted with the reactor defueled and all fuel stored in the spent i
l fuel pool.
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This MRF discusses reattachment of piping to the new steam
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generators in accordance with applicable SCE&G cutting and welding l
j procedures. These procedures are compatible with ASME Code i
criteria. This modification also removed temporary interferences and reinstalled and appropriately tested them to assure that the original j
design requirements were met. Performance of activities evaluated in j
this MRF returned the plant to a condition consistent with the original design basis.
i Additional evaluations were completed as part of this MRF for steam i
generator snubber reduction, crossover leg restraint removal and l
steam generator inlet restraint removals, utilizing leak-before-break I
technology, as allowed by revised General Design Criteria 4 (GDC-4).
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These changes do not involve an unreviewed safety question.
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MRF 90001 This change addresses the fabrication and installation of a temporary MCNI penetration seal to accommodate conduits carrying service air, closed circuit TV, and argon gas. This temporary change was removed prior to entering Mode 6 after the completion of steam generator replacement. This change does not involve an unreviewed safety question.
MRF 90002 This MRF included the structural modifications within containment, M CN A-C,F,0 modifications performed outside containment, and rigging. A plan for MMSI-11674 providing alternate fuel oil to the EDGs was developed in the event SOP-307 normal fuel oil was lost during transport of the S/G in support of MCN-Rev. 7-E 90002C. Soil investigations were performed primarily for Containment Access Runway analysis. The MRF installed the temporary structures within containment to remove the old stream generators and installed the new steam generators during RFO 8. Installed "B" Aux. Crane.
Retains Equipment Hatch Bearing Plate and Aux. Crane "B" as permanent plant structures. These changes affected FSAR Figures 1.2-1,1.2-5 through 1.2-7,1.2-12,1.2-13,1.2-26, 6.2-73, 6.2-73A, 6.2-75, 6.2-79A, 6.2-76, 6.2-78, and FSAR Table 3.2-2. These changes do not involve any unreviewed safety questions.
MRF 90003 Revised FSAR Figures 6.2-22,22a,22c,22e, P2g,22i,23, and 25 to reflect the changes rnade inside the S/G Compartments to the FW piping including the affected RB elevations which were performed I
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under MRF-90003. These changes do not involve any unreviewed i
safety questions.
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j MRF 90004 This MRF removes the Feedwater forward / reverse flush system that j
was required for the former steam generators. The MRF was also j
used to reroute the nitrogen supply for steam generator blanketing and to add test switches for the FWlVs. This change affected FSAR
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Tables 3.6-4, 6.2-53, 6.2-54, FSAR Sections 10.4,15.4.2.2, FSAR
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Figures 10.4-12,10.4-13 and 6.2-52. These changes do not involve l
any unreviewed safety questions.
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MRF 90006 Supports the instrumentation portion of the Steam Generator Replacement effort performed under MRF-90001. This MRF primarily deals with the re-routing / extending of instrument impulse tubing to the new tap locations for the Narrow Range ar'd Wide Range S/G Level Transmitters. Also new transmitters will replace the existing S/G Wide i
Range Level and Main Steam Flow Wide and Narrow Range i
Transmitters due to the change in water level span and steam flow i
characteristics for the RSGs. This MRF will also run new conduit i
inside the S/G compartments for Loops A and B to extend the existing j
conduit to the new locations for ITE3322 and ITE3332 (Steam 3
Generator inlet FW Temperature elements). These changes affected FSAR Section 6.3.26.1 and FSAR Table 3.10-3. These changes do not involve any unreviewed safety questions.
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l MRF 90007 Implements all instrumentation and control changes required due to the Steam Generator Replacement /Uprate and deletion of the S/G l
Forward and Reverse Flush System in the 7300 Process Cabinets, Solid State Protection System, Nuclear Instrumentation System, 2
i AMSAC, Main Control Board, Main Annunciation System, Plant Computer, and NTC Simulator. Plant setpoint implementation was included as part of this MRF. These changes affected FSAR Sections 7.2.1.1.2,7.6.7.10,7.6.11.10,7.7.1.7,7.7.1.8, FSAR Tables 7.2-1,
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7.2-3, 7.2-4, 7.5-2, Figures 7.2-1,7.6-10,7.7-6, and 7.7-8. These changes do not involve any unreviewed safety questions.
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MRF 90008 This change addresses the ccnstruction of new permanent site MCN A,B,G facilities required to support Steam Generator replacement. These l
facilities include the Old Steam Generator Recycle Facility, the i
Containment Access Building, the Administration Building and the l
Warehouse / Fabrication Building. Fire Protection requirements for the i
j CN1ainment Access Building were evaluated as part of this change.
l These changes do not involve any unreviewed safety questions.
MRF 90010 Captures each of the evaluations and analyses that were performod 1
for Steam Generator Replacement. NRC submittals dated September 3,1992, March 12,1993, April 30,1993 and October 29,1993, described the Safety Analyses that were performed to support Steam j
Generator Replacement. Many of the analyses submitted for S/G
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replacement were performed at the uprated core power level of 2900 MWt. The changes necessary to support S/G replacement were
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reviewed and approved by the NRC in Amendment 119 to the V. C.
i Summer Operating License. FSAR Amendment 96-02 incorporated i
the FSAR changes for this MRF, which affected Chapters 1,3,4,5,6, 10, and 15. Changes to Chapter 4 have been included in this MRF to incorporate the change to Vantage Plus fuel that was performed in MRF 22308. These changes do not involve any unreviewod safety questions.
MRF 90012 This MRF provides a temporary medium voltage power supply for steam generator replacement activities in containment. These changes do not involve any unreviewed safety questions.
EOP 2.2 This change to EOP-2.2, Transfer to Cold Leg Recirculatior., adds a Rev. 7 caution about high radiation levels, revised Step 11 to stop n single Charging pump and reworded Step 6-AA for clarification. This change does r'ot involve any unreviewed eafety questions.
FPP-003 This change to the fire protection procedures allowed the temporary Rev. 7-B use of non fire retardant wood in the Reactor Building in conjunction with the Steam Generator Replacement Project. This change does not involve any unreviewed safety questions.
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GOP-9 This change allows for the replacement of S/G manway gaskets or Rev. 2-A opening the S/G primary side without having to remove the Pressurizer manway. This change does not involve any unroviewed safety questions.
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3 PSP This change to the Physical Security Plan incorporated changes to the Amendment 34 Nuclear Protection Services organization, reflected the addition of a security camera and describes security communications equipment and facilities. These changes do not involve any unreviewed safety questions.
PTP-106.002 This procedure allows evaluation of FCV00122 flow capacity after this Rev.O flow control valve received maintenance. This change does not involve any unreviewed safety questions.
PTP-102.001 These procedure changes reflect changes to the Main Turbine Weekly Rev.10-D,E Tests following S/G replacement to gather data for full power Turbine Valve testing. These changes do not involve any unrevi A, ed safety questions.
PTP-125.001 These procedures reflect changes to the S/G Water Level Control Rev.O Test of the FRV response and FW Pump Speed Centrol Test of the PTP-125.002 FW Pump Speed Control portion of the SGWLC system following S/G Rev.O replacement. These changes do not involve any unreviewed safety questions.
PTP-125.003 These procedures provide guidelines for performing Turbine Rev. 0,0-A Generator step load changes of 10% and 25%. These changes were PTP-125.004 made to determine if control system setpoint changes were required to Rev.O improve plant performance following S/G replacement. These changes do not involve any unreviewed safety questions.
PTP-280.003 This change to PTP-280.003, FW Flow and S/G Moisture Carryover Rev.1 Lithium Tracer Test, combined the performance of FW Flow and C/G i
moisture carryover testing. These tests were required as a result of I
Enclosure to Documsnt Control D:sk Lettgr ANN 800 RC-96-0286 Page 13 of 14 the S/G replacement. These changes do not involve any unreviewed safety questions.
SAP-401 These changes to the Secondary Water Chemistry Program and the Rev. 7-A Feedwater and Condensate Chemistry Control procedure removes the CP-615 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> time requirement to isolate or repair tube condenser leaks.
Rev.13-C Improvements in the monitoring and treatment methods has made this commitment obsolete. These changes do not involve any unroviewed safety questions.
SAP-605 This change to SAP-605, Application of CHAMPS, incorporates Rev.5 responsibility changes relating to the administrative controls over the CHAMPS database. This change does not involve any unreviewed safety questions.
SOP-206 This change to SOP-206, Main and Auxiliary Condenser Air Removal Rev. 9-G System, adds a listing of valves and disconnect switches for installation of the Vacuum Pump seal water NH3 Removal System.
This change does not involve any unreviewed safety questions.
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ABBREVIATIONS and ACRONYMS ASME American Society of Mechanical Engineers BAR Bypass Authorization Request BTP Branch Technical Position CCW Component Cooling Water CHAMPS Computerized History and Maintenance Planning System CP Chemistry Proce,, dure CVCS Chemical and Volume Control System DHEC Department of Health and Environmental Controls EHC Electro-hydraulic Control EOP Emergency Operating Procedure FPER Fire Protection Evaluation Report FPP Fire Protection Procedure FRV Feedwater Regulation Valve FSAR Final Safety Analysis Report FW Feedwater FWlV Feedwater Isolation Valve IPCS Integrated Plant Computer System LOCA Loss of Coolant Accident MCN Modification Change Notice MMSI Mechanical Maintenance Special Instruction MRF Modification Request Form Mwt Megawatts (thermal)
NCN Non-Conformance Notice NH3 Ammonia NTC Nuclear Training Center PSP Physical Security Plan PTP Performance Test Procedure RBCU Reactor Building Cooling Unit RB Reactor Buildng RCCA Rod Control Cluster Assembly RCDT Reactor Coolant Drain Tank RCP Reactor Coolant Pump RCS Reactor Coolant System RFO Refueling Outage RHR Residual Heat Removal RN Revision Notice RSG Replacement Steam Generator SAP Station Administrative Procedure S/G Steam Generator SGWLC Steam Generator Water Level Control SI Safety injection SOP System Operating Procedure SSPS Solid State Protection System STP Surveillance Test Procedure VCT Volume Centrol Tank
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