ML20077M282
| ML20077M282 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 08/06/1991 |
| From: | Skolds J SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9108130267 | |
| Download: ML20077M282 (16) | |
Text
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outh Caronna Eteetnc & Gas Company Jotn a
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Jenkmswho EC NOM tuclear Operanons (603J 345 4040 SCE&G AUG 0 61991
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Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. L' 20055 Gentlemen:
1
Subject:
VIRGIL C ' SUMMER NUCLEAR STATION DOCKET NO. 50/395 l
OPCRATING LICENSE NO. NPF-12 1
ANNUAL 10CFR50.59(b)(2) REPORT Enclosed is the eighth Annual Peport submitted pursuant to 10CFR50.59 for Virgil C. Summer Nuclear Station. This report includes a brief description of non-conformances.-procedure changes, and modifications made to the i
facility as described in the Safety Analysis Report, as well as a summary of the safety evaluations. The non-conformance notices, identified by the Non-Conformance Notice number (NCN), the procedure changes, identified by the procedure number, and the modifications, identified by the Modification Request Form (MRF) where applicable, were completed prior to August 6, 1990, which ended the eighth year following the issuance of the Facility Operating License.
Should you have any questions concerning this issue, please call Mr. Manuel W. Gutierrez at (803) 345-4392 at your conven{ence.
Very,truly yours/
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MWG:JLS: led Enclosure c:-
- 0. W. Dixon Jr R. R. Mahan R. J. White S. D. Ebneter G. F. Wunder General Managers C. A. Price J. B. Knotts Jr L. R. Watson NSRC RTS (ANN 800)
File (818.02-8) i 4
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ENCLOSURE TO LETTER TO DOCUMENT CONTROL DESK ANNUAL 10CFR50.59 REPORT
l 1-l ElGHTH ANNUAL 10CFR50.59 REPORT VIRG H C. SUMMER NUCLEAR STATION MRf-20793 This modification removed a control twitch that allowed the Liquid Waste to Penstock discharge isolation valves to be operated together.
Individual valve control will prevent the potential for an unmonitored release.
This modification does not involve an unreviewed safety question.
MRF-20913 This modification removed the cutoclosure interlock on the RHR loop suction / isolation valves and provides an alarm to alert the operator that a suction valve is not fully closed when the reactor coolant pressure is above the alarm setpoint. This modification does not involve an unreviewed safety question.
MRF-21007 This modification increased the Service Water and Component Cooling Water system rating pressure to account for the Service Water pump motors being locked in their high speed setting. The increases in pressure stresses were evaluated and found to be within code acceptable values.
This modification does not involve an unreviewed safety question.
MRF-21075 This modification installed a liVAC unit in the Control Building EL 425, where HP personnel have offices. This modification does not involve an unreviewed safety question.
MRF-21081 This modification removed the remote monitoring system that was used to monitor routine atmospheric releases and significant unplanned releases. This function is performed by environmental monitoring teams in agreement with RG 1.97.
This modification does not involve an unreviewed safety question.
MRF-21098 This modification made permanent the temporary installation of piping and gauge for vent valve XVT-11019-EF on the turbine driven emergency feedwater pump.
The intent of the installed piping and gauge is to support the testing of the pump.
The installed piping and gauge are seis.nically supported. This modification does not involve an unrevi6wed safety question.
MRF-21223 This modification replaced the motor driven Emergency Feedwater pump discharge check valves with new dual seat, fast closure, and reduced leakage characteristic check valves. The replacement valves provide better performance and enhance the system response. Thise modificatior, does not involve an unreviewed safety question.
Page 1 of 14
MRF-21240 This modification is a revision to drawing 0-302-103 to reflect _ installation of flow prevention blanks in the kidney loop piping that interfaces with the condenser.
The modification of the kidney loop does not impact the safety of the plant. This modification does not involve an unreviewed safety question.
MRF-21256 This modification upgraded portions of the waste gas processing piping which may have the potential of carrying combustible gas mixture (from non-nuclear safety to quality related classification) including the provision of teismic design to maintain position integrity in the event of an earthquake. This modification does not involve an unreviewed safety question.
MRF-21280 This modification installed instruments, controls, valves, and revised the logic of valves and pumps in the condensate system. This modification was intended to provide efficient system operation during startup and trip recovery. This modification does not involve an unreviewed safety question.
MRF-21309 lhis modification replaced the steam generator blowdown containment isolation valves with disc gate valves and added a fill system to keep the downstream piping filled upon containment isolation. This modification does not involve an unreviewed safety question.
MRF-21315 This modification removed the R10 bypass manifold, RTDs, valves, piping, and supports associated with the RlD bypass system, and replaced the RTDs with thermowell mounted, fast response dual element RTDs, installed directly into the reactor coolant cold and hot leg.
This modification does not involve an unreviewed safety question.
MRf-21325 This change was made to correct and add information to FSAR figures 9.2-4. 9.3-4, 9.4-32, and 10.4-13.
The revision to these figures does not involve an unreviewed safety question.
MRF-21332 This modification revised drawing E-302-693, FSAR Figure 6.3-1, to indicate the appropriate stroke time for certain valves in the Emergency Core Cooling System.
This modification does not involve an unreviewed safety question.
MRF-21337 This modification revised the protected area fence around the tefueling water storage tank.oit area. This modification also provided easier accast to the refueling water storage tank upper recirculation valve, lhis modification does not involve an unreviewed safety question.
Page 2 of 14
MRF-21349 This modification added a voltage regulator and associated controls between the 115KV offsite power supply transformer and 7.2 KV class 1E bus; the controls allow isolation and bypass of the voltage regulator.
The voltage regulator is intended to adjust the voltage to the class 1E bus whenever there is a perturbation in the 115KV, thus precluding any effect on the safety bus.
This modification does not involve an unreviewed safety question.
MRF-21250 This modification provided sanitary services and utilities to the new office building erected outside the i
plant protected security area. This modification does not involve an unreviewed safety question.
MRF-21400A This change corrected FSAR Figure 9.1-3, (drawing D-302-651) to reflect the design temperature for the high density spent fuel racks installed per MRF-20337, and FSARFigure9.2-24(dravring 0-302-791) to reflect that 1
the alarms on the reactor water make-up level transmitters LT-7603 and LT-7604 are activated by individual comparators. This change does not involve an unreviewed safety question.
MRF-21401 This modification replaced fourteen bellows seal valves in the post accident sampling system. The replacement was necessary due to seat leakage experienced on certain bellows seal valves in this system. The replacement valves were installed in non-safety class piping, and do not affect any safety related fanction or system. This modification does not involve an unreviewed safety question.
MRF-21467 This modification revised drawing 0-912-144 FSAR Figure 9.4-3, to conform with the Design Basis Document. This modification does not involve an unreviewed safety question.
MRF-21479 This modification replaced the RHR sump and reactor building level transmitters with a common transmitter which does not use a dry reference leg. The common transmitter monitors reactor building level for flood protection and RHR sump level for minimum NPSH. This modification does not involve an unreviewed safety question.
MRF-21485 This modification revised drawings 0-912-136, FSAR Figure 9.4-2, and D-912-014, FSAR Figure 9.4-29, to conform with the Design Basis Document. This modification does not involve an unreviewed safety question.
MRF-21509 This modification installed level instrumentation on RCS hot leg, loops A and C.
This function is used only during mid-loop operation and is disconr)ected during normal plant operation. This modification was implemented to meet the requirements of Generic Letter Page 3 of 14
88-17. This modification does not involve an unreviewed safety question.
MRF-21517 This modification documents the change to Figure 9.2-4 reflecting the use of manual valves in the Component Cooling Water System in the outlet side of the RHR heat exchangers and locking of the valves in their normal position. This modification does not involve an unreviewed safety question.
MRf-21540 This change was made to correct the directional arrows showing the flow pattern on the condensate system flow diagram. This change does not involve an unreviewed safety question.
MRF-21562 This modification restressed the vertical tendons of the Reactor Building to preclude further relaxation losses over the plant life. The tendon surveillance program indicated that the vertical tendon forces were approaching minimum technical specification values. This modification does not involve an unreviewed safety question.
MRF-21595 This modification replaced the engineered safety features batteries to meet a four hour duty cycle in support of station blackout consideration, per Regulatory Guide 1.155 " Station Blackout." This modification does not involve an unreviewed safety question.
MRF 21635 This modification added piping to drain condensate from the pressurizer safety valves and eliminate the water seal on the valve inlet, thus eliminating the potential for inadvertent depressurization due to set point decrease. This modification does not involve an unreviewed safety question.
MRF-21726 This modification corrected the floor response spectra for the Service Water Pumphouse.
The corrected values of acceleration and displacement are lower than those used in the original design; therefore, the original design is more conservative.
This modification does not involve an unreviewed safety question.
MRF-21786 This modification replaced the fuel transfer tube gate valve with an autoclave type gate valve which meets or exceeds the original design requirements. This modification does not involve an unreviewed safety question.
MRF-33284 lhis modification repaireJ the north and south vent connections of the Refueling Water Storage Tank (RWST),
thereby returning the connections to their original configuration. Additionally, the south vent piping from the RWST connection to the auxiliary building charcoal exhaust duct was upgraded to quality related Page 4 of 14
requirements. This modification does not involve an unreviewed safety question.
MRF-32995 This modification installed blind flanges with a one half inch hole at the end of each drain pipe serving the HVAC chiller rooms. The blind flange and orifice restricts a possible steam path if a pipe break were to occur in the intermediate building. The equipment in the chiller rooms is designed for a mild environment.
This modification does not involve an unreviewed safety question.
MRF-33401 This modification removed two local maximum pressure indicators from the reactor coolant hot legs. These indicators were initially intended to provide local reactor coolant pressure during cold shutdown.
The indicators are no longer needed due to the availability j
of accurate indication and recording in the Control Room.
This change does not involve an unreviewed safety
- question, i
i I
1 4
Page 5 of 14
FSAR Rev.
This change to FSAR Figure 10.4-8 (drawing D-302-101)
Notice 794 corrects the tag number of the pretsure transmitter on Condensate Pump "C" Discharge from PT 304 to PT 3044.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Section 3.6 clarifies the design i
Notice 803 criteria used for plant design for protection against postulated piping failures in fluid systems outside containment, including evaluation of steam paths and the sealing of penetrations in the Auxiliary Building.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Figure 9.5-1 (drawing 0-302-231) i Notice 806 reflects the as-built flow configuration of the Water Treatment Building fire service sprinkler system. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Section 11.2.3.2 correctly describes Notice 807 how the common alarms on the waste processing panel are relayed to the Control Room. This change does not involve an unreviewed safety question.
FSAR Rev.
These changes to FSAR Chapters 13 and 17 reflect recent Notices 808 organization changes. These changes were administrative 818 & 819 in nature without any physical changes to the plant configuration. These changes do not involve an unreviewed safety question.
1 FSAR Rev.
This change to FSAR Table 5.2-7 Section 7.7.1.5, and Notice 809 FSAR Figure 7.7-4 removes several heater circuits from the pressurizer operating backup heaters to allow the control heaters to control pressurizer pressure. This mode of operation provides stable pressure control without using the spray control. This change does not involve an unreviewed safety question.
FPER Rev.
This change to Drawing E-023-018, and Sections 4.5.22.1 Notice 810 and 4.5.23.1 of the FPER reflect as-built condition of fire areas. This change does not involve an unreviewed sifety question.
FSAR Rev.
This change updates' Chapter 4 of the FSAR to reflect-the Notice 812 use of VANTAGE b fuel, beginning with Cycle 5.
Changes to '.he mechanical, nuclear, thermal, and hydraulic design bases are incorporated consistent with approved amendieents 74 and 75 to the' technical specifications.
This change does not involve an unreviewed safety question.
Page 6 of 14
FSAR Rev.
This change to FSAR Figure 9.3 4 (drawing 0-302-771)
+
Notice 813 indicates the correct operation of certain solenoid valves used to operate the containment isolation valves in the containment air sampling system. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Figure 9.4-3 (drawing 0-912-144)
Notice 816 reflects the as-built condition of the Control Room pressurization fan, dampers, and associated ducting.
This change does not involve an unreviewed safety j
question.
FSAR Rev.
This change to FSAR Section 12.3.3.1 reflects how Notice 821 personnel exposure TL0s are processed quarterly instead of monthly. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Figures 10.3-2 and 10.4-8 (drawings Notice 823 D-302-012 and D-302-101, respectively) reflects the as-built condition of the main steam system (non-safety related portion) and the condensate system.
This change does not involve an unreviewed safety question.
FSAR Rev.
ThischangetoFSARFigure9.4-20(drawing 0-912-151)
Notice 825 corrects a fire damper ta5...;mber in the Service Building. This change does not involved an unreviewed safety question.
FSAR Rev.
This change to FSAR Figures 9.3-1, 9.3-2, 9.3-3, and Notice 827 9.3-3a (drawings D-302-241, D-302-271, D-302-273, and 0-302-274 respectively) reflects the quality related upgrade of instrument air compressors, dryers, and filters that supply air to nuclear safety related or quality related components. This change does not involve an unreviewed safety question.
2 FSAR Rev.
This change to '
Section 3.9.3.8 removes the 1.5 Notice 830 factor applied OBE loadings to account for hardware and erection tolerances in the original design of pipe supports. This factor is no longer needed since as-built conditions were incorporated in the final analysis. This change does not involve an unreviewed safety question.
FPER Rev.
This change makes editorial changes and incorporates Notice 831 as-built condHions in FPER Sections 4.5, 4.6, and Drawings E-023-007. E-023-010, and E-023-019. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Section 5.7 corrects the ASME code.
Notice 833 SectionXI,yearreferenced(1974editionthroughsummer 1975 Addenda) for inservice inspection of ECC5 components as required by 10CFR50.55a(b)(iv).
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Section 3.9.3 revises the basis for Page 7 of 14
4 Notice 834 useoftheanchorboltstiffnessexpression(AE/2.5L).
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 9.3-14 (drawing D-302-352)
Notice 835 reflects as-built conditions of the Non-Nuclear Plant Drains. This change does not involve i unreviewed safety question.
FSAR Rev.
This change reflects analyses performed to asses the Notice 839 acceptability of having steam leakage to the condenser of up to 5% of nominal steam flow following closure of the main steam isolation valves. The results indicate that the impact on the non-LOCA satety analysis is negligible.
This enange does not involve on unreviewed safety question.
FSAR Rev.
This editorial change corrects a panel designation on Notice 841 FSAR Figure 8.3-4 (draw
.g E-206-061, sheet 1).
This change does not involve an unreviewed safety question.
FSAR Rev.
These changes incorporate the result of updated Notice 844 calculations on the post accident spray and ECCS sump pH values.
The environmental qualifications were also updated to reflect new zone maps and environmental conditions, as a result of the change in concentration of NaOH and H3003. The revised pH calculation yielded a reduction in the pH values previously reported in the FSAR for the spray solution recirculated within the containment.
These changes do not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Section 8.3.2.1.3 clarifies the text Notice 846 related to the operability of the class 1E batteries with a reduction of up to two cells on either battery. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR figure 9.3-16, sheet 3 (drawing Notice 847 E-302-675) reflects the replacement of twelve Rockwell Edwards valves in the CVC System, at the seal water injection filters, with Yarway valves.
The replacement Yarway valves were considered equal to or better than the replaced valves. This change de*s not involve an unreviewed safety question.
FSAR Rev.
ThischangetoFSARFigure8.3-1(drawingE-206-062, Notice 853 sheet 1) reflects the as-built condition of the power supply to the reactor core cooling monitor which is provided through an isolation fuse.
This change does not involve an unreviewed safety question.
Page 8 of 14 lu
FSAR Rev.
This change to FSAR figures 8.3-1 and 8.3-2 (drawing Notice 854 E-206-062, sheets 1 and 2 respectively) reflects as-i built configuration of interlocks installed on 120 volt l
AC inverter power supplied panels. This change does not involve an unreviewed safety question.
FSAR Rev.
This editorial change removed FSAR pages 15.4-47, Notice 855 15.4-48, 15.4-48a. These pages should have been removed when amendment 4 was incorporated. This change does not involve an unreviewed safety question.
FPER Rev.
This. change to FPER drawings and text reflects the as-I Notice 857 built piant configuration. This change does not involve an unreviewed safety question.
FSAR Rev.
Notice 858.
This change to FSAR Figure 8.2-4 (drawing E-206-012) provides clarification of the safety classification of protective relays in the diesel generator circuitry.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change ta FSAR Figures 7.5-3, 8G-3, and 8G-4 Notice 859 (drawingt E-804-662. E-224-532 sheet 3 E-224-532 sheet 4. respectively) upgrades the service water supply valves to the Reactor Building cooling units to active status. This change does not involve an unreviewed safety question.
FSAR Rev.
This change reflects current environmental qualification Notice 861 program and regulatory commitments. FSAR Sections 3.11 and Appendix 3A were rewrittent Sections 6.2.1.5 and 12A.5 were revised to reflect cross reference to applicable subsection changes in Section 3.11.
This change does not involve an unreviewed safety question.
FPER Rev.
This change incorporates revised fire loading Notice 862 calculations reflecting additional input from mechanical equipment and transient combustibles. This change does not involve an unreviewed safety question.
FSAR Rev.
This editorial change to FSAR Figure 10.4-10, drawing Notice 863 E-302-081, changed the designation of flow controllers.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change added new FSAR Section 3.9.2.8.3 to clarify Notice 864 the design criteria for designing pipe support components outside the jurisdiction of the ASME Code, Section 111 Subsection NF. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Figure 8.3-4, drawing E-206-061 Notice 865 sheet 1, corrects equipment and breaker identification.
This change does not involve an unreviewed safety question.
Page 9 of 14
FSAR Rev.
This change to FSAR Figure 10.4-13 drawing 0-302-781, Notice 866 added the steam generator wet layup purifier skid. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Figure 9.1-3, drawing 0-302-651, Notice 868 indicates that valve 6726-SF is locked closed instead of normally closed to preclude dilution in the spent fuel pool.. This change does not involve an unreviewed safety question.
l FSAR Rev.
This change to FSAR Section 10.3.5 reflects the use of Notice 872 boric acid and morpholine to maintain secondary side water chemistry. The use of these two chemicals will reduce corrosion, intergranular attack, and control pH.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Section 11.5 reflects actual Notice 873 operation of the Solid Radwaste System. The process control program reflects current methodology and equipment used to comply with regulatory requirements.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Sections 15.3.1 and 15.4.1 reflects Notice 875 modifications to the ECCS evaluation model for small and large break LOCA. The calculations performed show that the peak clad temperature is still be'ow 2200 F.
This change does not involve an unreviewed safety question.
FSAR Rev.
This change revised the stroke time of the Main Steam Notice 877 Isolation Valves from 5 seconds to 7 seconds from actuation to full closure. The 7 second stroke time is bounded by the reponse time required for a low steam line pressure. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Figures 8.3-Oh and 8.3-01 (drawings Notice 879-C-203-005 and C-203-006, respectively) reflects as-built conditions of the diesel generator shutdown control logic diagram. This change does not involve an unreviewed safety question.
FSAR Rev.
This change to FSAR Tables 6.2-54 and 6.3-1 reficcts the Notice 890 correct stroke time of the listed valves. This change does not involve an unreviewed safety question.
I Page 10 of 14
NCN-3322 The creal Nitrogen supply valve to the Safety injection Accu:N1ators.tas declared inoperable due to mechanical failure. Technical Specifications require this valve to remain closed while it is inoperable. A temporary mechanical jumper was installed between the accumulator fill header drain and the Nitrogen header vent to allow pressurization of the accumulators using the normal liquid fili piping and valves.
Installation of the mechanical jumper using high quality commercial material, capable of withstanding full Nitrogen pressure and routed below any safety related equipment, ensures that the accident analysis assumptions can be met.
The connecting points of the jumper are on non-safety related portions of the system. The supply was reworked by polishing the plug and the seat. This NCN in its disposition do not involve an unreviewed safety question.
NCN-3383 The Service Water Pump House Cooling Coils are not seismically designed. Their failure during a seismic event could introduce significant amounts of water into the ductwork, potentially failing the ductwork, and cause flooding in the pump house. The cooling coil isolat bn valves are to be maintained in the closed position until implementation of MRF-33383 is completed.
Isolation of the cooling water supply will preclude potential flooding. This isolation condition is acceptable as an interim solution, since temperature limits for components within the boundary of service by this cooling units are for long term equipment qualification.
In addition, if the temperature increases towards the equipment qualification limits, supplemental actions can be taken until the MRF is implemented. This NCN and its disposition do not involve an unreviewed safety question.
NCN-2965 Blackness testing of region 1 and 2 of spent fuel storage racks revealed that 21 cells out of 52 measured have possible gaps ranging in size from 0.5" to 1.0" in the boraflex absorber material. Based on Keff =.95, there is sufficient margin due to burnup accumJ1ated on each of the 42 fuel assemblies for the present observed gap. Additionally, a 3 out of 4 checkerboard loading scheme should be used in region 1 and 2 racks.
Fuel assemblies movement in region 3 was performed to minimize any further degradation due to irradiation induced shrinkage. Additional fuel movements associated with off-loadi*,g the cycle 4 core into region 1 of the spent fuel racks and loading of fresh region 7 into region 1--prior to loading the core for cycle 5--was also performed.
Reactivity analysis performed show that adequate margin exists after allowing for 1% margin due to gaps in the boraflex.
This NCN and its disposition do not involve an unreviewed safety question.
Page 11 of 14
=.
NCN-3348 During walkdowns for a streamline break steam intrusion evaluation, a missing clapper valve for a floor equipment drain was discovered. There are 2 floor drains serving the HVAC Chilled Water System equipment rooms in the Intermediate l
Building. These drain lines represent potential pathways for steam intrusion causing a harsh environment in a previously designated mild area. This NCN provides the disposition for both drain lines. For the short term, the drain without a clapper valve had a blank flange with a 1/4" drain hole installed. The clapper valve in the other drain line was braced shut and then opened daily for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> to allow draining. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> allowance was deemed acceptable for breaching the pressure barrier. The drain lines were subsequently fixed by adding blind flanges with 1/2" holes to allow draining. The 1/2" holes are sufficient to allow drainage but limit steam intrusion through the line to an acceptable level. The potential for flooding the chiller rooms via the drain lines was also evaluated. The maximum flood level in the rooms will not impact safety related equipment in the room. This NCN and its disposition do not involve an unreviewed safety question.
NCN-3522 The nuts on the discharge flanged connection to Component Cool uq System pump XPP-1B-CC were not purchased for ASME Class I H application. This condition was determined to acceptable based on a strength evaluation of the nuts in this application. However, to provide compliance with the ASME Code, the nuts will be replaced with Class III nuts the next outage.- This NCN and its disposition do not involve an unreviewed safety qvestion.
NCN-3528 This NCN stated r. hat the nuts on the inlet flanged connection to safety relief valve XVR-03144B-SW of the Service Water System were not purchesed for this ASME Class III application.
Use of these nuts was evaluateo as acceptable based on the low strength requirements for this connection. However, to provide complete compliance with the ASME Code, these valves were required to be replaced at the next refueling outage.
This NCN and its disposition do not involve an unreviewed safety question.
NCN-3534 Maintenance work request (MWR) 10759-0002 was written to install safety related piping the for service water pump house
-cooling coil modification. The bolts and nuts that were issued were safety related but not purchased for an ASME Code application. An engineering evaluation was done to justify operating under these conditions until plant condi'. ions allowed these nuts and bolts to be reworked.
Replacement of these fasteners with approved ASME Class III fasteners was completed. This NCN and its disposition do not involve an unreviewed safety question.
Page 12 of 14
i NCN-3538 The 0.5 inch studs and nuts on the flanged connection for pump suction of the Diesel Generator fuel oil day tank XTK-0020B were not purchased for ASME Code Class 3 application.
The studs and nuts were determined to be acceptable for interim use based on the studs conforming to ASME requirements and a strength evaluation of the flanged connection. However, to provide complete compliance with the Code, the fasteners will be replaced with approved ASME Class 3 fasteners during the next outage.
This NCN and its disposition do not involve an unreviewed safety question.
NCN-3199 The present DC ground detection system applies a ground on the battery to detect a voltage imbalance for indication of ground. Ground detection will now be provided using a high impedance voltmeter instead of lights, and ground leakage will be measured with a null-ammeter. This method will provide a better. indication of grounds in the ground detection circuit.
This NCN and its dispositions do not involve an unreviewed safety question.
NCN-3536 NCH 3536 identified studs and nuts on the flange connection on pump suction of diesel generator fuel oil day tank XTK-0020A and nuts on manway cover of fuel oil storage tank XTK-0053A as not being purchased for ASME Code Class 3 application.
The strength evaluation of flange connections demonstrates that the design loads and stress levels in the nuts are low.
Therefore, the installed nuts and studs are acceptable as-is.
However, to provide completed compliance wtih the ASME Code, the nuts will be replaced with ASME AS194 grade 2H nuts at the next outage. This NCH and its disposition do not involve an unreviewed safety question.
{l.
Page 13 of 14
PROCEDURE CHANGE SOP-311 Changed to provide backup power source while batteries were being replaced.
This was a temporary, restricted revision to allow the swing battery charger to be connected to a DC bus in addition to the normal charger, while the battery was being replaced. This provided backup power in case a charger or AC power to a charger was lost.
The procedure revision was applicable only in modes 5 and 6 during refueling 5, while the batteries were replaced. Only one train of DC power is required operable during modes 5 and 6. and a complete train of equipment can be disabled for maintenance as long as the other train is operable. The procedure ensured that the AC and DC -power for the operable train remained separated from the 'emporary power supplies for the train in which the batteries were being replaced. This procedure change did not involve an unreviewed safety question.
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