ML20198B087
| ML20198B087 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 12/11/1998 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20198B058 | List: |
| References | |
| NUDOCS 9812180053 | |
| Download: ML20198B087 (129) | |
Text
{{#Wiki_filter:_ _ _ . . _ . . _. ._ . _ _ --_ _ _ . . _ . . _ . . ._ _ l 1 Docket No. 50-336 I B17587 1 1 l 1 Attachment 2 '. Millstone Nuclear Power Station, Unit No. 2 l Addendum 2 - December 11,1998 to Millstone Nuclear Power Station Unit No. 2 Annual Report dated July 1,1998 December 1998 9812190053 901210 PDR K ADOCK 05000336 pg
i' Docket No. 50-336 B17587 INTRODUCTION None of the plant design changes described herein constitute, nor constituted, an unreviewed safety question per the criteria of 10CFR50.59. PL. ANT DESIGN CHANGES DCR Number Title (FSAR Sections, Tables, and Fiaures Affected) M2-97048 Safety injection (SI) Test Line Relief Valve 2-SI-466 Setpoint Change (5.2.8; processed with FSARCR 98-MP2-13) M2-98004 Reactor Building Closed Cooling Water (RBCCW) Pipe Support Modifications for GL 96-06 Water Hammer Loads and Temperature Changes (9.4.1, 9.4.3, 9.4.5; processed with FSARCR 98-MP2-4) M2-98027 Additional Trisodium Phosphate (TSP) for Containmerit (6.2.2, 6.2.3, 6.2.4, T6.2-1; procesed with FSARCR 98-MP2-33) M2-98043 Volume Control Tank (VCT) High Pressure Alarm Setpoint Change (9.2.4; processed with FSARCR 98-MP2-105) : TRMCR Number Title (FSAR Sections, Tables, and Fiaures Affected) 98-2-12 Emergency Diesel Generator Fuel Oil Supply (8.3.2; processed with FSARCR 98-MP2-134) FSARCR Number Title (FSAR Sections, Tables, and Fiaures Affected) 98-MP2-69 Communication Systems (7.8.2, 7.8.3) 98-MP2-83 Design Procedures for Restraints and Barriers (5.2.6) ! 98-MP2 91 Regulating Systems, Turbine Generator Control System (7.4.6) 98-MP2-95 Water Treatment Systems (9.12.2, 9.12.4, T9.12-1) , 98 MP2-110 Turbine Building Closed Cooling Water (TBCCW) System (9.7.3)
- 98-MP2-117 Major Components of the Condensate and Feedwater System j (T10.4-1) 1
l Docket No. 50-336 B17587 l 98-MP2-118 Steam and Power Conversion System (8.4.2, 8.4.4,10.1, l 10.4.5) l l 98-MP2-129 Auxiliary Systems, Compressed Air, Compressed Air Systems i ! (1.2.10, 9.11.1, 9.11.2, 9.11.3, 9.11.4, T9.11-1) 98-MP2-132 Decrease in Heat Removal by the Secondary System (14.2.1, 14.2.2,14.2.4.14.2.6, T14.2.1, T14.2.2 , T14.2.4 , T14.2.7 , F14.2.1, F14.2.4-) 4 l 98-MP2-133 Shutdown Cooling Heat Exchanger (SDC HX) Data (T6.3-3) l 98-MP2-135 Plant Ventilation Systems, Vital Switchgear (9.9.15) 98-MP2-140 Principle Parameters of the Safety injection System (T6.3-2, F6.3-2) 98-MP2-143 Condensate and Feedwater Systems (10.4.5) 98-MP2-147 Reactor Building Closed Cooling Water (RBCCW) System, Tests and inspection (9.4.4) , 4 98-MP2-149 Reactivity and Power Distribution Anomalies (14.4.1,14.4.2, 14.4.3,14.4.8, T14.4.1, T14.4.2 , T14.4.3-1, T14.4.3.1-T14.4.3.5 , T14.4.4 , T14.4.8 , F14.4.1, F14.4.3.1, F14.4.8-9) 98-MP2-152 Decrease in Reactor Coolant System Flow (14.3.1,14.3.3, T14.3.1, T14.3.3 , F14.3.1, F14.3.3-7) 98-MP2-153 Control Systems,4160 Volt and 6900 Volt Systems (7.4.2, 7.5.3, 8.2.1, T7.4-1, F7.4-8) 98-MP3-155 Communication Systems (7.8.2, 7.8.3) i 98-MP3-157 Diesel Generator Ventilation Systems (9.9.11) l 98-MP3159 Turbine Building Ventilation System (9.9.12) l
- 98-MP2-160 Radioactive Waste Processing System (11.1.1) i 2
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r ! DCR Number Title M2-97048 Safety injection (SI) Test Line Relief Valve 2-SI-466 Setpoint Change l Descriotion of Change This DCR changed the set pressure of Si recirculation line relief valve 2-St-466 from 560 psig to 415 psig. This DCN also revised the design pressure of the Si tank fill piping and Si recirculation header from 250 psig to 495 psig. The piping design pressure was raised to maximize the pressure available for filling the SI tanks which nomially are pressurized between 200 and 250 psig. The new piping design pressure is determined by and bounds the lowest pressure rated piping component in the affected piping. The new relief valve set pressure accounts for elevation variations and pressure drop due to flow through the Si tank system piping, and back pressure of the reactor coolant system quench tank to which the relief valve discharges. Reason for Chance The relief valve 2-SI-466 was set to lin at 560 psig. This set pressure was in violation of the piping design I code because it is above the present piping design pressure of 250 psig. The information has been updated in FSAR Section 5.2. Safety Evaluation Summary The safety evaluation addressed the effect of resetting relief valve 2-SI-466 from 560 to 415 psig and raising the Si tank fill and SI recirculation header design pressure from 250 to 495 psig on the safety function of the SI systems (high pressure SI, low pressure SI, Si tank) and containment isolation system (CIS). It is determined that these changes do not effect the capability of the SI systems and CIS to mitigate the design basis events described in the FSAR Section 14 Safety Analysis and concluded that this modification is safe and does not constitute an Unreviewed Safety Question. 1 i
DCR Number Ilde M2-98004 Reactor Building Closed Cooling Water (RBCCW) H Pipe Support Modifications for GL 96-06 Water llammer Loads and Temperature Changes Descriotion of Change l This DCR addressed a potential for generation of hydrodynam.ic or water hammer loads in the RBCCW system piping, resulting from containment air recirculation (CAR) / control element dr.ve mechanism (CEDM) cooler operation, during either a loss of coolant accident (LOCA) or a trair steam line break ' ( MSLB) concurrent with loss-of-normel power (LNp), and the evaluation of temperature effects in the RBCCW system resulting from changes in peak RBCCW temperature transients after a LOCA / MSLB. Reason for Change This change was made in response to NIC GL-96-06 and the review of FSAR section 9.4. Two issues were addressed and the first was that during a postulated design-basis LOCA / MSLB with a concurrent LNP , the RBCCW pumps and the CAR / CEDM cooler unit fans will temporarily lose power. The RBCCW fiow will stop immediately, while the CAR cooler unit fans will continue to coastdown for some interval of time. Under these conditions the stagnant RBCCW in tSe CAR / CEDM coolers may boil and create a steam volume in the RBCCW system, and when the RBCCW pumps restart the pumped liquid may rapidly condense the steam leading to water hammer loads on the CAR / CEDM coolers and associated RBCCW system piping and supports. The aforementioned scenario was not analyzed during plant construction. Based upon the calculated water hammer loads and the effects of temperature changes the following changes were made to satisfy the newly identified GL 96-06 water hammer loads. A total of four (4) pipe supports were modified and one new support was added to the RBCCW system. The second issue addressed the temperature changes in the RBCCW system due to changes in the peak RBCCW temperature transients resulting from a LOCA / MSLB which considers CAR cooler unit performance based on revised fouling factors. This resulted in a calculated peak RBCCW system temperature of approximately 147'F at the outlet of the RBCCW heat exchangers considering zero fouling in the CAR cooler units. t Safety Evaluation Summarv - The modifications addressed the NRC GL-96-06 water hammer issue and higher RBCCW temperatures. The structural qualifications of piping and supports for the newly identified LOCA-induced water hammer loads were performed using the same code allowable as the original design basis criteria and the pipe supports were re-evaluated to qualify them for the revised loads. Since the pipe stresses and the allowable l support loads were found to be within the design basis criteria, the pressure boundary integrity of the RBCCW system is not decreased. Also, since the piping and support loads meet all previous code l requirements, and the pipe stress calculations show the stresses to be within the code allowable, the
- l. reliability of the RBCCW system has not been decreased. In addition CAR and CEDM unit integrity were i evaluated to determine stresses within components of the cooler units based on calculated pressures.
Therefore, this change is safe and does not constitute an Unreviewed Safety Question. l t I
DCR Number Title l M2-98027 Additional Trisodium Phosphate (TSP) for Containment Descriotion of Change This DCR increased the minimum required volume of TSP as a result of a new calculation performed to support the current requirement to raise containment sump pil > 7.0 following a loss of coolant accident.
'eason for Change The results of a new calculation have determined that the volume of TSP which was required to be stored inside containment was not sufficient. The volume of TSP has been increased. The information has been updated in FSAR Section 6.2.
i Safety Evaluation Summary This change increased the TSP volume stored in containment and required by Technical Specifications (TS) and does not result in a reduction in the margin of safety as defined in the Bases for the TS. Therefore, this change is safe and does not constitute an Unreviewed Safety Question.
l i l DCR Number Title l M2-98043 Volume Control Tank (VCT) liigh Pressure Alarm Setpoint Change l Dsscriotion of Charlgg This DCR reduced the VCT high pressure alarm setpoint to 35 psig. Also, VCT pressure instrument loop P-225 was recalibrated based on the results of a new calculation. This calculation determined that the proper head correction for this instrument loop should be 12.1 psig. I&C Calibration Procedure IC 2429A was updated to reflect the new head correction value. The head correction adjusts VCT pressure instrument loop P-225 to account for the height of water above VCT pressure transmitter PT 225. Nonnal VCT water level was assumed for the calculation. The current head correction value specified in IC 2429A is 14.5 psig. Reason for Chance The VCT high pressure alarm setpoint needed to be reduced to provide Operations indication that the VCT is above normal operating pressure prior to relief valve operation. Also, no uncertainty or setpoint calculations were located associated with VCT pressure instrument loop P-225 which required a calculation to be performed to provide the basis for the new high pressure alarm setpoint. The information has been updated in FSAR Section 9.2. Safety Evaluation Summary The installation and functional testing of the reduction of the VCT high pressure alarm setpoint including the recalibration of VCT pressure instrument loop P-225 to account for new head correction value does not create plant conditions which have not been previously analyzed nor create a malfunction or accident not previously considered in the analysis. The modifications will ensure the VCT high pressure alarm activates prior to the operation of relief valve 2-Cll-ll5. The modifications do not adversely affect any safety related equipment nor the failure modes associated with any equipment important to safety. This equipment is not safety related and not required for accident mitigation. Therefore, this change is safe and does not constitute an Unresiewed Safety Question. l i
I l c TRMCR Number Title l 98-2-12 Emergency Diesel Generator Fuel Oil Supply l l Descriotion of Change I This TRMCR added Section 6.0," Emergency Diesel Generator Fuel Oil Supply " to the Technical I Requirements (TR) section of the Technical Requirements Manual (TRM). The related FSAR change to - FSAR Section 8.3, revised the amount of the required volume of fuel oil in the underground diesel oil
' storage tank to reflect 19,563 total gallons corresponding to 17,195 useable gallons "
1 Reason for Change
- . This change removed inconsistencies between the FSAR and TRM regarding the amount of usable fuel l required to be stored in the underground tanks.
Safety Evaluation Summary The change revised the amount of the required volume of fuel oil in the underground diesel oil storage tank to reflect 19,563 total gallons corresponding to 17,195 useable gallons. The change does not affect the requirement of operating two emergency diesel generators (EDG) at full rated load for 24 hours, then one
' EDG for an additional 144 hours, for a total of 7 days following a loss of offsite power. The change does not modify the quality of the fuel nor the quality of the fuel oil that will be used aller depletion of the
. safety related fuel oil supply in the above ground tanks. Therefore, this change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number lith 98-MP2-69 Communication Systems l Descriotion of Change This change to FSAR Section 7.8 incorporated the synchronous optical network (SONET) communications equipment. This network is connected in flat ring connguration (Ober optic cable) and by multiplexing equipment. Telecommunication traffic placed on the SONET system is the samc type that would be placed on the microwave system. ]1eason for Changg The FSAR required updating to include this communications netwerk. This change also ensures the Unit 2 and 3 FSARs are in concert with respect to discussions of site wide communications systems. Safety Evaluation Summary This change concluded that there are no interactions between the SONET and existing communication systems, nor interactions between the SONET system and other plant systems that can affect existing malfunctions or accidents or create the possibility of new malfunctions or accidents. The system does not affect the probability or consequences of malfunctions ot existing communications equipment or other l plant equipment. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. l l l
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1 i i I ; FSARCR Number lille 98 MP2-83 Design Procedures for Restraints and Barriers
. Descrintion of Change This change to FSAR Section 5.2 updates the information to reflect that the design criteria for barriers are l ba>cd upon energy methods, utilizing ductility ratios of 10 and 5, respectively for steel and concrete in tension and flexure.
Reason for Change p .. j During the ongoing FSAR verification effort, it was identified that certain information in FSAR Section 5.2 l l regarding ductility ratios was not consistent with FSAR Section 6.l. Safety Evaluation Summary This change did not affect the analyses of record concerning the acceptability of barriers and restraints subject to pipe impact. The current licensing basis is documented in FSAR Section 6.1. No calculations were found that use the ductility ratio of 3 as an acceptance criteria. Ilowever, even if the ductility ratio of 3 were used, the conclusions of the previously issued calculations would not change, because the previous ductility ratio of 3 is more conservative than the current licensing basis of 10. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. I 1 1 4 i I f l l
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.1 l i l I i FSARCR Number Title 1
98-MP2-91 Regulating Systems, Turbine Generator Control System l t
' Descriotion of Channe l
This change to FSAR section 7.4 reflects the use of regulated 120 VAC in the turbine electronic logic and trip circuits, rather than vital station AC power. Also,it modified the information to indicate the startup ! sequence consists of a number of steps controlled from C07. FSAR Section 7.4 was also modified by !~ adding reference to an additional turbine trip signal, on loss of 125 VDC power when turbine speed is less than 1300 RPM. Reason for Change This change makes the FSAR description consistent with the as-built configuration. Safety Evaluation Summary This change retlected existing plant design and does not modify the Technical Specifications. There is no j increase in the probability of occurrence of previously evaluated accidents or malftmetions of equipment i important to safety. There is no increase in the consequences of previously evaluated accidents or malfunctions of equipment important to safety. There is no increase in the possibility of an accident or malfunction of a ditTerent type than previously evaluated. There is no decrease in the margin of safety. Therefore, this change is safe and does not constitute an Unreviewed Safety Question, i I i _ _--_ __ - - , . _ ~ v.--. . . ,
rr- 1 l-p. FSARCR Number Title 98 MP2-95 Water Treatment Systems Description of Change This change to FSAR Sections 9.12 and FSAR Table 9.12 1 resolved inconsistencies in pump ratings that previously appeared. l Reason for Change During the ongoing FSAR verification effort, inconsistencies were identified between the flow ratings for the primary water transfer pumps (PWTPs) and the capacity of these pumps identified in the FSAR. l Safel' valuation Summarv This change updated the capacity information presented in the FSAR for the PWTPs. The pumps do not provide or support any safety related functions, are not required to support any accident scenarios, and are not considered in the establishment of the margin of safety for any safety related component. This change does not affect any licensing or design bases. Therefore, this change is safe and does not constitute an
.Unreviewed Safety Question.
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i I FS ARCR Number Title 98-MP2-110 Turbine Building Closed Cooling Water (TBCCW) System i ! Descrintion of Change This change to FSAR Section 9.7 included a clarification and a deletion from the list of equipment cooled
- by the TBCCW system, l
Reason for Change During the ongoing FSAR verification effort it was determined that these changes were necessary to provide clarification of TBCCW cooling loads. Safety Evaluation Summary The changes clarified and updated the list of equipment directly cooled by the TBCCW system. The changes are administrative in nature and do not increase or decrease the loads on the TBCCW system. In addition. the changes do not affect the way the system is operated or affect any equipment that is part of the system. The TBCCW system is not safety related and is not comprised of environmentally qualified i equipment. The system is not credited as being available following a main steam line break (MSLB) or high energy line break in the turbine building or, a loss of coolant accident or MSLB inside containment. 1 The TBCCW System contains non-radioactive treated water and the failure of TBCCW piping would not i j result in the release of radioactive material within the unit or to the environment. Therefore, this change is i safe and does not constitute an Unreviewed Safety Question. l (, l l I' l l i 4
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FSARCR Number lilk 98 MP2-117 Major Components of the Condensate and Feedwater System Descriotion of Change This change to FSAR Table 10A-l added new feedwater piping material ( ASTM A 335 Grade P5 ) information to the major components of the condensata and feedwater system list. Reason for Change Portions of the feedwater piping system were replaced with a material that is less susceptible to erosion-corrosion. Therefore, the FSAR required updating to accurately describe the principle materials of the feedwater system. Safety Evaluation Summary r The change incorporated the material for replacement feedwater piping into the FSAR. The new material, ASTM A 335 Grade PS, is a ferritic steel with chromium and molybdenum for improved erosion-corrosion resistance. The replacement material has been demonstrated to meet the design requirements. There is no effect on previously analyzed accidents or malfunctions. There is no effect on the Technical Specifications. Therefore, this change is safe and does not constitute an Unreviewed Safety Question.
l I FSARCR Number Title 98-MP2-I l 8 Steam and Power Conversion System Descriotion of Change l This change to FSAR Sections 8.4,10.1 and 10.4 added a description of the condensate polishing facility
- (CPF) with respect to its condensate polishing function and clarified the condensate flow path with respect i to the CPF.
I Reason for Change - _ This change was determined necessary in order to correct the flow path description and provides a summary description of the facility. Safety Evaluation Summarv l His change provides a summary description of the Unit 2 CPF This non-safety related facility has been l appropriately designed and its existence and operation are otherwise well documented and have been well known since initial planning stages. This change makes no physical change to the facility. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. l - I L
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_ . _._ ._.. _ . . . .. - . _.._. - _ _ __. .. __-.. . _ _ ._ _ _ _-._..m._. . . . . ....m _ _ . _ ._ .. l1 i' FSARCR Number Title I. 98-MP2-129 Auxiliary Systems, Compressed Air Compressed Air Systems Descriotion of Change This change to FSAR Sections 1.2 and 9.11 and FSAR Table 9.11 1 clarified information regarding the operation of the compressed air systems and makes typographical corrections, it also deleted Engineering Design Basis (EDB) information. Reason for Change During the ongoing FSAR verification effort, it was identified that certain information regarding the
- l. compressed air systems required updating and clarification 1.
Safety Evaluation Summarv This change to the FSAR has been reviewed against Technical Specifications and approved plant operating I- procedures. The changes corrected, amplified, or updated information in the FSAR, and do not make any physical changes to the facility. Changes to EDB continue to be controlled by the appropriate plant procedures and processes. The changes have no impact on any malfunction or accident. Therefore, this
- change is safe and does not constitute an Unreviewed Safety Question.
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FSARCR Number Iitic 98 MP2-132 Decrease in IIcat Removal by the Secondary System l Description of Change 1 1 This change to FSAR Section 14.2, including Tables and Figures, implemented a major update, as a result ' of a reanalysis of events. In addition to these major changes several minor editorial changes w ere made. Reason for Change These changes are a result of the ongoing FSAR verification effort. The major Onding was that the original l inlet piping to the main steam isolation valves (MSIVs) was insuf6ciently sized to prevent overpressurization of the primary and secondary systems. In addition to the physical replacement of the l piping, the loss of external load and MSIV closure analyses were reanalyzed taking into account the new I inlet piping design. Safety Evaluation Summary These changes did not increase the probability of occurrence of a malfunction of equipment important to safety or of a previously evaluated accident. The possibility of a malfunction or accident of a different type has also not been increased as a result of this change. The consequences of either a malfunction of equipment or of an accident have not been increased. Therefore, this change is safe and does not constitute an Unreviewed Safety Question.
l l l FSARCR Numbet Title l 98-MP2-133 Shutdown Cooling Ileat Exchanger (SDC IIX) Data Descrintion of Change l This change to FSAR Table 6.3-3 revised the boric acid concentration information for the SDC llX tube side fluid from I percent to 1.5 wt. %. Reason for Change l l This change provided consistency with FSAR Table 3.3-2, showing boron, as boric acid,0-2620 ppm, 1 l FSAR Table 4.4 2, showing boron from 0-2620 ppm; and FSAR Table 9.2-2; that also shows boron limits l from 0-2620 ppm. I Safety Evaluation Summary This change is supported by existing FSAR boron limits and by the results of an engineering evaluation l' performed the original equipment supplier for the SDC llX. The evaluation concludes that the fluid in the tube side of the llX is designed to accommodate reactor coolant with a boric acid concentration of up to 1.5 wt. % boric acid. This change makes no physical change to the facility, does not change orjustify any change to the boric acid concentration in the reactor coolant, and does not change any operation of the plant. The activity makes no change to any probabilities or consequences of any malfunctions or accidents, l it does not present the opportunity for any new malfunctions or accidents, does not affect any boundary or margin of safety. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. l l l l
l l l l l f l FSARCR Number Title i 98-MP2-135 Plant Ventilation Systems, Vital Switchgear l Descrintion of Change , This change to FSAR Section 9.9 revised the description of the location of cooling equipment for the low er l 6.9/4.16KV AC switchgear room. ! Reason for Change During the ongoing FSAR verification effort, it was identified that the description of the cooling equipment for the lower switchgear room could be more accurately described. The actual configuration is correctly reflected in FSAR Figure 9.9-4. This change does not reflect a change to the facility, rather it is a change to the description of the facility in the FSAR. Safety Evaluation Summary 1 The change revised the description of the location of the ventilation / cooling equipment for the lower ; 4.16/6.9 KV AC switchgear. Due to its location in the cable vault, the ducting for this subsystem incorporates fire dampers that would prevent the spread of a fire from the lower switchgear room to the cable vault. These dampers would not be required if the subsystem components were located in the lower l switchgear room. Since these dampers were part of the original plant design and were, it.wefore, designed in accordance with appropriate standards, their malfunction need not be considered a new malfunction nor ! do they present an increased probability of an existing malfunction. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. I' I
FSARCR Number Title 98-MP2-140 Principle Parameters of the Safety injection System Description of Change This change to FSAR Table 6.3 2 and FSAR Figure 6.3-2 revised the high pressure safety injection (llpsi) pump shut off head from 2750 R to 2850 R. Reason for Change This change provides consistency between the FSAR , the design basis calculations and the bounding Technical Specification requirements. Safety Evaluation Summary The change increased the nominal lipSI pump shutoff head from 2750 R to 2850 R to be consistent with Design llasis calculations as well as the Technical Specification requirements which already recognized that the pumps are capable of developing head greater than 2850 R based on the pump performance characteristics and surveillance test data. It does not change plant equipment, processes or procedures. This administrative change does not initiate the possibility of a malfunction or accident, different from any previously evaluated; it does not increase the probability of occurrence or the consequences of any malfunction or accident; and does not decrease the margin of safety as defined in the basis of any Technical Specification. Th:refore, this change is safe and does not constitute an Unreview ed Safety Question. 2 1 I I s ! l t . I
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i { FSARCR Number Title 1 98-MP2-143 Condensate and Feedwater Systems l l Descriotion of Change This change to FSAR Section 10.4 revised the description of the condensate and feedwater system, with respect to secondary chemistry injection, to describe the location of the normal and alternative chemical injection points. .These descriptions were updated to reflect current design as documented on the current P&lDs and operating procedures. Reason for Change . The locations described in this section conflicted with the actual location that is in accordance with the design of the condensate polishing facility (CPF). This change provides consistency for the normal and attemate injection paths described in FSAR Section 10.4 and shown on FSAR Figure 10.4 2. Safety Evaluation Summary The locations of the chemical injection points were previously not accurately described in Section 10.4. l This change corrected that information. This change does not introduce a possibility of a new accident or malfunction nor does it increase the probability of an accident or a malfunction. No Technical Specifications or bases are affected by this change for any mode of operation. Therefore, this change is safe and does not constitute an Unreviewed Safety Question.. 9 l l t I-y# -- 2g-'Wr c+w-- w'+ -m Me7 -- gg ,>w-w- ,w--<t w tw-ec-=v -- 4 g- -,w2 e t' - -
l l FSARCR Number Title 98 MP2-147 Reactor Building Closed Cooling Water (RBCCW) l System, Tests and Inspection l l Description of Changc i l This change to FSAR Section 9.4 updated information to reflect plant operations for RBCCW pump and heat exchanger shif1s to limit check valve slam (ie. water hammer). It renects the enhanced method of I testing RBCCW equipment operation and performance so that RBCCW check valve slam is minimized. It removed ambiguity from the FSAR regarding the testing of RBCCW components in that the term , gradually is neither defined nor explained in the context. ' Reason for Change During the ongoing FSAR verification it was determined that a clariGcation to the text to accurately reHect : plant operations in regards to timely RBCCW pump and heat exchanger shills to limit RBCCW check I valve slam (i.e., water hammer) was necessary. l Safety Evaluation Summary This change did not add any new plant equipment and did not require any change to actual equipment operation per plant procedures. This change does not create the possibility of a malfunction of equipment j important to safety or affect the consequences of such a malfunction. Due to the nature of the change to i redect the enhanced testing of RBCCW equipment operation and performance, it does not initiate an accident previously evaluated and identified in the FSAR. More specincally, this change does not initiate or impact the radiological consequences of a loss of coolant accident , or of the other accidents identified in the FSAR. Additionally, implementation of this change does not initiate an accident of a different type than previously addressed. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. I l l l l l
[ 1 l FSARCR Number Title l 98 MP2-149 Reactivity and Power Distribution Anomalies Dnctiotion of Change This change to FSAR Section 14.4, including Tables and Figures, implemented a major update due to reanalysis of Event 14.4.1, Uncontrolleu Control Rod /Ilank Withdrawal from a Subcritical or Low Pow er Startup Condition (URWS). The changes included change in the descriptions of the analyses, change in the results of the analyses, and wording changes for clarification to be more consistent veith the current licensing basis analyses. A number of editorial changes were also included. Reason for Chengs This change was a result of the reanalysis perfonned by Siemens for the URWS event. In addition to updating the FSAR for the new URWS analysis, the comments from the ongoing FSAR verification elTort review were incorporated. Since the changes from the review are not associated with any new analysis or l new plant configuration, the changes are primarily to clarify the description of the current licensing basis analysis of record. Safety Evaluation Summary Revised analysis and evaluation have been performed for the URWS event described in the FSAR to incorporate the increased maximum reactor protection system response time of 0.7 seconds and the trip setpoint uncertainty of +12.62% for the variable overpower trip function. The result show that no fuel failures are predicted for the event and all the acceptance criteria are met and thus the conclusion of Section 14.4 is unchanged. Changes were reviewed to detennine the impact on licensing basis accident analysis as defined in the FSAR. The change does not increase the probability of occurrence of a malfunction of equipment important to safety or of a previously evaluated accident. The possibility of a malfunction or accident of a different type has also not been increased as a result of this change. The consequences of either a malfunction of equipment or of an accident have not been increased. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. l l l l
i f FSARCR Number Tith 98 MP2-152 Deercase in Reactor Coolant System Flow Descrintion of Change This change to FSAR Section 14.3, including certain Tables and Figures, incorporated clarifications or corrections of some information to adequately describe the existing licensing basis analysis. The changes are not associated with any new analysis or new plant configuration. Reason for Change During the ongoing FSAR verincation effort, it was identified that some editorial corrections, administrative changes, or clari0 cation were needed. Safety Evaluation Summary All the changes identined were either clarification, administrative changes, or editorial corrections. The changes in the sequences of events are editorial corrections to more adequately reflect the existing licensing basis analysis. Therefore, this change is safe and does not constitute an Unreviewed Safety Question.
l FSARCR Number Title 98 MP2-153 Control Systems,4160 Volt and 6900 Volt Systems 1 Descrintion of Chance ~ l This change to FSAR Sections 7.4,7.5, and 8.2, FSAR Table 7.4 1, and FSAR Figure 7.4-8 included changes to update information and enhance appearance, and to include reference to control element l assemblies (CEA) position display system power level and bypass inputs. It also changes the 4160 volt I description of the 4160 and 6900 volt systems, design bases, functional requirements.
- l. Reason for Change During the ongoing FSAR verification etTort, it was identitled that inconsistencies existed between the FSAR and plant configuration.
Safety Evaluation Summary These changes involved rearrangement of text associated with control element drive system (CEDS) single failure criteria, changing the upper bound of the speed setting of the CEDS group programmer from 50 to ; 40 inches per minute, and deletion of the requirement to automatically print out CEA positions at I prescribed intervals and upon detection of CEA deviations, it also changed the number of CEAs from 69 to 61, and deleted the automatic sequential mode of operation, which leaves the CEDS with only manual CEA motion capabii;ty. The changes do not have any negative impact on any system, structure, or ; component important to safety. The modifications will not increase the probability of occurrence or affect I the consequences of any accident or malfunction previously evaluated, create any new malfunction or accident, or decrease the margin of safety. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. l l l
2 FSARCR Number ~ Title 1 98-MP2-155 Communication Systems I Description of Change l This change to FSAR Section 7.8 updated and clarified the communications systems descriptions. l Reason for Change During the ongoing FSAR verification effort it was identified that the FSAR descriptions of the communications systems require updating and clarification to agree with the currently installed system configurations Safety Evaluation Summarv
)
The changes updated the communications systems descriptions to reflect the current systems configurations. The changes reficct systems upgrades to ensure reliability and communications coverage, and increased communication effectiveness regarding the Emergency Plan, Security Plan and Appendix R. The changes do not conflict with any safety requirements of the Appendix R Compliance Report, the Evacuation Plan or the Security Plan. Therefore, this change is safe and does not constitute an Ut reviewed Safety Question. l l
_. . ._ . ~ ._ ._. . - _ _ . - - _ _. _. . . . . _ - . - _ . _ . _ . - - - _ . e ; s 4 FSARCR Number Iitig 98-MP2-157 Diesel Generator Ventilation Systems t Description of Change - This change to FSAR Section 9.9 implemented an administrative change for clarification of ventilation system types and required recirculation air flow.
' Reason for Ch'ange During the FSAR verification effort, it was identified that clarification was needed regarding diesel generator ventilation system requirements.
Safety Evaluation Summary The change added a claritication to the recirculation air flow, and removed a specific recirculation air flow rate associated with a component since that component is already incorporated in the overall allowed recirculation rate. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. c e
,----..-r .-.- . . . - -_ ,
l l FSARCR Number Title 98-MP2-159 Turbine Building Ventilation System Descrintion of Change This change to FSAR Section 9.9 revised information to more accurately depict the configuration and operation of the turbine building ventilation system. The actual configuration is accurately depicted in FSAR Figure 9.9-4. The changes do not represent changes to the facility, but rather changes to the description of the facility. Emoafpr Change During the ci going FSAR verification effort, it was identified that certain information could be updated to more accurately describe the configuration and operation of the turbine building ventilation system. Safety Evaluation Summary The turbine building ventilation system is not safety related and is not credited in any accident analysis. The changes do not represent changes to the facility, but rather changes to the description of the facility in the FSAR. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. i l l
1 FSARCR Number Title , 98-MP2-160 Radioactive Waste Processing System ; l 1 Descriotion of Channe This change to FSAR Section 11.1 corrected the statement regarding the radioactive waste processing system requirements to state that releases are required to be less than the limits. l Reason for Change The change was made to remove inconsistencies between the FSAR and the Technical Specifications which only require that releases be less than the limits in 10CFR20.. Safety Evaluation Summarv This change revises the FSAR information concerning criteria for releases of radioactivity and it has no alrects on malfunctions of equipment important to safety or on consequences of accidents. It does not involve any tests or experiments. It does not decrease the effectiveness of the program to control release of radioactivity. Therefore, this change is safe and does not constitute an Unreviewed Safety Question. l 1 I I l l
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01 l i 9812180053- J i m . ,?i$ 1o $7 '. Northeast Utilities System I An a E M f d PR9G 81TED FOfi NORTHEAST NUCLEAR ENERGY CO. TITLE MILLSTONE UNIT 2 BY WBT CHKD. MEL APP. JTK APP. DwC wC LOGIC DIAGRAM - ANTICIPATED TRANSIENT DATEtO-25-88 DATE 11-1G-88 DATE 11-17-88 OATE 11-18-88 WITHOUT SCRAM (A.T.W.S.) SCALE N/A' OWG. NO. PP WATERFORD,CT. P. A
- 80-082 25203-28105 SH.36 FIGURE 07.09-01 SH- 01 NOVEMBER 1998
I RC30A @ ! PT-102A hU m HIGH ALARM CONTACTS ~ (28500 SH.53A,B ) RC30B @ PT-102B 1V m HIGH ALARM CONTACTS ~ C100 (28500 SH.54 A,B ) DIVERSE g
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SCRAM > RC30C PT-102C Q) MATRIX (32012 SH.48 )
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HIGH ALARM CONTACTS V (28500 SH.56A,B ) RC300 @ PT-102D 1V m HIGH ALARM CONTACTS ~ (28500 SH.57A,B ) RC30A R.R.S. CH."X" LOW ALARM CONTACT (28500 SH.16) l RC30B l R.R.S. CH."Y" l LOW ALARM CONTACT i (28500 SH.16) i i I SCHEME No. NM01 FACILITY Z5 3 NOTES: (SEE NOTE 3)
~~
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- REF. BLOCK DIAG. M-G SET No.1 5 37005,SH.21 U
- 2. A REF. BLOCK DIAG. M-G SET No.2 37005,SH.22
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'P- (NCORP.DCN DM2-00-1527-97 #BZM i Si 32012,SH.'48 m 4~"
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- U MF P.A.* NO. out REVISIONS 1 BY CHKAF en,.- **
C29 055 MG*1 (C291 INTERPOSING RELAY 4" CONTACTOR TRIP
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94X/MC1 (32012 SH.48A) C05 VERSE SCRAM RELAYS 948 C30 U A. D.3 DSS 0$$ 9 - MG#2 (C30 ) 32012 SH.48) INTERPOSING RELAY g" CONTACTOR TRIP Z (39055 SH.158) 94X/MG2 (32012 SH.48A) J O AUX EED A SERTURE
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CARD A!: o Aval!ab!c on - 22 1 Jorture Cnid AUX 3EED INITIATION (32012 SH.45) m 9812180053-2 o o m nhi$ Pie to 81 F Northeast Utilldes System E S N 'PRW BITED NORTHEAST NUCLEAR ENERGY CO. TITLE MILLSTONE UNIT 2 BY T.A. SWIFT CHKD- MEL ' APP. WCH APP. 3wc BLOCK DIAGRAM DATE 7/21/87 DATE 11-12-87 DATE 11-13-87 DATE WP DIVERSE SCRAM SYSTEM (A.T.W.S.) SCALE NNE DWG. to. W ATERFORD. CONNECTICUT P.A.* 804382 25203-37005 SH.105 FIGURE 07.09-02 SH- 01 NOVEMBER 1998 _ e es +ee*58 S
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REFERENCES:
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-- -O(CTH-1 ) (CTH-5 ) -- -O(Tx-7 ) 25203-39045 SH.45A C05R -
1 Aux RELAY MG #2 A x FEED aux RELAY MG #1 25203-31189 SH.1 RC30A LOAD -- INITIATION -- LOAD 25203-31189 SH.2 RC308 2 CONTACTOR -- Z2 -- CONTACTOR 25203-31189 SH.3 RC30C 32012 SH.48A) 6 10 12 SH.48Al Q2012 SH.45) ( 25203-31189 SH.4 RC300
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- 2. FOR HS102A-D SWITCH DEVELOPMENT Apen e un SEE 32012 SH. E. FIG.6 3.TEMINATIONS AT TX & CTH ARE A SHOWN FOR TESTING PURPOSES ONLY. oK l
l {g I REVISIONS DURING CONSTRUCTION P. A.
- lNOTE:
l MANUAL REVISIONS TO THIS DOCU)ENT I g W EN AS-BUILT ARE PROHIBITED. l L_____________l O Northeast Utilities System acme. ocms> 15-95. N D TITLE FOR NORTHEAST NUCLEAR ENERGY CO.
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