ML18038A770
| ML18038A770 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 10/25/1989 |
| From: | Terry C NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18038A768 | List: |
| References | |
| NMP2L-1210, NUDOCS 8911020134 | |
| Download: ML18038A770 (168) | |
Text
7 NIAGARA u MOHANK NIAGARA MOHAWK POWER CORPORATION/301 PLAINFIELD ROAD, SYRACUSE, N.Y.13212/TELEPHONE (315)474-1511 October 25, 1989 NMP2L 1210 U.S.Nuclear Regulatory Commission Attention:
Document Control Desk Hashington, D.C.20555 Re: Nine Mile Point Unit 2 Docket No.50-410 IKf=B-Gentlemen:
Pursuant to 10 CFR 50.4(b)(6) and 50.71(e), Niagara Mohawk Power Corporation hereby submits one signed original and ten copies of Revision 1 to the Nine Mile Point Unit 2 Updated Final Safety Analysis Report, hereinafter referred to as the Updated Safety Analysis Report (USAR)for Nine Mile Point Unit 2..Copies are also being sent directly to the Regional Administrator, Region I and the NRC Resident Inspector at Nine Mile Point.In accordance with 10 CFR 50.71(e)(4) this update includes modifications completed prior to April 30, 1989.The certificate required by 10 CFR 50.71(e)(2) is attached to this letter, All errata items identified in Attachment 1 to our previous USAR transmittal letter of April 28, 1989, have been resolved and the appropriate changes incorporated into this update.However, as we noted in our previous transmittal letter, Niagara Mohawk's internal Nuclear Compliance and Verification group conducts an additional independent verification of the technical basis of'hanges and the accuracy of the USAR changes.This verification of certain USAR changes for both this update and the original submittal has not been completed, The remaining open verification items fall into one of four categories:
1).The majority of open verification items involve inconsistencies in the level of detail shown on USAR figures when compared to the source design documents.
These items do not involve questions of accuracy, but will require development of standards and revision of a large number of design drawings to satisfy NHPC's internal verification procedures.
89ii020134 89i025 PDR ADOCK 05000410 PDR 1473b~$9~{
l 4' 2).Several verification items relating to setpoints on USAR figures are still being completed.
These items have raised questions about setpoints contained in the USAR.Procedures are in place, including 10 CFR 50.59 evaluations, to ensure adequate control of setpoint changes in the plant;however, setpoints on Logic Sketches (LSKs)in the USAR are not routinely updated.Setpoints shown on LSKs are provided as guide values and are not as-built.This is identified on the USAR figures by notes that state: Setpoints shown on logic drawings are for logic clarification only and may be only approximations of the actual process setpoints.
Setpoint data sheets must be referred to for actual process setpoints.
A small number of the setpoints in the USAR text were originally verified using the design LSKs.There is, therefore, the possibility that these setpoints are also not as-built.A program is now being developed to verify setpoints in the text against the as-built values.3).Some items from this update (Revision 1)are still in the final verification process.4).Source documentation for changes developed by GE had not been available, preventing final verification.
Programs to resolve the general arrangement and setpoi nt issues will be established no later than November 30, 1989.A schedule for completion of the programs and all open verification items including any open items from 3 and 4 above wi 11 be established at that time.As stated in our April 28, 1989 submittal letter, procedures are in place to document and resolve verification comments.USAR changes resulting from those comments will then be incorporated.
Attachment 1 is being submitted in fulfillment of the requirements of 10 CFR 50,71(e)(2)(ii) to identify changes made under the provisions of 10 CFR 50.59 but not previously submitted to the Commission.
Included in Attachment 1 are eight safety evaluations which were inadvertently left out of our April 28, 1989 submittal.
Four of these safety evaluations reflected changes made to the design of the plant prior to the issuance of the full-term operating license.The other four should have been included as changes for the last submittal.
All eight safety evaluations were incorporated into Revision 0 to the USAR.None of the safety evaluations in Attachment 1 involved an unreviewed safety question as defined by 10 CFR 50.59(a)(2).
Sincerely, NIAGARA MOHAWK POWER CORPORATION WER/sek 1473b C.D.Terry Vice President Nuclear Engineering 5 Licensing Attachment xc: Regional Administrator, Region I Mr.R.A.Capra, Director Mr.R.E.Martin, Project Manager Mr.W.A.Cook, Resident Inspector Records Management s'
~y UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of]]Niagara Mohawk Power Corporation
]](Nine Mile Point Unit 2)]Docket No.50-410 AFFIDAVIT C.D.Terr , being duly sworn, states that he is Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto;and that all such documents are true and correct to the best of his knowledge, information and belief.1989.Subscribed and sworn to before me, a Notary Public in and for the State of New York and County of , this W~PA day of d'otary Public in and for County, New York pgNEq,5MB~'
HdgyPubPCR th'933503 s~te g1'HGw Y~~~~gyp~/m)~My Commission expires:
t SAFETY EVALUATION REPORT SURGERY SER No.: PG-201 SER Title: Implementation of C02 Fire Protection in Switchgear Area.System: Fire Protection FSAR Sections Affected: F 9.4-3a, 9.4-12b, P 9.4-17, F 9.4-6 (All)Description:
Incorporation of Modification PN2Y86MX090.
This modification provides reinforcement of walls and doors and provides dampers to accommodate C02 discharge and the associated pressure of Fire Protection equipment.
This covers the normal swi tchgear area El.261 E&W and Turbine Building Switchgear East.Incorporated in conjunction with modification PN2Y86MX114.
This change does not adversely affect the safe shutdown analysis and does not constitute an unreviewed safety question.(7858G).89ll020134,,
SAFETY EVALUATION REPORT
SUMMARY
SER No.: PG-201 SER Title: Implementation of C02 Fire Protection in Switchgear Area.System: Fire Protection FSAR Sections Affected: F 9.4-10E
Description:
Incorporation of Modification PN2Y86MX114.
This modification provides for reinforcement of walls, doors and incorporation of dampers to accommodate C02 discharge and the associated pressure of Fire Protection equipment.
This covers the normal switchgear area El.237 E 5 H, Turbine Building Switchgear El.277'0" Nest, and Radwaste Switchgear El.277'0".Incorporated in conjunction with modification PN2Y86MX090.
This change does not adversely affect the safe shutdown analysis and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: PG-201 SER Title: Environmental Sample Tap Installation.System: NA FSAR Sections Affected: F 9.2-lh, 10.4-7d
Description:
Incorporation of Modification PN2Y86MX108.
This modification provides an added sample tap to monitor SHP and CNS (service water and circulating water)for contamination.
This is in accordance with NRC IE Bulletin¹80-10 and Reg.Guide 4.2 and does not constitute an unreviewed safety question-.
(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: PG201 C SER Title: Removal of Helded Tables in Control Room System: NA FSAR Sections Affected: F 1.2-15, Sh.l
Description:
Incorporation of Modification PN2Y87MX188.
This modification removed a welded seismic table from the control room.This table was used as a work table and was too large and cumbersome for use in the control room.Table was shown in USAR Figure 1.2-15, Sh.1.The removal of this table will not affect contmi room operation and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT SUONRY SER No.: 87-039 SER Title: Sealing of Embedded Conduit in Fire Barriers System: NA FSAR Sections Affected: Section 9A.3.5.1.2 Oescription:
This evaluation addresses a change in sealing criteria for embedded conduit, 1" or less in diameter.This change relieves the requirement to provide fire barrier sealing on some conduit (1" Dia.or less).This is based.on the NRC acceptance of similar relief at Cleveland Electric Illuminating (Perry Site).It was determined that this change does not affect the safe shutdown capability and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 87-050 SER Title: Addition of Dx Coil,to 2HVH-ACU 2A/B and Humidification System.System: Radwaste Building Ventilation (HVN)FSAR Sections Affected: P 9.4-37, 9.4-37a, 9.4-66, T9.4-4, 9.4-1, F9.2-8a, 9.2-8b, 9.3-lie, 9.4-3f, 9.4-10e, 9.4-21, Sh.2, 9.4-11, Sh.12, 9.4-11, Sh.15.Description:
Incorporation of Modi fiction PN2Y86MX093.
This modi f 1 cation involves changes to the Radwaste Control Room Ventilation to maintain temperature and&umidity within required limits for equipment and personnel, The changes maintain the original design intent of the ventilation system and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT SUNNARY SER No.: 87-059, Rev.1 SER Title: Removal of Secondary Containment Hatches System: N/A FSAR Sections Affected: F 1.2-7, Sh.1, 1.2-7, Sh.2, 1.2-8, Sli.1, 1.2-9, Sh.1, 1.2-9, Sh.2, 1.2-10, Sh.1, 1.2-10, Sh.2, 1.2-6, Sh.2.Description:
This change will allow operation of the plant with secondary containment floor hatches open or removed for ease of plant operability, maintainability and efficiency.
This can be accomplished without adverse impact to plant design parameters or accident analysis and therefore does not constitute an unreviewed safety question.9 (7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 87-060, Rev.2 SER Title: RDS Scram Discharge Volume Vent and Drain Valve Limit Switches.System: Control Rod Drive System (RDS)FSAR Sections Affected: F 4.6-5, Sh.3, 7.2-1
Description:
Incorporation of Modification PN2Y87MX092.
This modification provides scram discharge volume vent and drain valve position indication to the PMS Computer.This will enable verification of valve position for surveillance testing.: This will not affect system performance and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 87-087 SER Title: Addition of RRCS Feedwater Runback Inhibit System: Redundant Reactivity Control System (RRCS)FSAR Sections Affected: Section 7.6.1.8, 7.6.2.8.4, F7.6-9, Sh.6, Section 7.7.1.3
Description:
Incorporation of Modification PN2Y86MX110.
This modification will provide an inhibit switch for the Redundant Reactivity Control (RRCS)feature of feedwater runback.This switch is only to be used during surveillance testing to prevent a spurious trip at power.This will prevent the potential severe plant transient that could occur.Operator action.will maintain plant parameters while the inhibit switch is in use.Analysis has shown that the use of this switch during surveillance testing will not increase the probability or consequences of an accident and therefore does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 87-097, Rev.2 SER Title: Secondary Containment Design Bases System: N/A FSAR Sections Affected: P 6.2-57d
Description:
This change provides the evaluation for changes in the secondary containment drawdown analysis.This identifies the assumptions and requirements for maintaining plant conditions consistent with the revised analysis.Operating conditions and the accident analysis are considered and the requlrementr maintained and identified in the USAR changes.The safety analysis and NRC requirements are maintained and these changes do not constitute an unreviewed safety question.(7858G) 0 0 SAFETY EVALUATION REPORT
SUMMARY
SER No.: 87-137, Rev.1 SER Title: Haste Neutralizing Tank Discharge Filter/Bypass Line Addition.System: Make up Hater Treatment System (HTS)FSAR Sections Affected: F 9.2-5a, 9.2-5e Oescription:
Incorporation of'odification PN2Y87MX168.
This modification provides additional filtering and piping to maintain effluent discharges within required limits.This is consistent with the NMP2 Environmental Protection Plan and State and Federal discharge requirements and therefore does not constitute an unreviewed safety question.-
(78586)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 87-145;Rev.1 SER Title: Condenser Drain Tank, 2ARC-TKl, Check Valve System: Air Removal system (ARC)FSAR Sections Affected: F 10.4-1, Sh.5, 10.4-2a, 9.3-10c, T9A.3-12, P10.4-7
Description:
Incorporation of Hodification PN2Y87HX185.
This modification provides a check valve and piping changes in the condenser air removal system to prevent backflow of condensate to the drain tank (2ARC-TKl) during system operation.
This enhances system operation and does not affect conditions of the safety anal~is.Therefore this does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 87-155 SER Title: Reactor Feedwater Pump Seal Water Modifications
.System: Feedwater System (FWP)FSAR Sections Affected: F 10.1-6c
Description:
Incorporation, of Modification PN2Y86MX098.
This modification incorporates a duplex strainer and replacement of pressure control valves, 2FWP-PCV5A/B/C with a manual plug valve, 2FWP-V35A/B/C in each feedwater pump seal supply line.These changes provide cleaner water to the seals and enables Operati'Qns to manually control the seal water pressure to the.feedwater pumps.These changes do not change system operation or the safety analysis.Therefore this does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATtON REPORT
SUMMARY
SER No.: 87-174, Rev.1 SER Title: Addition of GEMs Annunciators
~System: Process Radiation Monitoring FSAR Sections Affected: F 9.4-9, Sh.18, 9.4-13, Sh.10, P 9.4-44
Description:
Incorporation of Modification PN2Y87MX211.
This modification provides additional annunciation for GEMs monitoring for the reactor/radwaste building vent radiation monitoring and adds reflash capabilities for the main stack effluent and radiation monitor annunciation, This maintains compliance with Technical Ypecification required control room annunciation for the identified parameters.
This modification does not affect system operation or the safety analysis and therefore does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-008, Rev.1 SER Title:-Addition of Solenoid Valves to RCS Pump Seal Staging Lines System: Reactor Coolant System (RCS)FSAR Sections Affected: F 5.4-2b, 5.4-2c, 9.3-lg, T3.2-1, Sh.2, 3.2.1, Sh.26a
Description:
Incorporation of Modification PN2Y87HX184.
This modification replaced the existing AOVs on the RCS pump seal staging line with SOVs.This enables the valves to close on a loss of AC Power to the RCS pumps to prevent pump and seal damage.The change to SOVs was necessary because maintaining air to the AOVs (to close)during a loss of power, could have potentially led to a degradation of the primary containment integrity and a violation of the bypass leakage criteria per Technical Specifications.
This modification maintains compliance with the safety analysis and therefore does not constitute an unreviewed safety question.(7858G) 0 SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-010 SER Title: Bypass Switch for 2HRS-PS107
.System: Main Steam (MSS)FSAR Sections Affected: F 10.1-3h
Description:
Incorporation of Modification PN2Y87MX232.
This modification provides a bypass switch that prevents the tripping of 2MSS-AOV92A/B, and isolation of the Moisture Separator Reheaters, during surveillance testing of turbine valves.During surveillance testing of the turbine valves at low power, a small enough pressure could be sensed at 2HRS-PS107 to trip AOV92A/B.This modification will prevent inadvertent trips during this condition and does not affect the safety analysis.Therefore this modificaiton does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-014 SER Title: Add Pressure Indicator to 20FG-FT3A/B System: Off Gas (OFG)FSAR Sections Affected: F 11.3-la
Description:
Incorporation of Modification PN2Y87MX246.
This modification provides a pressure indicator to the off gas system to enable Operations personnel to perform density compensation of indicated system flow to determine actual system flow.This will enchance system performance and does not affect the safety analysis.Therefore, this will not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-022 SER Title: Setpoint Change for 2DFR*LS145 from 2.25" to 2.75"'ystem: Reactor Building Drains (DFR)FSAR Sections Affected: F 9.3-13, Sh.5, 9.3-9e
Description:
This setpoint change will increase the alarm condition sensed by 2DFR*LS145 in the RCIC pump room.This level switch monitors water level in the RCIC pump room, The setpoint change more accurately identifies an alarm condition and will not impact the existing flood analysis for the area.This will therefore not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-027, Rev.1 SER Title: Change of QA Classification of Conduit-System: N/A FSAR Sections Affected: T 3.2-1, Sh.26c, 3.2-1, Sh.16, 3.2-1, Sh.15a
Description:
This change revises the Quality Assurance requirements identified in Table 3.2-1 for conduit and its associated appurtenances (except when part of an environmental seal).This changes the requirements from"I"-to"NA" while maintaining pertinent provisions of the operational quality assurance program.This change does not affect the safety related function of any system or component and therefore does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-029 SER Title: Install Isolation Valves for HVK Makeup Check Valves System: Control Building Chilled Hater System (HVK)FSAR Sections Affected: F 9.4-la
Description:
Incorporation of Modification PN2Y87HX252.
This modification provides isolation valves to facilitate maintenance on valves 2HVK*V12 and*V95.The addition of these isolation valves will enable maintenance to be performed without the need to isolate the subsystem expansion tank and render the subsystem ii95perable per Technical Specifications.
This maintains the requirements of the safety analysis and therefore does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-034, Rev.1 SER Title: Removal of Restricting Orifice 2ICS*R0158 System: Reactor Core Isolation Cooling (ICS)FSAR Sections Affected: F 5.4-9, Sh.1, 5.4-9, Sh.2
Description:
This change addresses the removal of Restricting Orifice 2ICS*R0158.
During system testing, it was identified that restricting orifice*R0158 did not perform its intended function due to the existing piping design.The orifice was therefore removed to enhance system operation and maintain required parameters.
This change identifies the orifice removal in the affected SAR figure.There is no change to actual system performance and therefore does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT SUNDRY SER No.: 88-035, Rev.l SER Title: Redesign of Condenser Sampling Lines System: Turbine Plant Sampling (SST)FSAR Sections Affected: F 9.3-5e, 9.3-5f
Description:
Incorporation of Modification PN2Y87MX209.
This modification replaces sample pumps, changes sample piping and provides backflush capabilities to the condenser sampling system.These changes correct excessive failures and difficulties in the sampling system.This does not affect the design function of the system or the safety analysis.Therefore, this does not constitute an unrevlewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-037 SER Title: Reroute Second Point FN Heater Level Transmitter Piping.System: Feedwater Heaters (HOL)FSAR Sections Affected: F 10.1-7a, 10.1-7b, 10.1-7c
Description:
Incorporation of Modification PN2Y88MX055.
This modification reconfigures the level instrumentation for the second point feedwater heaters.This reconfiguration is designed to reduce the effect of feedwater transients on the extraction steam system and reduce spurious trips.This change will no~ffect the safety analysis and will not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT SURGERY SER No.: 88-038 SER Title: Addition of EHC Narrow Range Pressure Indicator ,System: Main Steam (MSS)/Electro-Hydraulic Control System (TMB)FSAR Sections Affected: F 10.1-3g
Description:
Incorporation of Modification PN2Y88MX012.
This modification installed a narrow range pressure transmitter and indicator at 2MSS-PT143, to provide main steam, pressure.This indicator will enable operations to more accurately determine.steam pressure to set the EHC pressure regulator.
This will enchance system operation and will not affect the safety analysis.Therefore this does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUAT ION REPORT
SUMMARY
SER No.: 88-047, Rev.2 SER Title: GTS System Single Failure Mods.System: Standby, Gas Treatment (GTS)FSAR Sections Affected: F 6.5-1, Sh.2, 6.5-1, Sh, 5, 6.5-1, Sh.8, 9.4-81, T 8.3-1, Sh.3, 8.3-2, Sh.3, 8.3-4, Sh.6, 8.3-4,.Sh.18
Description:
Incorporation of Modification PN2Y88MX101.
This modification modified valves 2GTS*MOV28A/B internally to provide fail open capability on loss of power.The air inlet valves 2GTS*MOV4A/B are cross connected.
These changes insure Mat the delay heat removal capability of the standby gas treatment system wi 1 1 be protected against the loss of a single train.Valves*MOV28A/B will also be changed to the normally open position to protect against a single failure.This modification maintains the requirement of the safety analysis and therefore will not constitute an unreviewed safety question.(7858G)
SAFETY EVAlUATION REPORT
SUMMARY
SER No.: 88-049 SER Title: Modify Airflows to RWCU Pump Rooms System: Reactor Building Ventilation (HVR)FSAR Sections Affected: F 9.4-8c, 9.4-8d, 9.4-8f
Description:
To insure proper ventilation is provided to the Reactor Water Cleanup (WCS)Rooms, during the recirculation mode of the Reactor Building Ventilation System, holes will be cut in the curtains placed over the WCS Room doors.The curtains.were provided to maintain design conditions for a high energy line breW and i.nsure proper ventilation during normal operating conditions.
The air flow to and from the WCS Room has been ad)usted to insure proper ventilation is provided in all modes.This change helps maintain the requirements of the safety analysis and therefore will not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-055 SER Title: Reactor Building Unit Cooler Thermostat Setpoint Change.System: Reactor Building.Ventilation (HVR)FSAR Sections Affected: F 9.4-9, Sh.8, 9.4-9, Sh.20
Description:
As required by the Secondary Containment Drawdown Analysis, a minimum Q T must be maintained between service water and reactor building temperature.
This could require heating of the reactor building while the unit coolers were in operation.
This change revised the unit cooler setpoint so as not to conflict with heating of the Reactor Building as required.The setpoint is a range between 85 to 97 F to allow Operations personnel flexibility In ad)usting the unit cooler setpoint to maintain the required b, T when service water temperature changes.This change maintains the requirement of the safety analysis and wi 1 1 not constitute an unreviewed safety question.(7858G) 0 SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-057 SER Title: Relocate'Nitrogen Bottle Rack, TB El;261'ystem:
Hot Hater Heating (HVH)FSAR Sections Affected: F 9.4-22@, 1.2-19;Sh.2
Description:
Incorporation of Modification PN2Y88MX109.
This modification relocated a frequently accessed nitrogen bottle rack out of a potential radiation/contamination area to an unrestricted area: This was to reduce collective exposures and radwaste volume.These nitrogen bottles are used in the hot water h~ting system for pressurization and to minimize oxidation in the piping.This change does not affect the safety analysis and does not constitute an unreviewed safety question.~g (7858G)
SAFETY EVALUATION REPORT SUIOIARY SER No.: 88-058 SER Title: Circulating Hater Gate Valve Mid-Position Indication
~System: Circulating Hater System (CHS)FSAR Sections Affected: F 10.4-7d, 10.4-8, Sh.8, 10.4-8, Sh.9
Description:
Incorporation of Modification PN2Y88MX070.
This modification provides mid position indication for the circulating water gate valves to facilitate operation of the valves in the zoning mode of the cooling tower.The additional valve posi tion indication is provided on the revised SAR figures.This Qiange enhances system operation and will not affect the safety analysis.Therefore this modification will not constitute an unreviewed safety question.(7858G) 0 SAFETY EVALUATION REPORT
SUMMARY
SER No.: 8&-064, Rev.2 SER Title: Chicago Fluid Power Actuator Upgrade ,System: Various FSAR Sections Affected: F 9.3-lb
Description:
Incorporation of Modification PNZY&&MX064.
This modification incorporates changes to air supply equipment to'hicago Fluid Power Actuators in the Auxiliary Steam, Turb)ne Auxiliary, and Moisture Separator Reheater Systems.This is due to high level of repair and maintenance required on these actuators-.
These components do not perform any safety functions and there will not be an impact to the safety analysis.Therefore this modification does not constitute an unreviewed safety question.(785&G)
.~
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-068 SER Title: Reactor Building HVAC Fan Interlocks.System: Reactor Building Ventilation (HVR)FSAR Sections Affected: F 9.4-9, Sh.1, 9.4-9, Sh.2, 9.4-9, Sh.3
Description:
Incorporation of Modification PN2Y88MX043.
This modification adds interlocks between the operating Reactor Building Ventilation Fans, both supply and exhaust, and their associated discharge dampers.These will cause the dampers to go fully closed if its associated fan should fail to start.This will prevent a recirculation flow path and possible improper air flow through the Reactor Building, resulting in exhaust fan trips and GTS initiation, if the fans fail to start.This will enhance system operation and not affect the safety analysis.Therefore this will not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATlON REPORT
SUMMARY
SER No.: 88-069, Rev.1 SER Title: Reactor Building HVAC Low Flow Override Switch , System: Reactor Building Ventilation (HVR)FSAR.Sections Affected: F 9.4-9, Sh.5, 9.4-9 (New)Description:
Incorporation of Modification PN2YSSMX053.
This modification provides-a low flow override switch for the Reactor Building HVAC.This replaces an existing push button for"the same purpose.The switch will be used during fan manipulations until normal flow has been established and prevent inadvertent isolations of the HVR system due to low flow conditions.
This modification does not affect the safety analysis and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT SUNNARY SER No.: 88-070 SER Title: C02 Tank Room Platform System: N/A FSAR Sections Affected: F 1.2-8, Sh.1, 12.3-8, 12.3-41
Description:
Incorporation of Hodification PN2Y86MXlll.
This modification provides an access platform from the Hotwater equipment area to the C02 Tank Room.This is to enhance personal safety and replace the use of a ladder to gain access.This will not affect the safety analysis and does not constitute an unreviewed safety question.(7858G) 0 SER No.: 8&-071 SAFETY EVALUATION REPORT SUNMARY SER Title: Reactor Recirculation Pump Seal Replacement System: Reactor Recirculation System (RCS)FSAR Sections Affected: T 5.2-5, Sh.4
Description:
Incorporation of Hodification PN2Y&7HX157.
This modification provides a replacement mechanical shaft seal assembly for the Reactor Recirculation pumps.This is due to the high failure rate of the existing type of seal assembly and unavailability of replacement parts.Additional changes to the.seal staging flow will also be made.The replacement seal meets or exceeds the requirements of the original seal and therefore does not constitute an unreviewed safety question.O O (785&G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-073 SER Title: Reactor Building HVAC Surveillance Test Switches ,System: Reactor Building Ventilation (HVR)FSAR Sections Affected: P 9.4-32, F 9.4-9, sh.5, 9.4-9, Sh.10
Description:
Incorporation of Modification PN2Y88HX042.
This modification provides a bypass test switch for the high radiation isolation on the Reactor Building Ventilation System.This is to replace)umpers used during surveillance testing and will enhance'personal safety and reduce unintentional isolations that~have occurred during testing.This modification does not affect the safety analysis and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT SUNDRY SER No.: 88-078, Rev.1 SER Title: Add Condenser Neck Spray System.System: Condensate System FSAR Sections Affected: F 10.1-5a, 10.1-5b, 10.1-3k
Description:
Incorporation of Modification PN2Y88MX037.
This modification provides a cooling system to the condenser neck area to be used when steam is dumped directly to the main condenser.
This wi 1 1 help in reducing higher than normal exhaust hood temperatures and prevent turbine trips from this condition.
Water will be utilized from the condensate system for cooling when steam from the bypass valves is dumped to the main condenser.
This modification does not affect any safety functions or impact the safety analysis.Therefore, this does not constitute an unreviewed safety question.'I (7858G)
SAFETY EVALUAT ION REPORT SENARY SER No.: 88-080 SER Title: Position Indication for RCIC Valves System: Reactor Core Isolation Cooling (ICS)FSAR Sections Affected: F 5.4-9b, 5.4-9d
Description:
Incorporation of Modification PN2Y88HX102.
This modification provides position indication for the RCIC pump test bypass valve to condensate storage tank and the RCIC pump turbine governing valve.This position indication wi 1 1 be recorded on the GETARS system for use during surveillance testing.This g.ll not affect system performance or any safety functions.
Therefore, this modification does not constitute an unreviewed safety question.E,~.(7858G)
SAFETY EVALUATiON REPORT
SUMMARY
SER No.: 88-081 SER Title: Diesel Fuel Oil Spill Prevention System.System: Diesel Building Drain System (DFD)FSAR Sections Affected: F 9.3-12b
Description:
Incorporation of Modification PN2Y88MX050.
This modification provides a fuel oil spill containment area at the diesel fuel oil fill location outside the Diesel Generator Building.This includes a concrete pad to contain a spill and piping to remove water from the pad area and direct it to the Diesel BUilding Drain System.This modification.is in response to an Environmental Protection Agency (EPA)inspection.
This modification complies with EPA requirements and does not affect the safety analysis.Therefore, this change does not constitute an unreviewed safety question.(7858G) 0 SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-086, Rev.2,88-065, Rev.1 SER Title: Nine Mile Point Nuclear Division Organization as of March 1989 System: NA FSAR Sections Affected: P 13.5-1, 13.5-2, 13.5-3, 13.5-3a, 13.5-4, 13.5-5, 13.5-6, 13.5-7, T 13.5-1, Sh.1, 13.5-1a (Deletion) 13.5-3, Sh.1, 13.5-3, Sh.2, T 13.5-4, 13.5-6, Sh.2, 13.5-6, sh.3, 13.5-6, Sh.4, P 1.10-19*, 1.10-19a*, 1.10-33*, 1.10-33a*, 13.4-1*, 13.4-2*, 13.4-2a', 13.4-2b*, 13.4-3*, F 13.4-1*, P 1.10-16*, 1.10-9*, 9A.3-la, 9A.3-2, 9A.3-3, Section 13.1 (except Table 13.1-4)*, T 13.4-1*, 13.4-2, Sh.1*, 13.'4-2,'Sh.
2*, 13.4-3, Sh.1*, 13.4-3, Sh.2*, T 13.4-35, Sh.3*Description:
This evaluation addresses changes in the Nine Mile Point Nuclear Division organization as of March 1989.This includes organizational changes made in September, 1988.These changes have no impact on the safety analysis and will not constitute an unreviewed safety question.*Rev.0 Changes(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88-087 SER Title: Relocate Off Gas Freeze Out Dryer Level Control System: Off Gas System (OFG)FSAR Sections Affected: F 11.3-1b
Description:
Incorporation of Modification PN2Y88MX077.
This modification removed the existing level control instrumentation for the Off Gas Freeze Out Oryers and installed a new drain receiving tank and discharge pump with associated instrumentation and controls.This corrects level control problems with collected moisture and prevents system inefficiencies created by the old instruments.
This does not affect any safety function or the safety analysis.Therefore, this modification does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATiON REPORT SUNMARY SER No.: 89-003 SER Title: Correct and Clarify Classification of Fire Barriers.System: Fire Protection FSAR Sections Affected: F 9A.3-3, 9A.3-4, 9A.3-5, 9A,3-6
Description:
The evaluation corrects discrepancies identified between the FSAR figures identifying fire barriers and actual plant conditions.
No changes to the plant were required.This does not affect the safe shutdown analysis and does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATlON REPORT SUGARY SER No.: 89-006 (Unit 1 SE¹)SER Title: Vice President QA Reporting to Executive VP-Nuclear Operations.System: N/A FSAR Sections Affected: P 13.1-2, F 13.1-1, 13.1-1a, 13.1-2
Description:
This evaluation addresses the change in reporting level for the Vice President-Quality Assurance.
This change does not affect any safety functions or the safety analysis.This does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 89-008, Rev.5 SER Title: Service Water System Divisional Separation Logic.System: Service Water System (SWP)FSAR Sections Affected: F 9.2-2, Sh.6, 9.2-2, Sh.10, 9.2-2, Sh.25, 9.2-1h, P 9.2-7, 9B.8-3, 9B.8-5, T 9B.8-3, Sh.13 Oescript ion: Incorporation of Hodi f i cation PN2Y89MX030.
Thi s modification provides changes to the control circuits of service water valves to satisfy single failure criteria on a full loop and partial loop.These changes help maintain service water operability during accident and transient conditions.
This helps to maintain the required conditions for safe shutdown and will not affect the safety analysis.Therefore, this modification does not constitute an unreviewed safety question.(7858G)
SAFETY EVALUAT I ON REPORT
SUMMARY
SER No.: 89-012 SER Titte: High Level Annunciator Alarm for 2LHS-TK30-System: Liquid Radioactive Haste System (LHS)FSAR Sections Affected: F 11.2-1]Description:
This evaluation addresses software changes that were made to the LHS (Liquid Radioactive Haste)computer to alarm a common annunciator on,a high level in tank 2LHS-TK30.
This change does not change the function of the LHS system or affect any safety functions.
Therefore, this change does not constitute an utireviewed safety question.(7858G)
SAFETY EVALUATION REPORT SUNMARY SER No.: 89-018 SER Title: Isolation Valves 2RCS*SOV104/105 to be in the Normally Open Position System: Reactor Recirculation System (RCS)FSAR Sections Affected: F 5.4-2b
Description:
This evaluation identifies the correction to USAR Figure 5.4-2b to correctly reflect the normal position of 2RCS*SOV104/105.
These valves are normally open to enable continuous monitoring of rector coolant chemistry.
The normal position of these valves was inadvertently changed in USAR, Rev.0 to indicate a normally closed position.This change corrects that indication.
No physical changes to the plant or methods of operation resulted from this change.Therefore, this correction does not constitute an unreviewed safety question.(7858G)
Attachment 6 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: 89"031, Revision 1 Incorporation of NUREG"0313, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, Revision 2 Criteria into the Licensing Basis SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
NA Sections 5.2.3.4.1; 1.13 This change incorporates the criteria of Revision 2 to NUREG-0313, Technical Report on Material Selection and Processing Guildelines for BWR Coolant Pressure Boundary Piping, into the licensing basis, USAR Sec-tion 5.2.3.4.1.
In addition, a field weld has been noted as an exception to the NUREG-0313 criteria and will receive augmented examination.
This change resulted in plant Technical Specification and Inser-vice Inspection (ISI)program changes.The Technical Specification change was approved by the NRC by let-ter dated June 14, 1989.This change establishes requirements consistent with NUREG-0313, Revision 2, to enhance mitigatic.:
of intergranular stress corrosion cracking and therefore does not constitute unreviewed safety questions.
4436-176720183-HC4
Attachment 5 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: 89"032 Incorporation of Main Steam Isolation Valve (MSIV)Closure Assist Description and Associated Leak Testing Into the Licensing Basis SYSTEM: NA USAR SECTIONS AFFECTED: DESCRIPTION:
Section 5.4.5.2 a~~">This USAR change revises the USAR to include an MSIV spring closure assist description and a commitment to perform associated leaktightness testing.This change is a result of General Electric (GE)Report No.PED-01-0189 and associated GE SIL 477.This change does not change the current plant design and has no impact on analytical results or procedures except for ISI/IST program procedures for additional testing, which supports nuclear safety.Therefore, this change does not constitute an unreviewed safety question.4476-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: USAR,SECTIONS AFFECTED: DESCRIPTION:
89-033 USAR Clarifications and Editorial Corrections NA 1.Section 9.4.6.5 2.Failure Modes and Effects Analysis'(FMEA)Sec-tion 4.4, Table 4-1, Appendix A, and Appendix B The changes to the USAR section and the USAR Failure Modes and Effects Analysis are a result of identify-ing clarifications, typographic errors, and editorial discrepancies or omissions discovered during review of the USAR Revision 0, April 1989 submission.
The review concluded that the changes do not constitute any unreviewed safety questions.
5029-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: 89-034 Miscellaneous Editorial Changes to the USAR NA USAR SECTIONS AFFECTED: Figures 9.4-5, Sheet 8;6.2-70, Sheet 21;9.2-4, Sheet 6;9.4-11, Sheet 5y 8'lip 8'3y Sheet 2y Figure 9.3-7, Sheet 4;Table 2.3-4A;Chapter 14, List of Tables;98.8.
2.2 DESCRIPTION
These editorial changes revise the USAR sections listed.These changes revise various system logic diagrams, the plant master one"line diagram, and var-ious USAR pages which were inadvertently deleted.These changes are editorial in nature and have no im-pact on plant safety and, therefore, do not consti-tute an unreviewed safety question.5036-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.:~~89-035 SYSTEM USAR SECTIONS AFFECTED: NA Page 3B-ll;Table 3B-7;Figure.3B-1, Sheet 2;and Figure 3B-2, Sheet 2 DESCRIPTION:
Editorial typographical and/or clarification changes have been made to the above USAR pages, table, and figures.These changes were made to correct the'ex-isting USAR so that it is consistent with the design calculations.
This modification does not involve the plant design basis, procedures, or analyses and does not constitute an unreviewed safety question.5035-176720183"HC4
Attachment 8 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
89-038 Revisions to USAR Table 9.4-1 NA USAR Table 9.4-1, pages 1, 2, and 3 This SER documents changes to USAR Table 9.4-1.The foot-note describing the design basis for maximum indoor tem-peratures for safety-related equipment was expanded to include"and the summer outdoor'design maximum temperature of 100'F dry bulb and 73'F wet bulb." Added"cable chases and corridors" under the control building el 261 ft as a separate area on page 1 of the table to reflect the in-crease from 104'F to 110'F inside design maximum tempera-ture for these areas.The increase in indoor temperature is a result of using the higher outdoor air temperature as a design basis.These changes provide greater flexibility for plant opera-tion by revising acceptable temperature ranges.The in-crease in the plant outside air design temperature from.93'F to 100'F provides reasonable assurance that the out-door ambient temperature will not result in a plant shut-down in the future.This change will not increase the probability of equipment malfunction or failure, since the safety-related equipment located in the control building el 261 ft cable chases and corridors are qualified for the ambient conditions which were revised from 104'F to 110'F.These changes have no impact on plant safety and therefore do not constitute an unreviewed safety question.5053-176720183"HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM'SAR SECTIONS AFFECTED: DESCRIPTION:
89-039 Miscellaneous Changes to the USAR NA Figures 9.2-7 (Sheet 9)and 11.4-1a In order to eliminate a nuisance alarm caused by high ambient temperatures, the water treatment system caustic storage tank high temperature switch setpoint was increased from 80'F to 90'F, (Figure 9.2-7, Sheet 9).At this new setting, the high temperature switch will continue to perform its design function which is to provide indication of overheating by the tank's plate heating coil.Two radioactive solid waste system check valve sym-bols were revised from"socket weld" to"flanged" end connections as the result of a change in valve type (piston check to swing check).The change was made to minimize the potential for valve failure due to particles present in the system fluid and to facili-tate valve removal for maintenance.
The design func-tion of these valves remains unchanged.
These changes are within the design basis of the plant and do not affect any safety functions or anal-ysis, and therefore do not constitute an unreviewed safety question.5063-176720183-HC4 0 0 Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: 89-040 Update to USAR Failure Modes and Effects Analysis (FMEA)Volumes 1 and 2 to April 1989 As-Built Design Level SYSTEM: USAR SECTIONS AFFECTED: Various Safety-Related Systems Failure Modes and Effects Analysis (FMEA)Volumes 1 and 2 DESCRIPTION:
Changes were made as follows to the USAR for the FMEA which has been updated to the as-built design level, effective April 30, 1989.Sections 4 and 5 of FMEA, Volume 1, have been changed to reflect the updated FMEA.This change includes editorial corrections, clarifications, an'pdated list of reference documents, and a description of findings with resolutions.
Appendixes A and B in FMEA, Volumes 1 and 2, have had sections replaced by new printouts reflecting the update to t;he April 30, 1989, as-built design level.The FMEA demonstrates NMP2 BOP, BOP/NSSS interface, electrical power supply and distribution systems com-pliance with the single-failure criterion as required by IEEE 279-1971 and IEEE 308-1978.Therefore, these changes to the USAR do not consti-tute an unreviewed safety question.5108-176720183"HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: 89.-049 Editorial Changes to USAR Section 11.4 Regarding Low Specific Activity (LSA)Material SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
Solid'Waste Management System Section 11.4.These editorial changes to the USAR , text and Table 11.4-1 are made to correct editorial discrep-ancies that were identified in the review of the USAR Revision 0 update.These are editorial changes not affecting plant design or procedures and, therefore, do not constitute an unreviewed safety question.5120-176720183'"HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER No.: 89"050 SER TITLE: Revision to HPCS Diesel Generator Cooling System Logic SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
HPCS Diesel Generator Cooling Figure 9.5-41, Sheet 8 of ll USAR Figure 9.5-41, Sheet 8 of ll, has been revised to change the setpoint for the diesel generator cool-ing water low pressure, the time delays for this alarm and the logic which depicts the alarm function.These changes have no adverse impact on plant safety and reflect the as-built design of the plant.There-fore, they do not constitute an unreviewed safety question.5124-176720183-HC4
SAFETY EVALUATION REPORT SUNMARY SER No.: 89-055, Rev.1 SER Title: Resolution of General Items and Typographical Errors for Updated SAR, Revision 1 System: N/A FSAR Sections Affected: P 12.5-1, P 12.5-4, P 7.1-7a, 6.2-55b, 8.3-8, 8.3-9, T 12.5-1, P 6.2-88a, 15.6-13, T 15.7-5, 15.7-16, Sh.1, 15.7-17, Sh.1, F 10.1-5d, 5.4-13d, 6.2-70, Sh, 34, T 15.0-1, Sh.1, 15.0-1, Sh.2, 15.0-1, Sh.3, P 2.4-22, F 9.3-1c, 9.3-1g, T 6A.9-1, 9.4-1, Sh.3, 15.6-13, Sh.9, P 9A,3-42a, T 9A.3-5, 9A.3-10, Sh.1, 98.8-2, Sh.38b, P 2.5-171, 3.9A-14, 6.2-43a, 6.2-53, T 6.2-54, P 9.5-27, T 3.9A-12, Sh.17, T 6.2-55C, Sh.1
Description:
This evaluation addresses omissions, unintentional additions, typographical errors, printing errors and resolution of comments that resulted from Revision 0 of the Updated Safety Analysis Report (USAR).These changes, do not affect the design basis or the safe operation or shutdown of the plant.Therefore,'this does not constitute an unreviewed safety question...
(7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER Ho.: 89-056 SER Title: USAR Fire Protection Update.System: F,ire Protection FSAR Sections Affected: P9A-iii, 9A.3-4, 9.5-7, 9A.3-7a, 9A.3-8, 9A.3-10, 9A.3-17, 9A.3-42, T9A.3-4, Sh.2, 9A.3-4, Sh.4, 9A.3-4, Sh.5, 9A.3-4, Sh.3, 9A.3-1, Sh.2, 9A.3-1, Sh.3, 9A.3-2, Sh.2, 9A.3-3, Sh.1, 9A.3-4, Sh.6, 9A.3-6, Sh.2, 9A.3-6, Sh.3, 9A.3-6, Sh.4, 9A.3-8, Sh.2, 9A.3-9, Sh.9A.3-9, Sh.2, 9A.3-9, Sh.3, 9A.3-10, Sh.1, 9A.3-19, F9A.3-1
Description:
TIO"s evaluation documents the revisions necessary to the USAR to reflect the source documents used in establishing,and maintaining the fire protection systems as required.The revisions to the USAR dfd not require physical changes to the plant and do not adversely affect the safe shutdown or fire protection analysis<Appendix R).Therefore, these changes do not.constitute an unreviewed safety question.<7858G)
SAFETY EVALUATION REPORT
SUMMARY
SER No.: 89-058 SER Title: USAR Fire Protection Update System: Fire Protection FSAR Sections Affected: P 9A.3-16, 9A.3-17, 9A.3-40, 9A.3-41, 9A.3-4la, 9A.3-4lb, 9A.3-52
Description:
This evaluation documents revisions necessary to the USAR to reflect the source documents used in establishing and maintaining the fire protection systems as required.The revisions to the USAR did not require physical changes to the plant and do not adversely affect the safe shutdown or fire protectionmnalysis (Appendix R).Therefore, these changes do not constitute an unreviewed safety question.(7858G)
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: USAR SECTIONS AFFECTED: 88U-300, Revision 1 Editorial Changes to the USAR NA Section 10.4.6.2.2 and Figures 6.2-70, Sheet 1, and 9.4-1C DESCRIPTION:
These changes are made to the USAR section and fig-ures to establish consistency with previously issued USAR changes.(LDCNs)that are addressed by Safety Evaluation (SE)Nos.87-007, 88U"129, and 88U-282.Since these changes are being made for consistency with previously issued LDCNs that are addressed by SEs, they are editorial and do not affect the plant design or procedures.
Therefore, they do not consti-tute an unreviewed safety question.4479-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.SER TITLE: SYSTEM: 88U-301 Turbine Trip Transient Analysis NA USAR SECTIONS AFFECTED: Section 15.2.3.
2.1 DESCRIPTION
This change revises USAR Section 1S.2.3.2.1 to include the results of the Turbine Trip Transient Analysis considering the unavailability of feed" water system flow to the reactor vessel immediately following the trip.The event results show the existing USAR analysis is bounding.There-fore, this change does not constitute an unreviewed safety question.4449-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO~: SER TITLE: SYSTEM: 88U-302, Revision 1 Editorial Changes to the USAR NA USAR SECTIONS AFFECTED: Sections 6.2.3.4, 7.3.2.1.3, 7.4.2.2.4, 7.6.2.4.4, and 14.2.7;Tables 1.6-1, Sheet 7, and 1.8"1, Sheets 64 and 161;page 11.4-3a The following editorial changes were made to the USAR Section and tables noted: 1.USAR section cross<<references were added.2.Additional reference documents were added.3.Clarifications were added to distinguish test personnel qualifications during plant design, construction, testing, and operation phases.4.Revised reference documents and made editorial changes.These were editorial changes not affecting plant design or procedures and therefore do not constitute an unreviewed safety question.5119-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT CHANGE DESCRIPTION SER NO.!SER TITLE: SYSTEM: FSAR SECTIONS AFFECTED: DESCRIPTION:
88U-304, Revision 1 USAR Text Clarifications NA Figure 7.3-10, Sheet 1 of 2;Page 1.10-61;Page 15E.3-4;Page 15E.3-6;Table 7.3"17, 15 of 16;Table 7.3-17, 16 of 16;Page 7.7-9;Page 9.5-8;Page 4A-1;Page 3.9B-13;Page 8.2-22 Editorial and typographical changes vere made to the above pages, tables, and figures.These types of, changes are considered necessary to accurately represent the actual design of the plant.There is no impact to plant design basis, physical arrangement, or procedures and thus these changes do not represent an unreviewed safety question.5006-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO,: SER TITLE: 88U-'05 Update of Radiation Source, Term and Dose Rate Tables in USAR Chapters 12 and 15 SYSTEM: USAR SECTIONS AFFECTED: Radiation Sources Tables 12.2-4, Sheet 3;12.2-6, Sheet 1;12.2-7, Sheet 2;12.2.-9;12.2-10, Sheets 1, 2, 3;12.2-12, Sheets 1, 2, 3;12.2-13, Sheets 1 and 2;12.3-4, Sheets 1'and 2;15.7-10 DESCRIPTION:
Changes were made as follows to the USAR for radia-tion sources.The RWCU source term was revised to accurately reflect those used in radiological anal-yses and the supporting radiation protection source calculation', the title of Table 12.2-6 is changed to accurately reflect the content of the table;spent fuel pool cooling and cleanup system source activi-ties were revised to include isotopes previously neglected; The N-16 activities in equipment in the turbine building are revised to be'onsistent with-the supporting radiological analyses and calculation; the condensate system source term, liquid radwaste system components activities, and solid radwaste system components activities are all revised to pro-vide consistency with the supporting radiological calculations; the post-LOCA gamma dose rates in Table 12.3-4 are revised to make them consistent with radiological calculations; and the airborne activity in the reactor building due to a fuel handling accident is revised to correct a typographical error in the I-135 isotopic activity.This modification does not involve the plant design basis, procedures, or analyses results, and does not constitute an unreviewed safety question.4475-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
88U-306 Residual Heat Removal System Modifications Residual Heat Removal (RHR)Figure 5.4-14, Sheet 3 This change revises the design pressure and temperature of certain por-tions of the residual heat removal system (RHS).These changes are con-sistent with plant system design documents and reflect maximum anticipa-ted operating conditions.
The revised conditions are within the design capabilities of-the RHS piping and components and do not impact the physical design of the RHS system.Therefore, this change does not constitute an unreviewed safety question.4491-116720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO~: SER TITLE: SYSTEM: 88U"308 Editorial Changes to the USAR Standby Diesel Generator Fuel Oil Storage and Transfer System (EGF);Equipment Qualification USAR SECTIONS AFFECTED: Figures 9.5-40b, 9.5-41, Sheet 2 of 11~, and pages 3.11-4 and 3.11-7 DESCRIPTION:
This evaluation addresses the editorial and clarifica-tions for the USAR update.These changes update the USAR, and do not change/modify any structure, system, component, test or experiment.
The review concluded that the changes do not constitute any unreviewed safety questions.
- Changed in Revision 0.5020-.176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO~.'ER TITLE: 88U-309 USAR Table 8.3-4 Update SYSTEM'SAR SECTIONS AFFECTED: Safety-Related Electrical Loads Table 8.3-4, Sheets 1 and 30 DESCRIPTION:
This modification describes'a change to USAR Table 8.3-4 to agree with the plant as-built conditions for the Class 1E safety-related loads.The change in-volved revision of the locked rotor current of unit coolers 2HVC*UC108A and B from 84.0 to 64.3 amperes.5019-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: 88U-310 USAR TABLE 7'-3 UPDATE SYSTEM: LEAK DETECTION SYSTEM USAR SECTIONS AFFECTED: TABLE 7.6-3, Sheet 2 DESCRIPTION:
This modification describes a change to USAR Table 7.6-3, page 2 of 2, to agree with the plant as"built conditions for the range of temperature switches E31"N622A and B.The change involved revision of the instrument"range from"0-350'F" to"50-350'F." Also, footnote (1)was editorially revised to read from"Chapter 16" to"the.Technical Specifications." 5032-176720183-HC4
SAFETY EVALUATION REPORT
SUMMARY
Attachment 4 SER NO.: TITLE: SYSTEM: 88U-311 Editorial Changes to the USAR Service Water System FSAR SECTIONS.AFFECTED: Tables 9.2-1A, Sheets 1, 5, and 6;9.2-1B, Sheets 1 and 5;and 9.2-2, Sheets 1, 5, and 9'ESCRIPTION:
These changes to the USAR tables are a result of an editorial omission discovered during the review of SER 88U-014, Revision 0, Service Water System Modifi-cations.The change to the service water flow re-quirements made in the affected tables is consistent with the change described on SER 88U-014 to provide continuous flow to four of the safety-related unit coolers serving the residual heat removal and low pressure core spray pump rooms.Therefore, these-changes update the USAR tables to incorporate a previously approved plant modification.
The review concluded that the changes do not constitute any unreviewed safety questions, 5018-176720183-HC4
Attachment 5 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: 88U-312 Instrument Line Break and Spent Fuel Cask Drop Accident: Anal ys i s SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
NA Section 15.7.5, Tables 15.6-1, Sheet 2, and 15.6-4 USAR Table 15.6-4 is revised to incorporate changes in Instrument Line Break, EAB, LPZ, and Control Room doses due to a revision of the source calculation.
A typo-graphical:
error in Table 15.6-1 is corrected.
Sec-tion 15.7.5 is revised to correct the amount of I-131 released to the environments This modification does not involve the plant design basis or procedures.
It does not adversely affect plant accident analyses, and therefore, does not constitute an unreviewed safety question.5010-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: FSAR SECTIONS AFFECTED: DESCRIPTION:
88U-313 USAR Miscellaneous Changes NA Page 1.10-80;Table 11.1-5;Table 6A.10-7;Figures 6A.10-11, 6A.10-12, and 6A.10-13;Figure 6.5-1, Sheet 8;Page 12.1-8, and Table 6.2"56, Sheet 2 Editorial and/or clarification changes have been made to the above affected USAR pages, tables, and fig-ures, including changes to equipment designatio'ns, radiological source terms, and suppression pool'thermal analysis.The changes do not revise the plant design, procedures, or results of analyses and therefore do not constitute an unreviewed safety question.5045-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
88U-314 Revision to Reactor Vessel Skirt Ambient Temperature NA Table 14.2-301, Sheet 2 This change revises USAR Table 14.2-301 to update the reactor vessel skirt ambient temperature to be in agreement with the General Electric design basis.This change does not impact any design basis analyses and is consistent with the NSSS providers design cri-teria.Therefore, this change does not constitute an unreviewed safety question.5014-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM!USAR SECTIONS AFFECTED: 88U-316 Editorial Changes to the USAR NA Sections 8.3.2.1.2, 9.5.6.2.2.3, and 9.5.6.5;Table 3.9A-12, Sheet 4;and Figures 6.2-72K, Sheet 1 and 6.2-83 DESCRIPTION:
These editorial changes to the USAR text, table, and figures are per-formed to correct certain editorial discrepancies that were identified as a result of reviewing the USAR Revision 0 update.These are editorial changes not affecting plant design or procedures and therefore do not constitute an unreviewed safety question.5012-176720183"HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER No.: 88U"317 SER TITLE: Revision to Reactor Building Closed Loop Cooling Water Logic Diagram SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
Reactor Building Closed Loop Cooling Water Figure 9.2-4, Sheets 1 of 12, 3 of 12, and 11*of 12 These changes revise the USAR figures listed to re-vise the reactor building closed loop cooling water low suction pressure setpoint to provide improved operational flexibility, add a note that the reactor recirculation pumps cooler outlet valves have been rendered nonfunctional to reflect a change in cooling philosophy at the coolers'n addition, the instru-ment air compressor, water expansion tank level set-point has been revised.These changes do not affect.any safety analysis or safety functions, and there-fore do not constitute an unreviewed safety question.*Changed in Revision 0 5044-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
88U-318 Editorial Revision to USAR Figure 9.4-17 Miscellaneous Buildings HVAC Systems (HVY)Figure 9.4-17, Sheet 3 The changes to USAR Figure 9.4"17, Sheet 3 are the result of an inadvertent omission relating to changes previously addressed on SER 88U-118.Note 2 on USAR Figure 9.4-17 (Sheet 3)was revised to remove the demineralized water storage tank building and add the chiller building to agree with the logic shown and the related text description in USAR Sec-tion 9.4.7.5 (page 9.4-56)which was previously revised by LDCNs U-515 and U-808 and addressed in SER 88U-118.These changes are editorial in nature and have no"impact on plant safety and therefore do not constitute an unreviewed safety question.5041-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: 88U-319 USAR Text Clarification SYSTEM: Various USAR SECTIONS AFFECTED: DESCRIPTION:
Figure 9.4-2b;Figure 9.4-17, Sheets 1 of 13 and 2 of 13;Table 1.9-1, page 7 of 11 Editorial and/or clarification changes have been made to the above affected USAR sections.These changes were made to enhance the existing USAR so that it is consistent with design drawings and procurement spe-cifications.
Also, a compliance statement, which was inadvertently omitted, has been added to Table 1.9 to address NRC Standard Review Plan 9.1.2, Spent Fuel Storage.This change does not involve any hardware, analysis, or procedure modification and does not constitute an unreviewed safety question.5051-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: 88U"321 USAR Figure 8.3-7, Editorial Update Reactor Protection System USAR SECTIONS AFFECTED: DESCRIPTION:
Figure 8.3-7 dated April 1989 Changes have been made to the above-affected USAR sections regarding the circuit breaker trip ratings for the reactor protection system.These changes make the RPS overcurrent protection consistent with the as-built loads and were made to correct the existing USAR so that it is consistent with design drawings and procurement specifications.
This change does not involve any hardware or procedure modifica-tion and does not constitute an unreviewed safety question.5065"176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER No.: SER TITLE: SYSTEM: 88U-322 Miscellaneous PID Changes Control Rod Drive System USAR SECTIONS AFFECTED: Figures 4.6-5a, 9.4-3d, 9.3-5e, 9.3-5j DESCRIPTION:
This change deletes a pressure switch, 2RDS-PS105, which has not been installed and was never intended for use at NMP2.In addition, editorial changes to continuation flags have been made.These changes have no adverse impact on plant safety and therefore do not constitute an unreviewed safety question.5081-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
88U-324 Editorial Change to USAR Figure 9.3-12d Miscellaneous Drains (DFM)Figure 9.3-12d This change to USAR Figure 9.3-12d is the result of an inadvertent omission'n the engineering change document initiated to revise this figure's source document.This change to the screenwell building miscellaneous drain system sump pump performance is in agreement with the change described in Safety Evaluation 87-121, which evaluated the replacement of these pumps to accommodate the water flow into the associated sumps.Therefore, this change to update USAR Figure 9.3-12d incorporates a previously ap-proved plant modification.
The review concluded that the change does not constitut'e any unreviewed safety questions.
5104"176720183-HC4
Attachment 4SER NO.: SER TITLE: SAFETY EVALUATION REPORT
SUMMARY
88U-325 Miscellaneous Changes to USAR Figures SYSTEM'A'SAR FIGURES AFFECTED DESCRIPTION:
6.2-70 (Sheets 15, 27, 29, 37, and 41)9.2"7 (Sheet 9 of 12), and 9.3"10c.This safety evaluation addresses changes to.USAR Figures'or the primary containment isolation valve arrangements, turbine building drains, and the demineralized makeup water system logic diagram.The changes described are the result of identifying clar-ifications and editorial revisions.
The review concluded that the changes do not constitute any unreviewed safety questions.
5121-176720183-HC4
Attachment 4 SAFETY EVALUATION REPORT
SUMMARY
SER NO.: SER TITLE: SYSTEM: 88U-326 USAR Table 7.5-1 Update Service Water System USAR SECTIONS AFFECTED: Table 7;5-1, Sheets 1 and 6 DESCRIPTION:
Changes to USAR Table 7.5-1 have been made to update the USAR in order to be consistent with design drawings and specifications and NMP2 licensing commitments.
This change does not involve any hardware or procedure modifi-cation and does not constitute an unreviewed safety question.5125"176720183-HC4 0
(18~11~lid: al bKW (.'HJC 44RS M 814Attachment 4 SAFETY EVhWATION REPORT
SUMMARY
SER No.SER TZTLB: SYSTEM: USAR SECTIONS AFFECTED: DESCRIPTION:
88U-328 Editorial Changes to VSAR Section 6.2,5,5 Hydrogen Control System USAR Section 6.2.5.5 This change deletes a statement describing the operation of the control svitoh for the hydrogen recombkner cooling eater strainer blovdom valves.This change is editorial in natura and has no adverse imPact on ylant safety and therefore does.not constitute an unrevised safety question.
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