ML20117E625
| ML20117E625 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 05/31/1996 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20117E624 | List: |
| References | |
| REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NUDOCS 9605160271 | |
| Download: ML20117E625 (204) | |
Text
{{#Wiki_filter:. _ - . ._ . _ _ _ _ _ _ _ _ _ _ _ _ .- _ _ l rO I i l l l l l SEISMIC SAFE SHUTDOWN EQUIPMENT LIST , FOR PEACH BOTTOM ATOMIC POWER STATION UNITS 2 AND 3 IN RESPONSE TO: NRC Generic Letter 87-02/USl A-46 l VERIFICATION OF SEISMIC ADEQUACY OF MECHANICAL l AND ELECTR! CAL EQUIPMENT IN OPERATING REACTORS i PECO ENERGY COMPANY l l l I O 9605160271 960507 PDR ADOCK 05000277 P PDR
l SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 .
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TABLE OF CONTENTS f SECTION PAGE
1.0 INTRODUCTION
1 1 2.0 SCOPE / METHOD 1 3.0 ASSUMPTIONS / LIMITATIONS 2 3.1 GENERAL ASSUMPTIONS AND LIMITATIONS 2 3.2 REACTIVITY CONTROL ASSUMPTIONS 4 3.3 REACTOR COOLANT PRESSURE CONTROL ASSUMPTIONS 4 3.4 REACTOR COOLANT INVENTORY CONTROL ASSUMPTIONS 4 3.5 DECAY HEAT REMOVAL ASSUMPTIONS 5 3.6 SUPPORT SYSTEMS ASSUMPTIONS 6 4.0 SAFE SHUTDOWN PATH 8 4.1 SAFE SHUTDOWN FUNCTIONS 9 4.2 SAFE SHUTDOWN EQUIPMENT LIST 16 4.3 OPERATIONS REVIEW OF SSEL 17
5.0 REFERENCES
18 ATTACHMENT I A. HIGHLIGHTED P&lD'S B. SAFE SHUTDOWN EQUIPMENT LIST l C. PLANT OPERATING PROCEDURES )
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I i SEISMIC SAFE SHUTDOWN EQUIPRE!NT LIST FOR PBAPS UNITS 2 AND 3 O
1.0 INTRODUCTION
The Seismic Safe Shutdown Equipment List (SSEL) was prepared in accordance with the Generic Implementation Procedure (GIP) Revision 2 . (ref. 5.2). This report presents .the systems analysis and component ! selection process for the SSEL and the SSEL itself. I There were no significant or programmatic deviations from the GIP in preparation of the SSEL.- 2.0 SCOPE / METHOD l Safe shutdown for the A-46 analysis is defined as bringing the plant to and l maintaining it in a hot shutdown condMion during the first 72 hours following i a seismic event. No other extraordinary events are assumed to occur. In selecting the paths that could be used to conduct a safe. shutdown, Emergency Operating Procedures and special event procedures for Peach Bottom were reviewed along with the shutdown methods identified in the Peach Bottom Fire Protection Program (ref. 5.5). As a result, the path selected is similar to those used to shut down the plant in the event of a fire O or other emergencies. The basic principle used to select the seismic safe shutdown path and SSEL components is a safety classification approach with the application of the criteria established in SOUG GlP and the EPRI Report NP-6041-SL - (ref. 5.1). As allowed for in both documents components selected for use in performing a safe shutdown may include non-safety grade equipment. This basic approach assures that the components selected are the minimum required to shut down the reactor, maintain the integrity of the Reactor Coolant System (RCS) pressure boundary, and maintain it in a safe shutdown condition. Technical input (e.g., P&lDs, and procedures) for developing the safe shutdown path had a freeze date of November 1,1992. This date was chosen in order to collect the required documentation needed for the reviews and walkdowns. Seismic walkdowns were performed beginning in July,1993. Components accessible only during outages were inspected during refueling and other. unit outages. The results of the walkdowns by the Seismic Review Team (SRT) are a snapshot in time. Where review of the walkdown results indicated an area of concern, current documentation was reviewed to confirm the walkdown conclusion. O Page 1
SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 O# Four safe shutdown functions were chosen as the basis for developing the SSEL. They are reactivity control, reactor inventory control, reactor l pressure control and decay heat removal (DHR). From these functions a l success path logic diagram (SPLD) was developed. In developing the SSEL, if achieving and maintaining a safe shutdown function is dependent ) on a single item of equipment whose failure would fail the safe shutdown i l function, an alternate path using a different train or a different item of j equipment was included on the SSEL. . 3.0 ASSUMPTIONS / LIMITATIONS l l Assumptions used in identifying the safe shutdown success path and I generating the composite SSEL are described below. General assumptions are provided first followed by those specific to each safe shutdown function. 3.1 General Assumptions and Limitations l 3.1.1 Offsite power is assumed to be lost due to the seismic event and to be j unrecoverable during the 72 hour time period following the earthquake. In l the relay analysis, offsite power was considered available if it hindered the i safe shutdown of the plant. O 3.1.2 No other accidents or extraordinary events (i.e., fire, HELB) are postulated to occur concurrent with the seismic event or during the 72 hour period following the earthquake. 3.1.3 The plant will be brought from normal operating conditions to a safe shutdown condition. At the beginning of the event, the plant (both units) is assumed to be at 100% power at rated temperature and pressure. 3.1.4 Only instrumentation that is necessary to control and monitor safe shutdown functions or equipment will be included on the SSEL. 3.1.5 Manual operator actions are a means of providing redundancy for a component provided there is sufficient manpower and time to perform the action (refs. 5.1 and 5.2, Sect. 3). 3.1.6 Self actuated check valves do not require a seismic evaluation and are considered as passive components. However, they are included on the SSEL if credited as a boundary interface for the success path. iO
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g SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 ' " . V 3.1.7 Heat exchangers and tanks are considered passive components for the i purposes of this review. These particular components are not required to change state to accomplish their safe shutdown function, but are required , to be identified for review of seismic adequacy. 3.1.8 The effects of spurious actuation of safety signals (i.e., isolation signals) have been considered for negative impact (e.g., boundaries, water sources) on the operation of the USI A-46 safe shutdown path and/or equipment. That is, if a spurious safety signal could cause an inadvertent component ' actuation which would violate a boundary or adversely impact a water . source, the component was included on the SSEL. , 3.1.9 A valve indicated as locked open or closed on a P&lD is assumed to be physically impeded from changing state (i.e., prevented from opening or , closing due to being wired in position, breaker racked out, etc.). 3.1.10 The normal position assumed for a valve is as indicated on the respective system's P&lD. For air and electrically operated valves with a system operating mode dependence, the initial position is assumed to be other than that required to support the safe shutdown path. These valves are considered active. Manual valves are assumed to change position only by O operator action. 3.1.11 Relief valves that are credited for providing over-pressure protection of a safe shutdown path are considered to be passive. Because of the number of such valves, they have not been included on the SSEL. Only those relief valves which may be challenged (i.e., become active) as a result of a i transient during the recovery from the earthquake are included on the l SSEL. I 1 3.1.12 If a flow diversion path contains two (2) normally closed valves, only one of the valves needs to be included on the SSEL If the valves are power operated (e.g., MOV, AOV) the selected valve has been reviewed to ensure that relay chatter does not open the valve. No other spurious operation needs to be considered for the valve. 3.1.13 Automatic initiation of equipment is assumed when available. Manual initiation is assumed to occur if automatic initiation fails. O Page 3
SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 0 3.2 Reactivity Control Assumptions 3.2.1 The Control Rod Drive (CRD) system is required and is sufficient to achieve and maintain reactivity control, even with a stuck control rod, during and following an earthquake. Therefore, the Standby Liquid Control (SLC) system is not considered an essential safe shutdown system and has not been included on the SSEL (ref. 5.11). 3.2.2 The scram discharge volume vent and drain valves are required to be shut to minimize potential radioactive discharge to the Reactor Building drains. The function of these valves supports both reactivity and inventory control. 3.2.3 The scram discharge volume is not included on the SSEL since it is considered a passive component (pipe). 3.2.4 The individual components which comprise the hydraulic control units (HCUs), (e.g., scram pilot valves, SOV, cylinders), are not included on the SSEL since they were evaluated with the HCU as a whole. 3.2.5 The Reactor Protection System is considered to be fail safe, and no failure p of a single component is capable of preventing a scram signal. V 3.3 Reactor Pressure Control Assumptions 3.3.1 The main steam safety relief valves (SRVs) are considered the primary and attemate paths for reactor overpressure control. All SRVs (RV-71 A through RV-71 L) were included on the SSEL to ensure that sufficient and redundant relief capacity was available for reactor coolant pressure control. 3.3.2 The SRVs which perform the Automatic Depressurization System (ADS) function are also considered the primary and alternate paths for reactor depressurization since they have accumulators (ref. 5.6). The ADS SRV accumulators are required for cycling the valves in the event instrument , nitrogen is not available. Nitrogen bottles outside the drywell were included on the SSEL to provide for valve cycling if necessary using manual operator action. 3.4 Reactor Coolant Inventory Control Assumptions 3.4.1 The HPCI or LPCI system are assumed to be capable of maintaining RPV inventory. O Page 4
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4 SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 0 3.4.2 Only one of the four RHR pumps (operating in the LPCI mode) is required to maintain reactor vessel level. Conservatively, all four pumps are provided on the SSEL to account for a single active failure and provide redundancy. 3.4.3 RHR pump minimum bypass flow valves remain open to protect the pumps :
'at shutoff head operations. This bypass flow diversion back to the Torus will not adversely impact make-up flow to the reactor.
3.4.4 The HPCI control oil system (including the auxiliary lube oil pump) for the HPCI turbine is required to start the HPCI system. , 3.4.5 Because of the numerous flow diversion paths leading from the Condensate Storage Tank (CST) and the seismic vulnerability of the tank, the CST has not been included on the SSEL. The Torus is considered the primary . source of water for makeup. However, if available, the CST could be ' utilized. 3.4.6 The Torus is the only source of water injection required to bring the plant to a stable shutdown condition. Components required to ensure an automatic transfer of water sources for HPCI from the CST to suppression O pool (i.e. level transmitters, etc.) have been included.on the SSEL to eliminate reliance on operator action. 3.5 Decay Heat Removal Assumptions 3.5.1 The Torus Cooling mode of operation, utilizing High Pressure Service Water (HPSW) through the RHR heat exchanger, will be used to remove decay heat transferred to the Torus. 3.5.2 The Alternate Shutdown Cooling mode of RHR operation will be used to remove decay heat from the reactor by filling the reactor and main steam lines with water and returning it to the suppression pool through an open SRV. 3.5.3 The Torus Cooling mode of operation is used to reduce the temperature in the Torus (if a LPCI initiation signal is not present). RHR can be in the LPCI mode on one train and in the Torus Cooling mode on the other train. 3.5.4 The SRTidentified that the dams upstream and downstream of PBAPS may not be easily qualified for the design earthquake. As a result, the availability of the Conowingo Pond as a heat sink cannot be assured so the Emergency Cooling Tower and associated components have been included O on the SSEL. Page 5
l SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 l l 3.6 SUDDort Systems AssumDtions 3.6.1 Emergency Diesel Generator , it is assumed that the plant conditions (i.e. LOOP caused by the ! earthquake) will cause the operator to manually start the EDG if it hasn't l started automatically. 3.6.1.1 The Diesel Oil Storage Tank together with the Diesel Generator Fuel Oil l Day Tank for each Diesel Generator will provide sufficient fuel oil for 72
- hours of diesel operation.
! 3.6.1.2 The station battery for each diesel generator unit is required to support the' operation of its respective diesel generator. A station battery is required to support the operation of a diesel generator both during engine startup and during diesel generator operation. l 3.6.2 Emergency Service Water System 3.6.2.1 The Emergency Service Water (ESW) System is required to ensure that cooling to each Emergency Diesel Generator is provided. In addition, all four diesel generators can be supplied by one ESW pump. l 3.6.2.2 The ESW System is required to provide cooling water to the RHR pump i seal coolers and the HVAC cooling coils in the HPCI and RHR Pump Rooms. 3.6.2.3 Only one of the two ESW pumps is required to support a two unit shutdown. 3.6.2.4 Only one of the two emergency service water booster pumps is required if ESW is in the recirculation mode to the Emergency Cooling Tower. 3.6.2.5 No instrumentation has been provided on the SSEL to monitor ESW System operation. System operation can be determined based on supported system performance and equipment observation. 3.6.2.6 Safety relief valves for individual heat exchangers in the ESW system are ' not considered to be required for over-pressure protection and are not i included on the SSEL. 4 U Page 6
l SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 O 3.6.2.7 in order to support the operation of the Diesel Generators, the Emergency i Service Water pumps will need to " auto start". This feature has been I accounted for in the relay review for the ESW pumps. 3.6.3 High Pressure Service Water 3.6.3.1 The High Pressure Service Water (HPSW) System is required to ensure , that cooling to each RHR heat exchanger for Suppression Pool Cooling and l Alternate Shutdown Cooling is provided. j 3.6.3.2 For HPSW System operation, only one of the two pumps in each train will ; be required to provide adequate flow to the associated RHR heat i exchangers. However, both pumps are included on the SSEL to provide for ! redundancy. l 3.6.3.3 No instrumentation has been provided on the SSEL to monitor HPSW System operation. System operation can be determined based on i suppoited system performance. 3.6.3.4 HPSW valves MO-32-2344(3344), loops A and B crossties may need to be opened under certain operating scenarios. Therefore, they have been O included on the SSEL. 3.6.4 Electrical Distribution System 3.6.4.1 The station batteries will be relied on to provide essential 120V AC inverter loads and 125V DC loads necessary for the short period of time following an earthquake until the Emergency Diesel Generators have re-energized the battery chargers. 3.6.4.2 The AC power supply transfer switches for the 125V DC battery chargers have not been included on the SSEL for the following reasons: They do not contain any relays or contacts for which a relay review would be required. Switches are manually operated with no automatic transfer capability. 1 No operator action will be required to transfer AC power supply to i the battery charger since the atternate power supply will not be l required. I 3.6.4.3 The loss of an Emergency Diesel Generator may require the back feeding ! of emergency busses. Operator actions to perform this function currently exist in PBAPS Special Event Procedure SE-11, " Loss of Offsite Power" O Page 7
a SElSMIC SAFE SHUTDOWN EQUlPMENT LIST FOR PBAPS UNITS 2 AND 3 : i i l (ref. 6.7.2). 3.6.5 HVAC 3.6.5.1 The ventilation supply fan for each of the Diesel Generator rooms will be ! required when its respective diesel is operating to provide a source of ! combustion air and maintain the room's temperature within acceptable limits. The supplemental supply fan for each of the rooms is included on the SSEL to provide back-up to the main fan. 3.6.5.2 Upon a loss of Control Room HVAC, it may be necessary to open doors to some Control Room panels in order to provide adequate cooling for some components located in these panels. Direction for this is provided in procedure ON-115. 3.6.5.3 The ventilation systems for the Switchgear and Battery Rooms will be required in order to support the operation of safe shutdown equipment in those spaces. 3.6.5.4 The ventilation for the pumphouse is necessary to support continuous operation of the HPSW and ESW pumps. 3.6.6 instrument Air Syetem 3.6.6.1 The instrument air system is assumed to fail following the SSE due to the loss of offsite power. The failure position of air operated valves within the ! various systems have been considered for this report and reflected in the
" Required State" field on the SSEL.
3.6.6.2 Components (solenoid valves, air bottles, etc.) for pneumatic valves on the SSEL that fail in a safe condition upon loss of air have not been included on the SSEL. 4.0 SAFE SHUTDOWN PATH The various combinations of systems that provide the four seismic safe shutdown functions form the set of possible success paths. A seismic safe shutdown path was chosen from these possibilities and is based on the PBAPS Appendix R safe shutdown methodology. This p in 's briefly described below and shown in Figure 4.0-1.
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SEISMIC SAFE SHUTDOWN EQUlPMENT LIST FOR PBAPS UNITS 2 AND 3 O The preferred method has reactivity control via the control rods, inventory control via HPCI or alternatively ADS and LPCI A or C systems, over pressure control by the SRV valves and decay heat removal by the Torus cooling and alternate shutdown cooling modes of RHR. The following are descriptions of the four safe shutdown functions and chosen systems necessary to safely shut down and maintain the plant in a hot shutdown condition following a seismic event. Where required, more than one component or path is identified in order to accomplish the safe shutdown function. The drawings identified in Section 4.1 are provided in Attachment A. 4.1 Safe Shutdown Functions 4.1.1 Reactivity Control Adequate shutdown margin will be established and maintained by the use l of the control rods. The initial control of reactivity using the control rods and the Hydraulic Control Units (HCUs) is considered capable of surviving individual equipment failures (i.e., failure of an HCU) and no detailed relay chatter review was performed. The actual cause of the control rod insertion ! (i.e., manual or automatic scram) was not considered. The components which comprise the Control Rod Drive and Reactor Protection Systems are : not included on the SSEL. ! l The Low Power Range Monitors (LPRM) provide indication of reactivity l control. Indication of core reactivity and control rod position, requires inclusion of electrical distribution panels 20Y50 and 30Y50 on the SSEL. i These panels will provide alternate power for the full core display, "4 rod" i display, and SRM/lRM. I The paths that can be utilized to ensure reactivity control are shown on the following P&lDs: M-356, SH.1, 2: Control Rod Drive Hydraulic, Part A M-357, SH.1, 2: Control Rod Drive Hydraulic, Part B Page 9
SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 lO l l Seismic Event O 8" *
- 7 8 * * *'
REACTOR SCRAM } REACTIVITYCONTROL ESW > HPSW l AC POWER D R i y , A CONTROL ROD ' INSERTION N2 (For ADS) , the reactoris considered single rNudoarinstrumentagon3' failure proof m to monitor reactor power PRESSURE CONTROL l l SRVs l i Ins n lion INVENTORY CONTROL ! PRIMARY BACK-UP l (Feed into System) I i ADS i l f HPCI l LPCI ( A or C7 . I 1 l ( m )--- l DECAY HEAT REMOVAL ADS l ! l l l l RHR RHR j SPC ASC3 , ! I I ) l Notes:
- 1. ASC : Altemate Shutdown Cooing; TenpS'N SPC : Suppression PoolCooing /
, 2. Instrumentation to monitorthese
' systems is included on the SSEL ist.
- 3. ADS may be required to reach O permissive pressure.
Te M E'Am O V FIGURE 4.0-1 PEACH BOTTOM SAFE SHUTDOWN PATH Page 10 L_
l-ie ! SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 l O 4.1.2 Reactor Coolant Pressure Control ; Reactor vessel overpressure protection for the primary and attemate paths ! is provided by the operation of the main steam safety relief valves (SRVs). This functior'. occurs automatically when reactor pressure reaches the setpoint of each SRV. Operators can manually perform this function by
- opening the ADS SRVs and relieving reactor pressure to the Torus. To depressurize the reactor the ADS System is used. Manual actions associated with connecting backup nitrogen bottles to the ADS SRVs will :
be necessary due to the limited actuations that accumulators can support. All the safety relief valves have been included on the SSEL even though only five may be required to depressurize the RPV. Inclusion of all valves for a seismic review will ensure that sufficient SRVs remain functional. The ; SRV discharge vacuum relief valves prevent drawing suppression pool l water into the SRV discharge lines following termination of blowdown. i Reactor coolant pressure control is monitored using the following ) instrumentation and their associated loops: l Pl2(3)-6-90A O - Pl2(3)-6-90B PR2(3)-6-96 PR2(3)-2-3-404A PR2(3)-2-3-404B The paths utilized for control of the Reactor Coolant System pressure are shown on the following P&lDs: M-351, SH 1,2, 3,4: Nuclear Boiler M 333, SH 1,2 Instrument Nitrogen 4.1.3 . Reactor Coolant inventory Control 4.1.3.1 The inventory of water within the reactor is supplied from the Torus and will j be maintained by the HPCI System or the LPCI mode of the RHR Systems. The HPCI System is the preferred method for ensuring that the reactor core is adequately cooled. The HPCI System will maintain reactor water level when reactor pressure is greater than the RHR pump shutoff head in LPCI mode. HPCI injects water to the reactor via the "A" feedwater line (ref. 5.6). O Page 11
t I SE!SMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 O Drain lines, and their associated control valves, from the HPCI steam line l have not been included as part of the success path. These lines and ; valves are not considered to represent a significant steam diversion path because of the line size and the existence of the steam trap. ; i The alternate method for ensuring that the reactor core is adequately l cooled is through the operation of the ADS and the LPCI mode of the RHR System. The ADS System is required to reduce reactor pressure below the l RHR pump shutoff head. When reactor pressure is reduced below the low pressure permissive, the injection valves can be opened and an RHR pump started to maintain the required reactor water level. The RHR pump (s) will take suction from the Torus and pump water into the reactor vessel using "A" or "C" trains of the RHR System. If both units were in the LPCI mode at the same time, one unit will use the "A" or "C" trains of RHR for LPCI injection while the other unit would use the "B" or "D" trains of RHR for LPCI injection, in the event of a failure of a 4KV safeguards bus, operator actions will be required to alternately operate the RHR System in LPCI injection mode and Torus cooling mode. Existing procedures are in place at PBAPS to perform this function (ref. 5.7.2). Only one of the four RHR pumps per unit are required to maintain reactor O i r i vei t it e i< 8 i vei e#<ie 'eci ePe< tie". so ev <. 'i 'e#< RHR pumps for each unit are provided on the SSEL to account for single active failure and provide additional redundancy. Due to diesel generator loading limitations at PBAPS, only four of the eight RHR pumps can be running at any one time. Reactor water level is monitored using the following instrumentation and their associated loops: Ll2(3)-2-3-85A Ll2(3)-2-3-85B Ll2(3)-2-3-86 LR2(3)-2-3-110A l LR2(3)-2-3-110B l LR2(3)-2-3-113 i The paths that can be utilized to ensure Reactor Coolant System inventory control are shown on the following P&lDs: M-351, SH 1, 2, 3, 4: Nuclear Boiler M-309, SH 1,2: Cond & Refueling Water Storage & Transfer System O Page 12
E i 4 i, SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 M-361, SH 1, 2, 3, 4: Residual Heat Removal M-362, SH 1,2: Core Spray Cooling System M-365, SH 1,2: High Pressure Coolant injection 4 M-366, SH 1,4: HPCI Pump / Turbine Details 4.1.3.2 Discharges from the Reactor Coolant System All lines connecting to the reactor coolant pressure boundary that are not required for either reactor pressure or inventory control will be isolated either automatically, or manually (operator action) utilizing plant emergency , 3 procedures, to prevent losses from the reactor coolant system. This
- includes the following potential leak paths
y Main Steam System l- - Reactor Head Vent , Reactor Shutdown Cooling Reactor Water Clean-up ' c Since the main condenser may not be available as a result of the loss of off-site power, the MSIVs have been included on the SSEL as active
- components since it may be necessary to close them.
't 4.1.4 Decay Heat Removal The primary method for removing reactor decay heat will be through the RHR System since the main condenser may not be available following an earthquake. The RHR System is utilized for decay heat removal in various operating modes to provide Torus Cooling and Alternate Shutdown Cooling. Heat is removed from the Torus following blowdown from the SRVs and/or operation of the HPCI pump by operating the RHR System in the Torus Cooling mode. In this mode, water from the Torus is circulated through an RHR heat exchanger, and retumed to the Torus. Once the reactor has been depressurized below a nominal pressure of 150 l 2 psia, the RHR system can be transferred from the Torus Cooling raode to l the Alternate Shutdown Cooling mode. In the Alternate Shutdown Cooling ! mode water from the Torus flows through the heat exchangers tc the reactor vessel via the LPCI injection path. Water is returned to the Torus via the SRVs. To establish the return path, the vessel water level is raised ]O Page 13
l ( SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 ' above the main steam lines. For the RHR System modes described above, heat is removed from the RHR heat exchanger by the High Pressure Service Water (HPSW) System which transfers heat to the Emergency Cooling System or Conowingo Pond. In addition, as identified previously in section 4.1.3, operator actions may l be requirad to alternately operate the RHR System in LPCI mode and Torus l cooling mode in the event of a failure of a 4 kV safeguards bus. Existing l procedures are in place at PBAPS to perform this function (ref. 5.7.2). l The paths that can be utilized to remove reactor decay heat are shown on the following P&lDs: l M-361, SH 1, 2, 3, 4: Residual Heat Removal l 4.1.5 Support Systems l In selecting systems and equipment to be used to accomplish the four safe shutdown functions, additional systems and components are identified and classified as Support Systems. The following systems have been identified hm as being required to support one or more of the above functions: The Torus which supports the Decay Heat Removal function. l Emergency Diesel Generators and its auxiliaries to provide emergency power in the event off-site power is lost. Electrical distribution for selected AC and DC loads (i.e., active components) identified on the SSEL. Emergency Service water to support the operation of the Emergency Diesel Generators, RHR pumps, and miscellaneous HVAC Systems. It should be noted that some of the HVAC and room coolers are included on the SSEL in order to have a seismic evaluation performed to ensure the integrity of the ESW System because their failure would divert ESW flow from required equipment. l 4.1.5.1 Emergency Service Water l Since no direct means of indication in the ficw paths of the ESW System ) have been included in the analysis, the operator will be relied upon to determine system operation based on:
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SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3
+ Flow is being provided to the diesel generator (s).
+ The comirmation of flow out of the Emergency Service Water side of the operating diesel generator heat exchangers.
4.1.5.2 High Pressure Service Water High Pressure Service Water is included to provide cooling water to the RHR heat exchangers. Since no direct means of indication in the flow paths of the HPSW System have been included in the analysis, the operator will be relied upon to determine system operation based on: l + Flow is being provided to the RHR heat exchangers.
+ The confirmation of flow out of the HPSW side of the operating RHR heat exchanger (s).
The paths needed to ensure the operability of the Emergency and High Pressure Service Water Systems to supply necessary heat loads are shown ! on the following P&lDs: M-315, SH 1, 2, 3, 4, 5: ESW and High Pressure Service Water Systems M-330, SH 1: Emergency Cooling System j 4.1.5.3 Emergency Cooling Tower i l - Emergency Cooling Tower provides a heat sink for the HPSW and ESW Systems. 4.1.5.4 HVAC HVAC in the Diese.1 Generator rooms (which also supplies combustion air for the respective diesel generator), HPCI Pump, RHR Pump rooms and HPSW Pump rooms are required to support l operation of those systems. t The Backup Instrument Nitrogen Supply System bottles have been included on the SSEL to support the operation of the ADS SRVs in the event the Instrument Air System fails during the earthquake. Since Control Room HVAC is not included on the SSEL manual action may be required to based on the methods provided in the i station procedures for loss of Main Control Room ventilation. Automatic start of the Diesel Generator room HVAC was included in Page 15 i
1 SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 lO l the analysis. l L The paths needed to ensure the operability of the plant HVAC systems are ! shown on the following P&lDs: M-399, SH 1,4: Emergency Switch Gear and Battery Room HVAC M-389 Radwaste Building HVAC M-385 Diesel Enclosure HVAC l M-396, SH1 Water Treatment and Intake' Structure Temperature Control Diagram L 4.1.5.5 Emergency Power The paths needed to ensure that operability of emergency power are shown on the following drawings: M-377, SH 1: DG Aux Systems (Starting Air) M-377, SH 2: DG Aux Systems (Air Coolant & Jacket Coolant) L M-377, SH 3: DG Aux Systems (Lube Oil) l - M-377, SH 4: DG Aux Systems (Diesel Fuel Oil) M-377, SH 5: DG Aux Systems (Comb. Air intake / Exhaust) E-8: Standby Diesel Gens & 4160V Emer. Power System, Unit 2 E-12: Standby Diesel Gens & 4160V Emer. Power System, Unit 3 4.2 Safe Shutdown Eaulomont List The SSEL is provided as Attachment B. Data for the individual fields on the SSEL was collected from reviews of plant drawings, the PECO Energy Co. ! component record list, plant operating procedures and preliminary walkdowns. Any specific methodology used to perform the various information collection efforts is discussed below. 4.2.1 The safe shutdown path was identified based on the assumptions and criteria presented in Section 3.0 as well as the SQUG GlP (ref. 6.2) with l input from the safe and alternative shutdown analysis (ref 5.8). Based on ! the identified paths, the Peach Bottom Unit 2 & 3 P&lDs were reviewed to identify those active and passive components in the paths which are required to support the safe shutdown function. The P&lDs were marked up and highlighted. lO ( Page 16 l
l SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 ' l The following fields of information for each active and passive component were collected from the P&lD or electrical one-line diagrams and input into the SSEL database: l Equipment Number. SOUG Equipment Class - from GIP (ref. 6.2). l Equipment Function - Active or passive to support the safe shutdown 1 function. Diagram and Support System Drawing Numbers. Equipment Description - Based on function of the component as indicated on the drawing. 4.3 ODerations Review of SSEL PBAPS operations reviewed the SSEL and determined that with the equipment on the SSEL, using plant normal and emergency procedures operators could bring the plant to a safe, shutdown condition. The primary procedures that would be used are summarized in Attachment C. 1 O l l i 1 1 1 l I l l lO l Page 17
._.-.- - . . - - - _ - .~ - - . - ._.- - _ _ - - . - . - - . _ - .
l SEISMIC SAFE SHUTDOWN EQUIPMENT UST FOR PBAPS UNITS 2 AND 3
5.0 REFERENCES
5.1 EPRI Report NP-6041-SL,"A Methodology for Assessment of Nuclear Power Plant j Seismic Margin," Rev.1. l 1 5.2 SOUG " Generic implementation Procedure (GIP) for Seismic Qualification of Nuclear Plant Equipment," Rev. 2, corrected February 1992. 5.3 ABB Impell (VECTRA) Project Instruction 0067-084-PI-001, " Identification of Safe Shutdown Paths, Equipment and Preparation of Success Path Component List (SPCL) for the PBAPS," Rev. O. 5.4 NRC Generic Letter 88-20, Supplement 4, " Individual Plant Examination of External Events (IPEEE) for Severs Accident Vulnerabilities - 10CFR50.54(f)," June 28,1991.
. 5.5 PBAPS Units 2 & 3 Fire Protection Program, Rev. 7.
5.6 Peach Bottom Atomic Power Station P&lDs: E-8, Rev.15 Standby Diesel Gens & 4160V Emer Power System, O E-12, Rev.11 Unit 2 Standby Diesel Gens & 4160V Emer Power System, l Unh3 M-309, SH 1, Rev. 51 Cond & Refueling Water Storage & Transfer Systems M-309, SH 2, Rev. 50 Cond & Refueling Water Storage & Transfer Systems M-315, SH 1, Rev. 42 ESW and High Pressure Service Water Systems M-315, SH 2, Rev. 41 ESW and High Pressure Service Water Systems , M-315, SH 3, Rev. 39 ESW and High Pressure Service Water Systems-l M-315, SH 4, Rev. 42 ESW and High Pressure Service Water Systems i M-315, SH 5, Rev. 43 ESW and High Pressure Service Water Systems ! M-330, SH 1, Rev. 22 Emergency Cooling System M-333, SH 1, Rev. 41 Instrument Nitrogen M-333, SH 2, Rev. 40 Instrument Nitrogen l M-351, SH 1, Rev. 53 Nuclear Boiler l M-351, SH 2, Rev. 54 Nuclear Boiler M-351, SH 3, Rev. 55 Nuclear Boiler l M-351, SH 4, Rev. 55 Nuclear Boiler M-356, SH 1, Rev. 46 Control Rod Drive Hydraulic System - Part A i M-356, SH 2, Rev. 46 Control Rod Drive Hydraulic System - Part A l M-357, SH 1, Rev. 26 Control Rod Drive Hydraulic System - Part B ( M-357, SH 2, Rev. 25 Control Rod Drive Hydraulic System - Part B !O j Page 18 f
SEISMIC SAFE SHUTDOWN EQUIPMENT LIST FOR PBAPS UNITS 2 AND 3 M-361, SH 1, Rev. 52 Residual Heat Removai System
- M-361, SH 2, Rev. 49 Residual Heat Removal System -
l M-361, SH 3, Rev. 49 Residual Heat Removal System i M-361, SH 4, Rev. 49 Residual Heat Removal System , M-362, SH 1, Rev. 51 Core Spray Cooling System M-362, SH 2, Rev. 51 Core Spray Cooling System i M-365, SH 1, Rev. 46 High Pressure Coolant injection System i M-365, SH 2, Rev. 48 High Pressure Coolant injection System ! M-366, SH 1, Rev. 40 HPCI Pump Turbine Details
; M-366, SH 4, Rev. 38 HPCI Pump Turbine Details i M-377, SH 1, Rev. 23 DG Aux Systems (Starting Air System) j M-377, SH 2, Rev.19 DG Aux Systems (Air Coolant and Jacket Coolant
[j M-377, SH 3, Rev 16 Systems) DG Aux Systems (Lube Oil System)
- M-377, SH 4, Rev. 22 Dg Aux Systems (Diesel Fuel Oil System)
! M-377, SH 5, Rev.1 DG Aux Systems (Combustion Air intake / Exhaust System)
- M-384, SH 1, Rev. 32 Control Room HVAC l M-384, SH 2, Rev.1 Control Room HVAC
- M-384, SH 3, Rev. 2 Control Room HVAC l M-385, Rev. 20 Diesel Engine Boiler Building, Shop and Warehouse
! M-389, Rev. 21 Radwaste Building Ventilation Flow Diagram M-396, SH 1 Water Treatment and intake Structure Temperature a
Control Diagram ! M-399, SH 1, Rev. 2 Emer Swgr, Battery Room, Laboratory Supply & Exhaust M-399, SH 4, Rev. 2 Emer Swgr, Battery Room, Laboratory Supply & Exhaust l i t i 5.7 PBAPS Units 2 and 3 Procedures 5.7.1 SE-3 Loss of Conowingo Pond 5.7.2 ' SE-11 Loss of Off-Site Power With Attachments D. H, J, L, M, N, W, X and Z j 5.7.3 T-101 RPV Control
; 5.7.4 T-102 Primary Containment Control i i 5.7.5 T-111 Level Restoration
. 5.7.6 T-112 EB Emergency Biowdown i F 5.7.7 T-116 RPV Flooding 5.8 MDE-86-0786 rev.1, Safe and Alternative Shutdown Analysis Philadelphia Electric Company, Peach Bottom Atomic Power Station Units 2 and 3, October 1986. O Page 19
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