Text

Rev 0 to Response to NRC Generic Issue 77: Flooding of Safety Equipment Compartments by Backflow Through Floor Drains, Rancho Seco Nuclear Generating Station
	ML20141D575
Person / Time
Site:	Rancho Seco
Issue date:	03/31/1986
From:	; ABB IMPELL CORP. (FORMERLY IMPELL CORP.)
To:	;
Shared Package
ML20141D570	List: ML20141D568; ML20141D575;
References
	01-0790-1476, 1-790-1476, NUDOCS 8604080156
	Download: ML20141D575 (75)
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{{#Wiki_filter:7-RESPONSE 10 NRC GENERIC ISSUE 77: " FLOODING OF SAFETY EQUIPMENT COMPARTMENTS BY BACKFLOW THROUGH FLOOR DRAINS" RANCHO SECO NUCLEAR GENERATING STATION Prepared for: J SACRAMENTO MUNICIPAL UTILITY DISTRICT n 1 Prepared by: Impell Corporation 350 Lennon Lane ]J Walnut Creek, California 94598 \\ Impell Report No. 01-0790-1476 Revision 0 404 March,1986 lIO40$DobK Oh$k2 P I e

Impell R; port No. 01-0790-1476 Revision 0 TABLE OF CONTENTS Page ABSTRACT

1.0 INTRODUCTION

1 -1 2.0 RESPONSES TO GENERIC ISSUE 2-1 l l 77 QUESTIONS 2.1 Response to Question 1 2-1 2.2 Response To Question 2 2-13 2.3 Response To Question 3 2-14

3.0 REFERENCES

3-1 LIST OF TABLES 2.1 Auxiliary Building 2.1 -1 2.2 Nuclear Service Electrical Building 2.2-1 2.3 Turbine Building 2.3-1 2.4 Reactor Yard Area 2.4-1 LIST OF FIGURES 2-1 Auxiliary Building Drains (Safety-Related Rooms), Elevation (-) 47'-0" 2-2 Auxiliary Building Drains (Safety-Related Rooms), Elevation (-) 20'-0" 2-3 Auxiliary Building Drains (Safety-Related Rooms), Elevation O'-0" 2-4 Auxiliary Building Drains (Safety-Related Rooms), Elevation 20'-0" 2-5 Auxiliary Building Drains (Safety-Related Rooms), Elevation 40'-0" 2-6 Isometric Diagram for Plumbing at El. 21 '-6", NSEB 2-7 Isometric Diagram for Plumbing at El. 40'-0", NSEB 2-8 Isometric Diagram for Plumbing at l l El. l '-6" and 40'-0", NSEB l 2-9 Simplified Retention Basin Diagram l 2-10 Check Valve for Prevention of Backflow 1 I

I Impall R: port No. 01-0790-1476 Revision 0 ABSTRACT I In response to the NRC Generic Issue 77 (Reference 1), " Flooding of Safety Equipment Compartments by Backflow through Floor Drains," this report provides a I detailed response applicable to Rancho Seco Nuclear Generating Station Unit One. An outline of the questions and response is provided below: Question 1: Provide a detailed discussion Columns 1, 2, and 3 of Tables 2.1 through of the equipment and floor drainage 2.4 provide the appropriate response. I systems which serve safety-Figures 2-1 through 2-8 are the related equipment or compartments applicable diagrams. containing safety-related equipment. Include diagrams as appropriate. Describe features which will " Comments" column of Tables 2.1 through prevent backflow from any area 2.4 provide the appropriate response. into compartments containing safety-related equipment. This I discussion should include the drainage system and any other compartment openings such as doors, unsealed penetrations or I grating through which fluid may fl ow. Sources of fluid to be considered Appropriate response is provided in Section are external flooding, flooding due 2.1. 3. to tank failures and pipe breaks including failure of expansion joints in the circulation water system. Fluids to be considered are water, Discussion is provided in Section 2.1.4. steam, and hot air. The effect of water is discussed in 2.1.3. I Confinn for those conditions This confirmation is provided b the identified above that redundant "Consnent" section of the tables. safety-related equipment will not be adversely affected by I fluid ingress into the equipment compartments. I 1 1

l lW Itp311 Repsrt No. 01-0790-1476 Revision 0 Question 2: Describe the design basis for Description is provided in Section 2.2. sizing the equipment and floor drainage systems and the means for assuring that they can effectively handle the maximum leakage flow conditions in the specific plant I areas of concern housing redundant safety-related equipment. Question 3: Indicate any past incf Gents of Appropriate response is provided in drainage system backflow or other Section 2.3. concern for failure of redundant safety-related equipment that has I arisen or been postulated in the past due to a fluid leak or harsh environment in safety-related equipment areas. I I

E Impe11 R p rt No. 01-0790-1476 Revision 0

1.0 INTRODUCTION

As per Reference 1 the Nuclear Regulatory Commission I (NRC) designated " Flooding of Safety Equipment Compartments by Backflow through Floor Drains," as Generic Issue 77. The NRC has requested that the Sacramento Municipal Utility District respond to following questions: 1. Provide a detailed discussion of the equipment I and floor drainage system (s) which serve safety-related equipment or compartments containing safety-related equipment. Include diagrams as appropriate. As part of the discussion, describe the features which will prevent backflow from any area into compartments containing safety-related equipment. This discussion should include the drainage system and arty other compartment openings such as doors, unsealed penetrations or grating through which fluid may flow. Sources of fluid to be considered are external flooding (ground water seepage, surface influence from rivers and j lakes, and rain fall ponding) and flooding due to tank failures and pipe breaks including failure of the expansion joints in the circulating water system. The backflowing I fluids to be considered are water, steam, and hot air. Confirm for those conditions identified above that redundant safety-related I equipment will not be adversely affected by fluid ingress into the equipment compartments. 2. Describe the design basis for sizing the equipment and floor drainage systems and the means for assuring that they can effectively handle the maximum leakage flow conditions in iI the specific plant areas of concern housing redundant safety-related equipment. I i 'I 1 -1 ,w_,

.---.~2^. Irpell Report No. 01-0790-1476 4 Revision 0 4 i 3. Indicate any past incidents of drainage system } backflow or other concern for failure of i redundant safety-related equipment that has arisen or been postulated in the past due to a i fluid leak or harsh environment in j safety-related equipment areas. f This report discusses the assumptions and the i methodology used in performing the above analysis and provides a summary response to each of the above questions. l i s i 4 't i I I E j i 1-2 I 1

Impell R:: port No. 01-0790-1476 Revision 0 2.0 RESPONSE TO QUESTIONS GENERIC ISSUE 77 In response to the Generic Issue 77 questions, the safety-related equipment is defined per the requirements of 10CFR50.49 (Reference 6). In reference 7 the Updated Safety Analysis Report (USAR) Chapter 14 accidents are evaluated and the systems necessary for accident mitigation are determined. In this evaluation components and support systems needed 4 to assure proper functioning of the mitigating I systems are identified. Using the information in Reference 7 as input, the harsh and mild environments for the safety-related components required for mitigating USAR Chapter 14 accidents are determined in Reference 12. The safety-related compartments are defined as the rooms which contain safety-related components. In preparing responses to the questions in Generic issue 77, extensive use of the Rancho Seco Updated Safety Analysis Report (Reference 3) is made. The detailed response to each question is provided below: 2.1 Response to Generic Issue 77 Question 1 The safety-related equipment at the Rancho Seco Nuclear Generating Station is located in the following buildings: (Reference 12) 1. Reactor Building 2. Auxiliary Building 3. Nuclear Service Electrical Building 4. Turbine Building 5. Reactor Yard Areas (Includes the NSRW pump houses) 6. Spent Fuel Building Question 1 is a complex and lengthy question and it requires detailed information on several issues. Question 1 is broken into its various subquestions and the response to each, including assumptions, is provided below: 2-1

T l Impell R: port No. 01-0790-1476 Revision 0 E 2.1.1 Provide a detailed discussion of the equipment and floor drainage systems which serve safety related equipment or compartments containing sarety-related equipment. Include diagrams as i appropriate. j The response to this question is provided on a building-by-building basis. Reactor Building j Reactor Building contains two normal sumps. All the equipment drains in the Reactor Building are routed i 4 to these sumps. Any fluid loss through equipment drains and postulated line breaks drains to these sumps. These sumps are located at the lowest elevation of the Reactor Building. The line breaks and their flooding heights have been analyzed in Reference 4. The maximum flooding height in the Reactor Building is 8 feet (el. -17 feet). As part of the environmental qualification project (Reference 6), safety-related equipment located in the Reactor Building are qualified to include flooding effects. Hence, the safety-related equipment in Reactor Building will perfonn its intended safety-related function and would not be affected by the postulated flooding conditions. Therefore, the Reactor Building drainage system is not evaluated in this report. Auxiliary Building The Auxiliary Building rooms 'containing I safety-related equipment are: (Reference 12) Room Description 001 West Decay Heat Removal Pump Room 002 East Decay Heat Removal Pump Room 011 Spray Additive Tank Area 020 Radwaste Control Panel Ares 043 HPI Pump 'B' Room 044 Make-up Pump Room ) 045 Corridor 046 Seal Return Cooler room 051 Containment Penetration Yalve Area-East 052 Containment Penetration Valve Area-West 053 HPI Pump 'A' Room 103 Corridor ) 2-2 I

Impell R:p;rt No. 01-0790-1476 Revision 0 119 Nuclear Service Battery Room E 120 Nuclear Service Battery Room 121 Switchgear Room 124 Switchgear Room 125 Nuclear Service Battery Room E 126 Nuclear Service Battery Room 130 Diesel Generator Room 132 Diesel Generator Room 204 Air Conditioning Equipment Room 208 Duct Space 209 Electrical Penetration Room 211 Ventilation Equipment Room 212 AC/DC Panel Room 213 AC/DC Panel Room E 214 Electrical Equip. Room 217 Electrical Equip. Room 218 AC/DC Panel Room E 219 AC/DC Panel Room 220 Station Battery Room 3 333 Technical Support Center B 338 Computer Room 339 Control Room 340 Shift Supervisor Office '5 341 Conference Room 342 Kitchen 343 Toilet 344 Corridor Figures 2-1 through 2-5 show the Auxiliary Building floor and equipment drain system arrangements for the 'I rooms containing safety-related equipment. Columns 1 through 3 of Table 2.1 provide a detailed description l of th'e floor and equipment drainage systems of the I safety-related compartments. Nuclear Service Electrical Building The Nuclear St.rvice Electrical building (NSEB) drainage sysym is designed in accordance with the t.alculations listed in Reference 11. There is only I fire water piping and domestic water pipi.ng in tho NSEB. 1Here is no high energy or process piping in the NSEB. Figures 2-6 thru 2-8 show the isometric I. through 3, provide a dat' ailed description of the NSEB layout Of the drain &5a system. Table 2.2, columns 1 dr&inage system, 2-3 i -4..

~ ~ ~ ~ .. _.._____ R._ E Impell Report No. 01-0790-1476 Revision 0 E Turbine Building The Turbine Building contains two sump areas; (1) Polisher and Makeup Demineralizer sump and, (2) Condenser Pit sump. The Turbine Building is a large open area and has grating floors at the 20' foot elevation. The building drains are designed to discharge to these two sumps. The Polisher and Makeup Demineralizer sump is located at grade level in the Turbine Building just east of the water shack. The sump itself is located below grade level and sump pumps P-965A and P-965B are mounted on the top of the sump. The sump receives drainage from the following: Makeup demineralizer equipment and area floor drains Polishing demineralizer regeneration equipment and area floors drains Acid injection pumps P-758A, B, and C Condenser pit sump pumps P-964A and B Steam generator drain booster pumps P-309A and B Floor drains from Station Battery Room and West Nuclear Service Battery Room Training and records building floor drains The Condenser Pit sump is located in the condenser pit area of the Turbine Building. The following areas have drains leading to this sump: Turbine deck drains Ground floor drains in the Turbine Building Condenser water box drains Condenser pit drains (' 2-4 l

I pell R: port No. 01-0790-1476 Revision 0 Chemical feed area drains Diesel generator room floor drains I The drainage system of the Turbine Building is described in columns 1 through 3 of Table 2.3. Reactor Yard Area I The Reactor Yard area is an open area and is designed tc endure all veather conditions. Table 2.4 provides information en the drainage system for the areas in the yard containing safety-related equipment, Spent Fuel Building Tl e safety-related equipment located in the spent fW building are installed high enough above the floor to prevent any damage due to flooding. 2.1. 2 Describe features which will prevent backflow from any area into compartments containing safety-related equipment. This discussion should include the drainage system and any other compartment openings ruch as doors, unsealed penetrations or grating through which fluid may flow. I The " Comment" column of Tables 2.1 through 2.4 describes the backflow prevention features of the safety-related compartments, e.g., curbs, sills, doors, etc. These features have been verified by a plant walkdown (Reference 20). Figure 2-10 shows a check valve in the drain line located at the grade level of the Auxiliary Building which prevents any backflow from the below grade level of the Auxiliary Building. Also, backflow preventers have been provided in the domestic water lines discharging into the acid waste pump and the sanitary waste sump to prevent any contamination of domestic water. The "Coment" column of these tables also provides the minimum installed height of safety-related equipment in the rooms. I 2-5

_.. i ~. _. ~ ~ ~'~ Impell Report No. 01-0790-1476 Revision 0 2.1.3 Sources of fluid to be considered are I external flooding, flooding due to tank failures and pipe breaks including failure of expansion Joints in tne circulating water system. 2.1.3.1 External Flooding (Reference USAR Section 2.4) Section 2.4 of the USAR discusses external flooding in detail. This section includes storms and lakes within a fifty-mile radius of the Rancho Seco site. A brief summary of this report is discussed below. The Rancho Seco site is gently rolling and is not intersected by any streams, but is bounded by well-defined drainage courses that intercept surface I runoff from the higher site topography. The plant grade permits excellent drainage at all times without the danger of flooding. Plant areas are graded to provide natural drainage to lower ground. ~ Storm water runoff at the Rancho Seco site is controlled primarily by surface ditches. Generi,1y, I overland flows will be intercepted by the ditches, and diverted around the plant to nr&di stream channel s. When this is not possible, runoff will be diverted down the cut slopes in culvert pipes and discharged to the plant drainage ditch system. The drainage ditch system was designed to accomodate the 25-year recurrence storm with a minimum of six inches I freeboard and the 100-year recurrence storm with zero freeboard. Rainfall intensities were determined from the rainfall-duration-intensity curves contained in the 1966 publication " County of Sacramento, Flood Control and Storm Drainage." Within recent historical times, no flooding or inundation from storms or runoff has occured within I the Rancho Seco boundaries. It is unlikely that the site can be inundated or flooded, even with abnormal rainf all intensities. 2-6 I n~ --.-.v-,. - - -. - - - ,v-- g-. s.- 9

~ ~ ~~ ~' Impe11 R: port No. 01-0790-1476 Revision 0 I To provide criteria for the design of an adequate I spillway to safeguard the drain embankment from any danger of overtopping, $ection 2.4,4 of the USAR Indicates that a hydrologic study of stortns which may produce critical floods was made. Two types of I storms might produce the critical outflow flood for spillway design. The frontal winter storm would produce the greatest amount of total rainfall, but I would be relatively low intensity. A sumer thunderstorm, on the other hand, would be of short duration but with very intense down pour. As per Section 2.4.4 of the USAR, the probable maximum frontal storm a of 72-hour duration was calculated in accordance with U.S. Weather Biireau Hydrometeorlogical Report No. 36 dated October, 1961. Whereas, the thunderstorm PHP was calculated in accordance with precedures recomended by the Sacramento District Office of the U.S. Amy Corps of Engineers dated December 1968. The relatively large area of the reservoir surface with respect to the effective drainage area and the maximum flood volumes determined ensures no flo0 ding of safety-related equipment or compartments from the worst postulated stom conditions. 2.1.3. 2 Flooding Due to T_ank Failures and Pipe Breaks I Incuding Failure of; Expansion doints_in the Circulating Water System As per USAR Chapter 14 Section 14.1.3.2, " lines which I_ do not exceed 200*F or 275 psig need not be cont.idered high energy lines. Break Size Criteria: Section 14.1.3.4 of the USAR states: Ine consideration given for breaks in which plant structures, systems and compenents important to safety could be affected included full I circumferential breaks in high energy lines in 1" inch and larger sizes, and, in addition, longitudinal breaks in pipes 4" inches nominal size and larger." i I 2-7 I .~

Impe11 R: pert N3. 01-0790-1476 Revision 0 i \\ i I Break Location Crit 6ria: In Section 14.1.3.3 of the USAR, the location oTWigh energy lines breaks are identified. The. pipe t.reak locations were postulated for high energy lines at the terminal ends and at I least two intermediate points at the most ariverse locations, based on proximity to equipment required for safe shutdown, where the relative stress valves were significant. I The USAR further states that no locations wer-e identified where the stress values exceeded the criteria. Pipe Rupture Effect.on Other Systems: As per USAR f hection 14.~ 1. 3.10, if was veritted that rupture of a pipe carrying a high energy fluid will not directly or ir.directly result in: A. Loss of required redundancy in any portion of the protection system (as defined in IEEE-279), Class IE electric system (as defined in IEEE-308), I engineered safety feature equipment, cable penetrations, or their interconnection cables required to mitigate the consequences cf th&t accident and place the reactor in a safe shutdown I condition, or D. Environmentally induced failures caused by a leak I or rupture Of the pipe which would not of'itself result in protective action but which would disable protection functions. In this regard, a loss of redundancy is permitted but a, loss of I function is not permitted. For such situations plant shutdown is required. Each potential problem was evaluated en the basir; of the guidelines, -1.e.: of a failu,*e 6f a line could damage a piece of equipment and the failure of thu I line did not result in protective action as defined in (B), above. Sing 1s failure was not assumed and credit was taken for redundancy. The arcas where ruptuf c of a pipe carrying high energy fluid might result directly or indirectly in loss of function of equipwnt included in (A) and (B) I above have been detannined and are listed as Items 3, 4, a, 9,10,14,15,16,17,,19, 20, 21, 23H, 23I, 231, 23L, 22M, 26, 27 and 29 on Table 14.1-17. I ne o 1 m - - - -A

Impell R:p3rt No. 01-0790-1476 R: vision 0 The following line breaks were investigated for flooding effects in Table 14.1-17: Feedwater Line (Item 24, Table 14.1-17) Mainsteam Line (Item 29, Table 14.1-17) BWST Tank Failure (Item 28, Table 14.1-17) Any line breaking and. flooding, both decay heat pumps (Item 22, Table 14.1-17) The table identifies the mitigating actions and concludes that the plant will still achieve a safe shut down despite the postulated failure. A detailed discussion of Item 22, Item 24 and Item 28 is provided below: Any Line Breaking and Flooding Decay Heat Pump Rooms 'in Auxiliary Building: (Ref. USAR Section 6.5.5.2) The decay heat room sumps are equipped with level alarms which annuciate both at the radwaste panel and in the main control room. The alarm is activated when the water level reaches within one foot of the top of the sump. In the event of flooding of the sbmps, the decay heat loop in the room that has become flooded can be isolated respotely from the control room to prevent the ficoding from spilling over into the adjacent roote. The decay heat pump rooms are physically separated by a' concrete wall which prevents flow of water from one' room to other until the room is flooded to elevation (-)39 feet - 0 inches. Motor operated valves are provided with remote controls to isolate the recirculation loops. The time required to c' lose the system isolation valves is 94 seconds. The quantity of fluid leakage during this time is calculated to be about 14,000 gallons. This is based on the co:nplete severance of the 18-inch emergency sump line and a linear ramp reduction in isolation valve flow area. In the event of this major failure of the system, the operator will have approximately 3 minutes in which to take action to begin isolation of the recirculation system before flooding of the adjacent decay heat room will begin to occur. 2-9

Imp 211 Report No. 01-0790-1476 Revision 0 I The operator will have three indications of gross failure of the recirculation system. A first indication will be operation of one of the large capacity sump pumps which would not be expected to ' I operate if leakage from the system were normal. Sustained operation of the 100gpm sump pump will be a positive indication of a gross leak requiring isolation. The second indication would be operation I of the annunciator or alarm on sump high level. The third indication would be a high radiation alarm n signal from the affected decay heat pump room or f l other Auxiliary Building areas. Consequently, for any line breaking and flooding the decay heat pump room, the operator will have adequate I warning, and the barrier between the pump rooms will prevent room to room flooding. Worst Case Feedwater Line Break: In the event of the failure of tne feedwater line in the area bounded by ~ the Reactor Building, Fuel Storage Building, the transfer tube structure and the Auxiliary Building, I the area will be drained using the tendon access gallery. Section 14.1.3.14 of the USAR states: "The gallery can store 175,830 gallons of water. An I overflow is provided by using a tendon gallery shaft to drain the excess of 175,830 gallons. Total capacity which could be released to this area is less l than 300,000 gall ons." Concrete curbs are installed to protect the Auxiliary Building from flooding through the doors. The diesel generator main walls will prevent flooding of the diesel generators. Consequently, equipment required for safe shutdown will be protected from flooding. Reactor Yard Area: The Reactor Yard contains large storage tanks. Ine USAR states: "In the event of a tank rupture in the yard area north of the Reactor I Building, the existing plant drainage system is adequate to drain the area without build-up of water, which could endanger Class I systems." E Turbine Building: Flooding in the Turbine Building is addressed in the USAR. The postulated flooding is from a main steam line or main feedwater and I condensate line failure. Table 14.1-17 of tho USAR states that the water from the break will be 2-10

I Impell Report No. 01-0790-1476 Revision 0 \\ contained in the condenser pit. Additionally, the Turbine Building has grated floor at elevation 20'. Consequently, the discharged fluid will flow unobstructed to the lowest point of the Turbine Building, the condenser pit. The grade level floor drains of the Turbine Building also drain to the condenser pit (see Section 2.1.1). The condenser pit can easily contain the discharged fluid resulting I from the ostulated line breaks. There is no safety-re ated equipment in the condenser pit. The e possibility of any fluid accumulation is extremely unlikely. Therefore, equipment required for safe shutdown is protected from any flooding effects. The effect of letdown break and Auxiliary steam line break is discussed in section 2.1.4 effect of steam and air. Expansion Joints Failure in the Circulating Water System: The following systems are evaluated for the I failure of expansion joints: i ( ;' L 1. Nuclear Service Raw Water System (NSRW): The expansion joints used in the NSRW system are located at the: Discharge lines of the NSRW Pumps P-472A and B Discharge lines of the NSRW Circulating Pumps P-476A and B _ l Inlet lines of the NSRW Filters F-475A and B Inlet and Discharge lines of the Diesel Generators Cooling Water Heat Exchangers E-473A - I and B Inlet and Discharge lines of the Nuclear Service Cooling Water Heat Exchangers E-480A and B r The expansion joints of the Nuclear Service Raw Water pumps are located at the discharge lines of pumps P-472A and B. The expansion joints are located inside the pump houses. The failure of the expansion joint inside the pump house will result in the loss of function of the NSRW pump. Any overflow from the pump house will pour back into the spray pond. The I redundant system is located 430' feet away and is 6 completely isolated from the flooding effects in the first pump house. For the NSRW circulating pumps P-476A and B, the situation resulting from an expansion joint failure is identical to circumstances described above. 2-11

Impell Rsport No. 01-0790-1476 R1 vision 0 There are expansion joints located at the inlet line of filtering units F-475A and B. The failure of the expansion joint will result in the loss of function of the filter. The redundant system is located 400' feet away and is completely isolated from the flooding effects at the first filter unit site. The expansion joints at the inlet and discharge lines of the Diesel Generator Cooling Water Heat Exchangers E-473A and B are located inside the Diesel Generator rooms. The failure of an expansion joint will result in the loss of function of the associated diesel generator. Excess fluid from the break will overflow to the Turbine Building and down to the Condenser Pit sump. 2. Circulating Cooling Water System The Circulating Cooling Water System is a low pressure non-safety-related system. No expansion joint failure is postulated for this system. In the unlikely event of an expansion joint failure, no safety-related equipment or system would be adversely affected. Any discharge of fluid will overflow into the Condenser Pit sump and/or the Intake Structure. 3. Plant Cooling Water System The Plant Cooling Water System is a low pressure non-safety-related system. No expansion joint failure is postulated for this system. In the unlikely event of an expansion joint failure, no safety-related equipment or system would be adversely affected. Any discharge of fluid will overflow into the Reactor Yard Area and/or the Intake Structure. 2.1.4 Fluids to be considered are water, steam, and hot air. The discussion on steam and hot air is as follows: In the below grade level areas of the Auxiliary Building, the failure of 6" inch auxiliary steam line and the complete severance of the 2-1/2" inch letdown line has been postulated. (USAR Chapter 14, Reference 3). The environmental conditions for these breaks have been determined in References 14, 15, 16, and 18. The analysis has modeled various safety-2-12

. _. _. _ _ _ _. _ _ ~. _.. _ _. _. I Impell R: port Ns. 01-0790-1476 Revision 0 I related compartments for determining post-accident environmental conditions. The safety-related I equipment are environmentally qualified to the calculated conditions as per the requirement of Reference 6. Reference 17 detennines the I environmental conditions in the above grade level areas of the Auxiliary Building due to postulated 3" auxiliary steam line break. Reference 19, determines the environmental conditions due to high energy line breaks postulated in Turbine Building, Reactor Yard Areas, Spent Fuel Pool Building. Safety-related equipment in these areas are environmentally I qualified to the post accident conditions. The calculated environmental conditions include the effect of line breaks on adjacent compartments. The effects of hot air have not been considered because the resulting conditions are enveloped by the steam accident environments. The effects of water is I discussed in Section 2.1.3. 2.1.5 Confirm for those conditions identified above I that redundant safety-related equipment will not be adversely affected by fluid ingress into the equipment compartments. Any effect on the safety-related equipment due to fluid ingress in the safety-related equipment compartments is discussed in the connent Section of Tables 2.1 through 2.4 The flooding effects due to potential leakage through floor construction cracks is not considered. The major leakage path between floors is assumed to be stairways, gratings or open penetrations. 2.2 Response to Generic Issue 77 - Question 2 The response to Question 2 about the design basis for sizing the equipment is provided as follows: The drainage system has been designed in accordance with the Uniform Plumbing Code as published by the I International Associations of Plumbing and Mechanical officials. The minimum drain size for equipment drains and floor drains in the plant is 2", which conservatively handles 30gpm (Reference 10, Table 4-2 I Page 39). As per Reference 8.1 (Section 5.1.1.1), 2-13

Imp 311 Repsrt No. 01-0790-1476 Revision 0 the equipment leakage flow ranges from 0.5 to 15gpm. l The drainage system is designed to provide adequate capacity to dispose of any leakage conditions. As per Reference 13, the following guidelines has I been used in routing drain lines: a. Drain lines are provided with floor clean out I (FCO), wall clean out (WCO) and clean out (CO) connections to facilitate cleaning of the drain lines. b. In general, floor drains are located at the low point of the floor. Any exceptions are noted on the plumbing and drainage drawings. c. For the Auxiliary Building, the minimum slope on the gravity lines shall be 1%. Any exceptions are noted on the plumbing and drainage drawings. d. For the Turbine Building, the drain line slope used is 1/8" per foot. SMUD design guides have been prepared for present and future plant modifications. These design guides provide the design bases for determining the flow rates, and the pipe sizes. The design guides are Mechanical Discipline 5208.30, Equipment and Floor Drainage Systems; Mechanical Discipline 5208.31, Routing of Plumbing and Drainage Systems; and Plant Design Discipline 5207.27, Plumbing Design Manual. l ,'g (Ref. 8). 3 2.3 Response to Generic Issue 77 - Question 3 The Rancho Seco Nuclear Generating Station's Site Document Control (SDC) maintains a log and copies of all Occurrence Description Reports (0.D.R.). All the plant incidences are documented using the 0.D.R.s. l The 0.D.R. logs (from 1974 to present) were reviewed for incidences of drainage system backflow or fluid leaks. The Occurence Description Reports are listed I in reference 9. As per these 0.D.R.s there has not been any incidence of drainage system backflow in the safety related areas. There have been incidences of minor leaks through pipes, pump seal leakage, etc. These have not affected or resulted in the failure of l l l I 2-14

s Impall Repsrt Ns. 01-0790-1476 Rtvisien 0 the redundant safety related equipment. The results of the 0.D.R. review is summarized below: Reference 9.1, 9.2, 9.4, 9.5, 9.6, 9.8, 9.9, 9.10, 9.12, 9.16, 9.18 document leakage associated with the decay heat system. The leaks were associated with pin holes th ough weld crack and decay heat pump seal s. The maximum leakage rate reported was 3 GPM. These small leaks did not result in a failure of the redundant safety-related equipment. Reference 9.3 documents leakage through a weld on the make-up pump suction valve bypass line in the seal injection and the make-up system. There was no damage to any redundant safety-related equipment as a result of this leak. Reference 9.7 documents water leakage from the Spent Fuel Pool wall into Turbine Building floor and drains, and also to a drain between the Spent Fuel Building and the Reactor Building. There was no damage to any redundant safety-related equipment as a result of this leak. Reference 9.11 documents the leakage through the sampling lines as a result of operator error. This incident did not result in any damage to redundant safety-related equipment. Reference 9.13 documents flooding of the Diesel Generator Fuel Oil Storage Tank area fuel oil pumg " pit with rain water. The diesel generator train A was declared inoperable. This incident did not result in failure of redundant safety-related equipment. Reference 9.14 documents the overflowing of the Miscellaneous Water Holdup Tank due to personnel error. This did not result in the failure of any redundant safety-related equipment. Reference 9.15 documents leakage through the valve HV-22501 in the purification and letdown system. The leakage was less than 2 GPM. There was no damage to redundant safety-related equipment. 2-15

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t. _.. _ _ I I; pall Report No. 01-0790-1476 Revision 0 I Reference 9.17 documents leakage through the PI23601 I root valve. Leakage was approximately 3 GPM. There was no damage to redundant safety-related equipment. I Reference 9.19 documents the failure of the make-up seals resulting in excessive leakage. Water on the floor was approximately 3" to 4" high. Water overflowed into the adjacent high pressure injection pump room and down to area 057, the Radwaste Transfer Pemp area. The leakage did not result in any damage to redundant safety-related equipment. Reference 9.20 documents that, the deluge valve on the Technical Support Center pre-action sprinkler system activated. The water from deluge valve drain I line discharged into a 5 gallon bucket which overflowed onto the floor. The water leaked through a construction seam on the floor to the East 480V I Switchgear room. This leakage resulted in wetting of some of the electrical panels. Plastic sheets were used to protect the panels and there was no report of damage to the panels. Plant modifications are in progress to correct this situation. 1 ) l l l l l l 2-16 ,---.,,,,,--,-.,,,---._,.------_,_.,.-_._e._..._--w-

W W 01-0790-1476 Reyfsfonf TABLE 2.1 AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 RCOM ELEV. DRAINAGE SYSTEM DETAILS COMMENTS 0 01 - -47' Room 001 has 1-2" floor Room 001 is the West Decay Heat Removal i West Decay drain and 2-2" equipment Pump room. The redundant decay heat Heat Removal drains which drain to a system is located in room 002 and is Pump Room 4" line discharging into completely isolated from flooding the West Decay Heat effects in room 001. There is no Removal Pump Room sump at possibility of backflow through the El. (-)47'. Sump pumps drainage system. These rooms do not P663A and P664A discharge share or discharge to a common drain to the Miscellaneous pipe. The minimum height of any safety Waste Tank, T-667. The related equipment is 22". A detailed 4" line to the sump is the discussion of these two rooms is i common drain line used for provided in Section 2.1.3. I drainage of rooms 001, 052 and 053. t I i l i 2.1-1

M M M M M M M m Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 i ROOM ELEV. DRAINAGE SYSTEM DETAILS COM1ENTS 002- -47' Room 002 has 1-2" floor Room 002 is the east decay heat removal East Decay drain and 1-2" equipment pump room. The redundant decay heat Heat Removal drain which drain to a 6" system is located in room 001 and is Pump Room line discharging into the completely isolated from flooding i East Decay Heat Temoval effects in room 002. There is no Pump Room sump at E1. possibility of backflow through the 1 (-)47'. Sump pumps P663B drainage system. These rooms do not and P664B discharge to the share or discharge to a common drain Miscellaneous Waste Tank, pipe. The minimum height of any safety j T-667. The 6" Ifne to the related equipment is 22". A detailed sump is the common drain discussion of these two rooms is line used for drainage of provided in Section 2.1.3. rooms 002, 043, 044, and 0 51. l l 2.1-2 i

M M M M M M M M M M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Eliffnued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 l ROOM ELEY. DRAINAGE SYSTEM DETAILS COPO4ENTS 011- -20' Room 011 has a 1-2" floor Room 011 is an open area at the west i Spray drain which drains to a end of corridor 015 (See Figure 2-2). Additive 6" line discharging into There are no barriers or obstructions Tank Area the radwaste area sump in to prevent the flow of fluid from area 057 at el. (-)29'. area 011 to corridor 015 and similarly Sump pumps P665 and P666 from 015 to corridor 036. Corridor i discharge to the 036 has a grated floor which allows the Miscellaneous Waste Tank, fluid to drain down to area 057, the T-667. The 6" line to Radwaste Transfer Pump area (el. -29'). the pump is the common Any discharge of fluid in area 011 will ( drain line used for spread over a large area and eventually j drainage of room 011 and drain down to area 057. Any flooding other areas of the can be easily contained in area 057. Auxiliary Building. There is no safety-related equipment in area 057. Fluid ingress into crea i 011 has no effect on the safety-related equipment. Backflow through the drainage system will i experience the flow / drain conditions described above. I l I I l l l i i -l ) I 2.1-3 l

M M M M M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 i ROOM ELEY. DRAINAGE SYSTEM DETAILS COP 9ENTS I l 20- -20' Room 020 does not have The configuration of area 020 is i Radwaste any drains. similar to area 011. Area 020 is I Control connected to corridor 015. There Panel Area are no barriers or obstructions i between area 020 and corridor 015 and similarly between corridors 015 and l 036 (area 057) (see Figure 2-2). Any discharge of fluid in area 020 will spread over a large area and eventually down to area 057 and the radwaste area sump. The minimum installed height of any safety-related equipment in this area is 9'. Safety-related equipment in area 020 l will not be affected by any fluid i ingress into this area. Backflow through the drainage system in this area is not possible since there are no floor or equipment drains. i i i i 1 l 2.1-4

m m e e e m W W M M M e M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) j AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 I l i } ROOM ELEY. DRAINAGE SYSTEM DETAILS COMENTS 043- -20' Room 043 has 2-2" floor Room 043 is adjacent to Corridor 036 High Pressure drains which drain to a 6" which has a grated floor. This grated Injection line discharging into the floor covers area 057, the Radwaste i Pump "B" Room East Decay Heat Removal Transfer Pump Area. There is a fenced Pump Room sump at el. gate between room 043 and corridor 036. (-)47'. Sump pumps P663B Any discharge of fluid in room 043 will and P664B discharge to the either drain out through the floor Miscellaneous Waste Tank, drains or flow freely into corridor T-667. The 6" line to the 036 and down to area 057 (el. -29'). sump is the coranon drain (see Figure 2-2). Area 057 has floor line used for drainage of drains which drain to the radwaste rooms 002, 043, 4. s::d area sump. This sump is located in 1 051. area 057. Any flooding is easily contained in this area. There is no 4 safety-related equipment in area 057. The minimum installed height of any safety-related equipment in room 043 is 22". Backflow tnrough the drainage system will experience the flow / drain conditions described above. Fluid l ingress into room 043 will not affect i the safety-related equipment. The redundant systems are located in room 053. Room 053 is approximately 132 feet away and is completely isolated from any flooding conditions that l might occur in room 043. ) i 2.1-5 l )

g g m M M M M M M M M M M M E R: port N3. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COMENTS 044- -20' Room 044 has 2-2" floor Room 044 is adjacent to corridor 045 l Make-up drains which drain to a and room 043. There is a door between Pump Room 6" line discharging into rooms 044 and 043. This door has a the East Decay Heat 1/2" floor clearance. Some fluid will Removal Pump Room sump at seep into room 043 from under the door. el. (-)47'. Sump pump The fluid discharged into room 043 will ~ P663B and P664B discharge experience the flow conditions 4 to the Miscellaneous discussed for room 043 (see room 043). Waste Tank, T-667 The 6" The entryway between room 044 and j line to the sump is the corridor 045 is a fenced gate. This l common drain line used for gateway has a 4" curb. This gate will drainage of rooms 002, allow unobstructed flow of fluid from l 043, 044, and 051. this room into corridor 045. Corridor 1 045 is connected to corridor 036. l There are no barriers or obstructions between these corridors. Corridor 036 J has a grated floor which will permit 1 the unrestricted flow cf fluid to area l 057 at el. -29'. Any flooding can be i easily contained in area 057. There i is no safety related equipment in area 057. Backflow through the drainage system will experience the flow / drain conditions discussed above. The height of fluid accumulation in this area is limited to the height of the 'i curb at its entrance to corridor 045. The minimum installed height of any safety-related equipment is 22". Fluid ingress into room 044 has no I effect on safety-related equipment. 2.1-6 j

M M M M M M M M M M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 i (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 1 i ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS i 045- -20' Room 045 does not have Corridor 045 adjacent to rooms 044 and Corridor any drains. Any fluid 046. There is a 4" curb between in this area will flow corridor 045 and room 044. The entry freely into corridor 036. way between corridor 045 and room 046 This area has a grated has a fenced gate. There is no curb fl oor. The grated floor or obstruction at this entryway. is over area 057. Area Corridor 045 is also connected to 057 is the Radwaste corridor 036. Corridor 036 has a Transfer Pump Area grated floor. Any discharge of fluid (el. - 29'). The fluid in corridor 045 will mostly flow to from corridor 045 will corridor 036 and down to area 057 at drain down to area 057 el. -29'. Any flooding can be easily and to the radwaste area contained in area 057. There is no 4 sump. safety-related equipment in area 057. Room 046 is a relatively small room 4 (see Figure 2-2). It has only one entryway (i.e., there are no other i doors or penetrations other than the I fenced gate mentioned above). Any i fluid entering room 046 will either a discharge down the floor drain (see ) room 046 Drainage System Details) or l flow back into corridor 045. There is no possibility of backflow through the drainage system since corridor 045 has no drains. The minimum installed i height of any safety-related equipment is 6'. Fluid ingress into this area has no effect on safety-related equipment. 2.1 -7 i l

[e \\ .-J. L. ~ M M M M M M M M M M M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COMENTS 046- -20' Room 046 has 1-2" floor Room 046 is connected to corridor 046 Seal Return drain which drains to a by an entryway. This entryway has a Cooler Room 4" line discharging into fenced gate and permits unrestricted the radwaste area sump flow of fluid from room 046 to corridor at el. (-)29'. Sump pumps 045. Any discharged fluid in room P665 and P666 discharge 046 will either drain out through the to the Miscellaneous Waste floor drain or flow freely into Tank. T-667. The 4" line corridor 045. Fluid overflowing into to the sump is the common corridor 045 will flow down to area drain line used for 057, at elevation (-)29' (see room drainage of room 046 and 045). The minimum installed height other areas of the of the safety-related equipment is 7'. Auxiliary Building. Any backflow through the drainage system will experience the flow / drain i conditions described above. Fluid ingress into this area has no effect on safety-related equipment. 2.1-8 l

W W W W M M M M M M M M M M M M M Report No. 01-0790-1476 Revision 0 l TABLE 2.1 (continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 1 i l ROOM ELEY. DRAINAGE SYSTEM DETAILS COP 94ENTS j 0 51 - -20' Room 051 has 2-2" floor Room 051 is adjacent to room 052 and Containment drains, and 1-2-1/2" floor corridors 045 and 010 (see Figure 2-2). Penetration drain which drain to a Room 051 has 4" curbs at entrances to Valve Area-6" line discharging into rooms 052 and corridor 045 (no door to l East the East Decay Heat room 052 and a fenced gate to corridor i Removal Pump Room sump 045). Room 051 has a 4" curb with a j at el. (-)47'. Sump pump door (1/4" floor clearance) at the P663B and P664B discharge entrance to Corridor 010. Any i to the Miscellaneous discharge of fluid in room 051, if not Waste Tank, T-667. The disposed through the floor drains will 6" line to the sump is overflow to the adjacent areas listed j the common drain line above. (See individual rooms and used for drainage of corridors for drainage details and rooms 002, 043, 044, flow conditions.) The height of fluid and 051. accumulation in this area is limited i to the height of the curbs at its entrance. The minimum installed height of any safety-related equipment in room 051 is 12". Any fluid backflow through the drainage system will experience the flow / drain conditions discussed above. Fluid ingress into this area has no effect on safety-related equipment. i l l l 2.1-9 l

M M M M M M M M M M M M M ] sfo b (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 i l ROOM ELEY. DRAINAGE SYSTEM DETAILS CO M NTS 052 -20' Room 052 has 2-2" floor Room 052 is adjacent to rooms 051 and Containment drains and 5-2" equipment 053. The entryway between rooms 052 Penetration drains which drain to a and 051 has a 4" curb with no door. ,l Valve Area-4" line discharging into There is a door (with a 1/2" floor West the West Decay Heat clearance) between rooms 052 and 053. Removal Pump Room sump Room 052 is also connected to rooms at el. (-)47'. Sump pump 001 and 002 by two floor HVAC P663A and P664A discharge penetrations. These penetrations have to the Miscellaneous Waste sheet metal covers and 13" high curbs Tank, T-667. The 4" line all around. The height of fluid to the sump is the comon accumulation will be limited to the drain line used for height of the curb at its entrance drainage of rooms 001, to room 051. Any discharge of fluid 052, and 053. in room 052, if not disposed through the floor and equipment drains, will i overflow to the adjacent areas listed above. (See individual rooms for drainage details and flow I conditions. ) The minimum installed height of any safety-related equipment l 1s 12". Any fluid backflow through the drainage system will experience the flow / drain conditions discussed above. Fluid ingress into this area has no effect on safety-related j equipment. l 2.1-10

M M M M M M M M M M M M M i Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS CO M NTS i 053- -20' Room 053 has 2-2" floor Room 053 is adjacent to room 052. i!igh Pressure drains which drain to a 4" There is a door with 1/2" floor Injection line discharging into the clearance between these rooms. Any Pump "A" Room West Decay Heat Removal discharged fluid is disposed of through Pump Room sump at el. the floor drains and by leakage from (-)47'. Sump pump P663A under the door into room 052. The P664A discharge to the redundant system is located in room Miscellaneous Waste Tank, 043. Room 043 is approximately 132 { T-667. The 4" line to feet away from this room and is l the sump is the common completely isolated from any flooding drain line used for e ffects. The fluid backflow through drainage of rooms 001, the drainage system is limited to the l 052, and 053 height of fluid accumulation in room 052. The minimum height of any safety equipment is 22". Fluid ingress into this area has no effect on safety-related equipment. I i I .l l 2.1-11

m m W W W W W W M M M M i Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS 103-O' Room 103 does not have Corridor 103 is adjacent to corridor i Corridor any drains. The fluid 104/105 and room 106. There is a will spread into corridor door with 3/4" floor clearance i 104/105 and Room 106. between corridors 103 and 104/105 Room 106 has 2-2" drains There is also a door with 1/2" leading to the acid clearance between room 106 and waste sump in area 057 corridor 103. Any discharge of fluid l at elevation (-)29'. in corridor 103 will overflow into The fluid in corridor the adjacent areas listed above. I 104/105 will be disposed There is no safety-related equipment in of manually. room 106 and corridor 104/105. The minimum installed height of any safety-related equipment in this area is 8". There is no possibility of backflow through the drainage system i since room 103 has no drains. Fluid i ingress into this area has no effect on safety-related equipment. l l l 1 i l i 2.1-12

M M M M M M f Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 l l I ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS i

119, O'

Rooms 119 and 120 each Rooms 119 and 120 are the East Nuclear 120-have 1-2" floor drain Service Battery rooms. The adjacent Nuclear which drain to a 4" line area is corridor 104/105. For the Service discharging to the Acid exception of a sink and an eyewash Battery Waste sump at el. (-)29'. there are no other sources of fluid Rooms-East Sump pumps P967A and B inside these rooms. Any discharge discharge to the Spent of fluid from these sources is Regenerant Tanks, T-689A disposed of through the floor drains. and B. The 4" line to The doors to corridor 104/105 have the sump is the common 1/2" door sills. The batteries are drain Ifne used for installed approximately 2' above the drainage of rooms 119, floor level. Fluid backflow through 120, and other areas of the drainage system will not pose any the Auxiliary Building. hazard to the safety-related equipment in these rooms. Fluid ingress into this area has no effect on i safety-related equipment. l i t i 2.1-13 e

M M M M M M M Report No. 01-0790-1476 4 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROGM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS 121-0' Room 121 has 1-2" Room 121 is adjacent to corridor Switchgear equipment drain which 104/105. There are two double doors Room drains to a 4" line connecting this room to the corridor i discharging to the area. The doors have a 1/2" door sanitary waste sump at sill and a 1/4" floor clearance. el. (-)20'. Sump pumps Fluid ingress into this area has no P968A and B discharge effect on safety-related equipment. to the sewer line. The 4" line to the sump is the common drain line used for drainage of rooms 121, 124, 214, 217, 343, and other areas of the Auxiliary Building. 1 I I t ) i I 2.1-14 -u m - ~ s -a

M M M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS 124-O' Room 124 has 1-2" Room 124 is adjacent to corridor Switchgear equipment drain which 104/105. There are two sets of double Room drains to a 4" line doors connecting this room to the discharging to the corridor area. The doors have a 1/2" sanitary waste sump at door sill and a 1/4" floor clearance. el. (-)20'. Sump pumps Fluid ingress into this area has no P968A and B discharge effect on safety-related equipment. to the sewer line. The 4" line to the sump is the common drain line used for drainage of rooms 121,124, 214, 217, 343, and other areas of the Auxiliary Building. 1 l 2.1-15 x

M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 R00M ELEY. DRAINAGE SYSTEM DETAILS COMMENTS i

125, O'

Room 125 has 1-2* floor Rooms 125 and 126 are the West Nucl~ ar e 126-drain which drains to Service Battery rooms. The adjacent Nuclear an 8" line discharging area is corridor 104/105. For the Service into the polishing exception of a sink and an eyewash Battery demineralizer and there are no other sources of fluid Rooms-West make-up demineralizer inside these rooms. Any dischar.ge area sump at el. O' of of fluid from these sources is the Turbine Building. disposed of through the floor drains. Sump pump P965A and B The doors to corridor 104/105 have discharge to the 1/2" door sills. The batteries are Regenerant Holdup Tanks, installed approximately 2' above the T-950A and B. The 8" floor level. Fluid backflow thrcugh line to the sump is the the drainage system will not pese any common drain line used hazard to the safety-related equipment i for drainage of rooms in these rooms. Fluid ingress into 125, 126, 220, and some this area has no effect en grade level areas of the safety-related equipment. Turbine Building. i l 2.1-16

M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Centinued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS 130-O' Room 130 has 2 quench Room 130 is Diesel Generator Room Diesel pits and 1-2" equipment "B". The quench pit located in this Generator drain which drain to a 6" room are filled with gravel and have Room "B" line discharging into the 2-2" drain pipes. The redundant condenser pit sump at system is located in room 132 el. (-)l0' of the Turbine and is isolated from this room. The Building. Sump pumps quench pit drain lines of the two P964A and B discharge to rooms are connected. However, the the dilution sump. The gravel in the pit will severely 6" drain line to the restrict the backflow through the condenser pit area sump is drain pipes. The redundant system the common drain line used will remain available. The excess for drainage of rooms 130, discharged fluid from room 130 will 132, and some areas at the overflow into the Turbine Building. grade level of the Turbine The Turbine Building has an ample Building. number of ficw drains and is a relatively large area (see Turbine Bldg., Table 2.3). Therefore, the possibility of fluid accumulation is very unlikely. 2.1-17

M M M M M M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS C0f0ENTS 132-O' Rccr.130 has 2 quench Room 132 is Diesel Generator Room Diesel pits ami 1-2" equipment "A". The quench pit located in this Generator drain which drain to a 6" room are filled with gravel and have Room "A" line discharging into the 2-2" drain pipes. The re<iundant condenser pit s:mp at system is located in room 130 el. (-)l0* cf the Turbine and is isolated from this room. Building. Surep pumps The quench pit drain lines of the two P964A and B discharge to rooms are connected. However, the the dilution sump. The gravel in the pit will severely 6" drain line to the restrict the backflow through the condenser pit area siw; is drain pipes. The redundant system the com:on drain line used will remain available. The excess for drainage of rooms 130, -discharged fluid from room 132 will 132, and some grsJe level overflow into the Turbine Building. aren of the Turbine The Turbine Building has an ample Eufiding.

r. umber of flow drains and is a relatively large area (see Turbine Bldg., Table 2.3).

Therefore, the possibility of fluid accumulation is very unlikely. 2.?-18

M M M M M M M M M M M Repcrt No. 01-0790 1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 -- QUEST _IGH 3 ROOM ELEY. DRAINAGE SYSTEM DETAILS CCMMENTS 204-20' Room 204 has 8-2" floor The adjacent area to rcom 207 Ts Air drains which drain to a corridor 207. The doces to corridbr Conditioning 6" line discharging into 207 have 1/2 floor clearance. Any Equipment the sewer cutside of the fluid ingress in this area has no Room Auxiliary Building. effect on safety-related equipment. The minimuri installed height of cr.y safety-related eculpment in this ares is 5'. Fluid ingress into this area has no effect on safety-related equipment. 208-20' Room 208 does not have The adjacent area to rcom 208 is room Duct Space any drains. 211. There are no foors,-curbs, or barriers between the two -rooms. Fluid ingress into this area nas n0 effect on safety-related equipment. 211-20' Room 211 does not have The adjacent area's to room 211 are Ventilation any drains, rooms 208 and 211, and corridor 207. Equipment Room 211 is completely cpen to room Room 203 However, it is separated froai room 209 and corridor 207 by doors with 1/2" floor clearance (see Figure 2-4). The equipment in roon. 211 is mounted on 5" concrete pads. Fluid ingress fato this area nas no effect on safety-related equipment. 2,1-19

m m M M M M M M M M M M i Report No. 01-0793-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY SUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 { ROOM ELEY. DRAINAGE SYSTEM DETAILS C0 K NTS 209-20' Room 209 does not have The adjacent areas to room 209 are Electrical any drains. room 211 and corrioor C07. There Penetration are doors between these roovrs. The Room doors have 1/2" floor clearances. The equipment in this roo6s is located on 6" concrete pads. Fluid ingress into this am has no effect on tafety-related equipment.

212, 20' Roon:s 212 aird 213 do not The adjacent areas to these rooms 213-have any drains.

are corridor 207 and roon 214 (see AC/DC Panel Figure 2-4. The door to corridor Rooms-East 207 has 1/2" (foor sill anr11/4" floor clearance. The redandant systems are located in root.s 210 and 219. The eguipment in this room is installed on 4 concrete pads. Fluid ingress into this area has no eff' ct on e safety-related equipment.

218, 20' Rooms 218 and 219 do not The adjacent areas to there rooms 219-have any drains.

3re carridor 207 ar-d 217 (see Figure AC/DC Panel ?-4). T!:e doer to corrider 207 has Rooms-West 1/2" door sill and a 1/4" floor clearance. The redundant system is located in 'ecors 212 a.1d 213. The equipmer.t is irrstalled on 4" concrete pads. Fluid ingtess into thit crea has no eff'ec^ on safety.rD ated equi < cent. 2.1-20

M M M M M M M M M M M M M M M M Report No. 01-0790-1476 Pewision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - CUESTION 1 l ROOM ELEY. CRAINAGE SYSTEM DETAILS COWENTS 214-20' Room 214 has 1-2" The adjacent areas to this room are l Electrical equipment drain which corridar 207, and rooms 213 and 217. Equipment drains to a 4" line There is a set of double doors l Kocas-East discharging to the connecting this roon: to corridor 207. sanitary waste sump at These doors have 1/2" door sills and el. (-120'. Sump pumps 1/4" clearances. The door to room P968A and B discharge 213 has a 1/2" floor cleararce. The to the sewer ifne. The door to room f17 has a floor clearance 4' line to the sump is of less than 1/8". Fluid ingress into the conmon drain line this area has no effect on safety-used for drainage of related equipeent, rooms 121, 124, 214, 217, 343, and other areas of the A3xiliary Building. I l l 2.1-21

M M M M M M M M M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COP 9 TENTS 217-20' Room 217 has 1-2" The adjacent areas to this room are Electrical equipment drain which corridor 207, and rooms 219 and 214 Equipment drains to a 4" line There is a set of double doors Rooms-West discharging to the connecting this room to corridor 207. sanitary waste sump at These doors have 1/2" door sills and el. (-)20'. Sump pumps 1/4" clearances. The door to room 219 P968A and B discharge has a 1/2" floor clearance. The door to the sewer line. The to room 214 has a floor clearance of l 4' line to the sump is less than 1/8". Fluid ingress into the conunon drain line this area has no effect on safety-used for drainage of related equipment. rooms 121, 124, 214, 217, 343, and other areas of the Auxiliary Building. I 1 2.1-22

W W W W M M M M M M M R; port No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COP 9 TENTS 220-20' Roa: 220 has 3-2" floor The adjacent area to room 220 is Station drains which drain to corridor 207. The door to corridor Battery an 8" line discharging 207 has a 3/4" door sill and less than Room into the polishing 1/8" floor clearance. The batteries i demineralizer and are located on 2' high stands. make-up demineralizer Fluid ingress into these areas has no area sump at el. O' of effect on safety-related equipment. the Turbine Building. Sump pumps P965A and B discharge to the regenerant holdup tanks, T950A and B. The 8" line to the sump is the common drain line used for drainage of Rooms 125, 126, 220 and some areas of el. O' of the Turbine Building. 2.1-23

Report No. 01-0790-1476 R;visien 0 i TABLE 2.1 i (Continued) l AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS 333-40' Room 333 does not have Technical any drains. Support Center 338-40' Room 338 does not have Room 333 is the technical support Computer any drains. center. Rooms 338 through 344 are R:om the computer room and control room. There are fire suppression water 339-40' Room 339 does not have system piping routed through rooms Control any drains. 333, and 340, 341, 342, 343 and 344. Room Any accidental discharge will be detected quickly and manual action 340-40' Rom 340 does not have can be taken to prevent the flow I Shift any drains. of water. The safety-related Supervisor equipment in the computer room Office is installed on 6" concrete pads. In the Technical Support Center, all 341 - 40' Room 341 does not have equipment is mounted on l' raised Conference any drains. floor. Fluid ingress into this Room area has no effect on safety-related equipment. 342-40' Room 342 does not have Kitchen any drains. 2.1-24

W W W W W Report No. 01-0790-1476 Revision 0 TABLE 2.1 (Continued) l AUXILIARY BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 l i l ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS 4 343-40' Room 343 has 1-2" floor See Connents previous page. Toilet drain which drains to l a 4" Ifne discharging to the sanitary waste sump at El. (-)20'. Sump pumps P%8A and B discharge to the sewer line. The 4" line to the sump is the common drain line used for drainage of Rooms 121, i 124, 214, 217, 343 and other areas of the j Auxiliary Building. I i 344-40' Room 344 does not have See Comments previous page. Corridor any drains. J I i i i l 2.1-25 l

W W M M Report No. 01-0790-1476 Revision 0 TABLE 2.2 NUCLEAR SERVICE ELECTRICAL BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEV. DRAINAGE SYSTEM DETAILS COP 94ENTS 061, -20', The Train B Cable Shaft Rooms 061,148 and 238 represent the 148, & l'-6", and Tunnel has 1-4" floor Train B Cable Shaft and Tunnel area. 237-21'-6" drain at -20' elevation. The safety-related equipment is Train B This floor drain dis-installed at least 2' above the Cable Shaft charges to a 4" common floor. Fluid ingress into this area and Tunnel sewer connection pipe has no effect on safety-related which after treatment equipment. is released into the l Retention Basins (Y-951 and Y-952) and eventually discharged to the Final 4 Effluent Basin.

062,

-20', The Train A Cable Shaft Rooms 062,149 and 239 represent the 149,a l'-6", and Tunnel has 1-4" floor Train A Cable Shaft and Tunnel area. 239-21'-6" drain at -20' elevation. The safety-related equipment is Train A This floor drain dis-installed at least 2' above the Cable Shaft charges to a 4" connon fl oor. Fluid ingress into this area and Tunnel sewer connection pipe has no effect on safety-related which after treatment equipment. is released into the Retention Basins (Y-951 and Y-952) and eventually discharged to the Final Effluent Basin. 1 i l 2.2-1

M M M M Report No. 01-0790-1476 Revision 0 TABLE 2.2 (Continued) NUCLEAR SERVICE ELECTRICAL BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ) 4 i ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS ~ 231-21'-6" Corridor 231 has 1-4" Corridor 231 is connected to corridor i Corridor floor drain at elevation 141 at el.l'-6" by an open stairway 1 21 '-6". Any excess fluid (i.e. no curbs, doors, etc.). Fluid will drain to the 4" sewer ingress into this area has no effect connection pipe leading on safety-related equipment. to the Retention Basins j (Y-951 and Y-952) and ultimately to the Final Effluent Basin. l 236-21'-6" The Train B Mechanical Room 234. Train B Electrical Equipment Train B Equipment Room has 2-4" Room is adjacent to room 236. Room Mechanical floor drains at elevation 234 has water tight doors and is not Equipment 21'-6". Any excess fluid affected by conditions in room 236. Room will drain to the 4" sewer All equipment is located on 6" connection pipe leading concrete pads. The redundant i to the Retention Basins systems are located in room 237. (Y-951 and Y-S32) and Fluid ingress into this area has no ultimately to the Final effect on safety-related equipment. Effluent Basin. f j 2.2-2

i W W W W W W R:p3rt N3. 01-0790-1476 Revision 0 TABLE 2.2 (Continued) NUCLEAR SERVICE ELECTRICAL BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 ROOM ELEV. DRAINAGE SYSTEM DETAILS COMENTS 237-21'-6" The Train A Mechanical Room 235, Train A Electrical Equipment Train A Equipnant Room has 2-4" Room is adjacent to room 237. Room Mechanical floor dcains at elevation 235 has water-tight doors and is not Equipment 21'-6". Any excess fluid affected by conditions in room 237. Room will drain to the 4" sewer All equipment is located on 6" connection pipe leading concrete pads. The redundant to the Retention Basins systems are located in room 236. l (Y-951 and Y.152) and Fluid ingress into this area has no ultimately to the Final effect on safety-related equipment. 1 Effluent Basin. 362-40' Per reference 11.2, All equipment is mounted on a Computer room 362 has 1-4" 14" raised floor. Redundant j Room B drain at elevation systems are located in room 363. 40'. Any excess fluid Room 363 is isolated frem the will drain to the 4" sewer conditions in room 362. Fluid ingress connection pipe leading into this area has no effect on i to the Retention Basins safety-related equipment. (Y-951 and Y-952) and ultimately to the Final i Effluent Basin. I 2.2-3 1

W W W W W W W W Rep:rt No. 01-0790-1476 Revision 0 TABLE 2.2 (Continued) NUCLEAR SERVICE ELECTRICAL BUILDING - RESPONSE TO GENERIC ISSUE '/7 - QUESTION 1 ROOM ELEV. DRAINAGE SYSTEM DETAILS COMMENTS 363-40' Per reference 11.2, None All equipment is mounted on a 14" Computer room 362 has 1-4" raised floor. Redundant systems { Room A drain at elevation are located in room 362. Room 362 is 40'. Any excess fluid isolated from conditions in room 363. i will drain to the 4" sewer Fluid ingress into this area has no connection pipe leading effect on safety-related equipment. to the Retention Basins (Y-951 and Y-952) and ultimately to the Final Effluent Basin. l l l 2.2-4

W W W W W W W W Report No. 01-0790-1476 Revision 0 TABLE 2.3 TURBINE BUILDING - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 'l ROOM ELEY. DRAINAGE SYSTEM DETAILS COMENTS l Turbine O', The Turbine Building has Any discharged fluid due to a line Building 20' & 48-4" floor drains and break will mostly drain down to the l 40' 35-4" equipment drains at condenser pit sump which will be elevation O', no floor discharged to the dilution sump. drains (the 20' elevation Fluid ingress into this area has no has grated floor) and 8-4" effect on safety-related equipment. l equipment drains at elevation 20', and 79-4" floor drains and 16-2" equipment drains at elevation 40'. These drains discharge to j either the make-up and demineralizer sump at i elevation O' or the condenser pit sump at elevation -10'. The i make-up and demineralizer sump pumps P965A and B discharge to the Regen-erant Holdup Tanks T950A and B and the condenser pit sump pumps P964A and B discharge to the dilution sump. 2.3-1

M M M M M M M M M M i Report No. 01-0790-1476 Revision 0 TABLE 2.4 REACTOR YARD AREA - RESPONSE TO GENERIC ISSUE 77 - QUESTION 1 i ROOM ELEY. DRAINAGE SYSTEM DETAILS COMMENTS Nuclear O' The Nuclear Service Raw The NSRW pump houses are located on the Service Water Pump Houses do not north end of the reactor yard area. Raw Water have any drains. Flooding is possible due to an Pump Houses expansion joint /line failure in this [ Reactor Yard area. In the case of such an event, Area] the function of the NSRW pump is lost. Therefore, the impact of flooding on the affected system is not of concern. The redundant system is located 430' away from the first area and will not be affected by conditions in the first pump room. Therefore, the redundant system will remain available. i 1 Auxiliary O' The Auxiliary Feedwater The Auxiliary Feedwater Pump area I Feedwater Pump area does not have is located in the Reactor Yard - 1 Pump Area any drains. However, the Tank Farm area. This area is open to [ Reactor Yard Tank Farm area nearby has the surrounding areas. Any discharge Area - Tank 1-12" floor drain. This of fluid will be dispersed quickly and Farm Area] floor drain discharges to spread over a large area. Therefore, the Final Effluent Basin. fluid cannot accumulate in this area. The minimum installed height of any safety related equiment in this area is 2'. l 2.4-1

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~

Impell Report No. 01-0790-1476 Revision 0 k x M Esi!No*5$1 T1 ApERTUM CARD l Also Availa131e ou Aperture Card l_ I w-LEGENDi W5 "

3 FLDDR DRAIN O EQUIPMENT DRAIN Y-RELATED ROOMS) 0" 1P ROOMS g(,c4ogol% -of ACAD/MAUX-47/RC W*

s. O sY M Q DHR PUWP ROOM SUWP j TO EL(-)47*-0* WEST ':3 h A- [0 51] 10531 3 m 0W Et o'- 0 TO EL(-)47*-O" ROWWS 121.124 FROM EL20*-0* EAST DHR PUWP ROOWS 214.217 ll ROOM SUMP FROM EL40*-0* ~ ' ROOM 343 C 10561 10101 10141 1017l j r = F Irivi ~ SAMTARY WASTE SUMP ,s l AN; SM otnaps p b LoE j to22J Lo16J g qp P9CSA/B l E C loS51 [0541 1 J r' ] 10181 E m0W ELo*-0* ROOM 120 \\ 7 T-- ~1 F w FIGURE 2 AUXILIARY BUILDING DRAINS (S ELEVATION (- m h

/, Impell Report No. 01-0790-1476 Revision 0 (U m [0421 ggq 10461 a g 7-L ir 10411 l209] =6 4 2 10431 10441 l II - l0361 [o40[ ll A & ) b RADWASTE AREA SUMP AT EL(-)29*-0* AND M M 030 M 032 M M Q SUMP PUMPS P665 & P666 [039] g 11071 FROW ELC'-0* R00W 11s Lolal Esl ~ L ~ l0281 1026l 10371 10201 i F l31 L ~ ACD WASTE SUMP 1023l f024l AT EL(-)29'-0* { AND SUMP PUMPS n-ee67A/a gg M""*' Card -2 Apertare AFETY-RELATED ROOMS) teogno: ) 2 0'- 0" . n. coa onus O EQUlPMENT DRAIN ACAD/MAUX-20/RC % oCo9 ol % oA;

0 TD TUREINE BLDG. ELC-)10' CONDENSER PIT SUMP AND SUMP PUMP 3 P964A/B si I Llea.J s _$-\\ 4 (, 1138 lie 7I c '{ 11301 l131 3 11291 M,[ a n _s ~, e- _ TD TURBINE BLLG, ELC' PDL15H1NG a p t1 w_ DEM'R & II25l MAKE-UP DEMIN. AREA SUMP & SUMP ll PUMP 3 965A/B I, g \\ A- = v 2 s II #' FRDM EL.20' U RCDM 22D Jq\\ p l123] n lieel s q I1261 %\\ r sN TD E u ->ac -c-SANTARY VASTE SUMP L ~ FIGURE 2-3 [ AUXILIARY BUILDING DRAINS (SAf i ELEVATION O' y ~ r' .1 W enwust

/. Impell Report No. 01-0790-1476 Revision 0 TD SEVER J l l i. A l L, a > ua = l1131 m b N1115 l N i1161 s ei b it361-a n RCM ELEC-l 110 I RCCM 204 g 2 -l r m i ~ uvJ l119l llllll 11341 y T vast 3 N-TC Eu->E9- -r a EL,Ee-g Agc g acen ge 1106] (120] FRCH ELEC' f O ure; iPERTURE g 5, CARD l' 3I f.n. !, IE2fd2TE Also Xvailable On i Aperture en ' 8" LEGEND E FLDDR DRAIN

ETY-RELATED ROOMS) o couiescuT nRain F0" a cuencs e2T i

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p Impell Report No. 01-0790-1476 Revision 0 b KPERTURE CARD Also Xvailable On Wperture Card I / Ol m l A 12101 12091 12031 (F] V s yc E 12071 g 1 g a .a I 12121 5 reTs1 12141 ~ FLDDR DRAIN 3 IN RCDM 204 LRAIN TD LINE3 E E SHDVN AT GRADE LEVEL E a ) y LAI fg SANITARY LEGEND TY-RELATED ROOMS) E FLODR DRAIN 0" o courmcu1 naam i ACAD/MAUX20/RC ____o

~ w 0 E 13241 g a 1322I I [ n 13251 13271 I 1349] ~ D ll ll lk 1345l lg 13461 13281 = ] O i _s c=_. - s TD ELC-)20' 3ANITARY J' VASTE SUW'"M 13431 N b 7-L n,I ~ E 13441 134e1 133el 13411 13391 1 I 1340] U CONTROL ROOM p r i FIGl AUXILIARY BUILDING DRA: ELEVA' 1

7 l Impell Report No. 01-0790-1476 Revision 0 l y-6%t. i I351I 'dSc" L r U U q F l3121 r g 3, , gllll i m E (3191 13161 [214] }13091 13291 -a u = [229] ,3 3, --= y-13311 I2El 1302) Tl = i.i= APERTURE 13041 M 1306l ggy g J i Also Xvailable On Xperture Card JRE 2-5 NS (SAFETY-RELATED ROOMS) LEGEND: FION 40'-0" . rLODR DRAIN ACAD/MAUX40/RC Sto o toFo l% " s. I L. r f,,a#'jd A h'#< l l' / s %,r'5<{< k, ~,' N sq h, E i's>k -s, 9 k, W

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y' i ) L .=t ' - b! }]OTES : ~ h. L~~~ ~ BR0t2Nf iMH ARE RuntDHD l ',*h lAl t'esicRETE.' A,,, s 50LlO L/ MEG "MRK tkPGSED 3.. z.. y OR.5PSPCUDED RELQM TNK BLAA. N-k-Tned bhWW/W is A/Or TO Mt wagwYRD 'Yms DMaw1N6 IL /N7ENDCD TO h,% PM099IDE AM OvfMngL gCAsgs4g

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co.e6 Impell Report No. 01-0790-1476 Revision 0 Figure 2-9 7 5 RETENTION BASIN AREA SIMPLIFIED DIAGR AM

I Impe11 Rtport No. 01-0790-1476 Revision 0 l V .i d IS ". C* % -- j' I f *stw 40 ,J04 8 2 J.# #8 4L I

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l Impe11 Report No. 01-0790-1476 Revision 0

3.0 REFERENCES

l 1. Letter from John E. Stolz (NRC) to Mr. R. J. I Rodriguez (SMUD), dated September 6,1985.

Subject:

Generic Issue 77, " Flooding of Safety ) Equipment Compartments by Backflow through Floor Drains." 2. Letter from R. J. Rodriguez (SMUD) to Hugh L. Thompson, Jr. (NRC), dated October 18 1985, RJR I 85-504.

Subject:

Generic Issue 77, 3 Flooding of Safety Equipment Compartments by Backflow througn Floor Drains." 3. USAR July 1982 Including Amendment 3, August 26, 1985, Pincho Seco Nuc1 car Generating Station, Sacramento Municipal Utility District. 4. SMUD Calculaticn Z-RB-M 1472 Revision _0, " Time vs Recctor Building (RB) Flood Level." 5. P&ID's 5.1 M-592, Revision 18, Hiscellaneous Systems. 6. 10CFR 50.49 Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants 7. SMUD Calculation 2-EQP-E0165, Revision 3, , g E " Identification of Epipment Required for l l Accident Mitigation 8. SMUD Design Guides l B.1 SMUD Design Guide 5208.30, dated 9/13/85, Equipment and Floor Drainage Systems. 8.2 SMUD Design Guide 5208.31, dated 9/13/85, Routing and Plumbing and Drainage Services. B.3 SMUD Design Guide 5207.27, dated 9/19/85, Plumbing Design Manual. 3-1

I Impell Report Noe 01-0790-1476 Revision 0 I 9 Occurrence Description Report 9.1 0.D.R. dated 10/28/75: DHS-522, Decay Heat System "B" 9.2 0.D.R. dated 5/5/79: Pump Seal Leakage 9.3 0.D.R. dated 3/18/76: Failure of Weld on Plan Eley. O'-0" to 20'-0" Auxiliary Building I Make-up Pump Suction Bypass g 9.4 0.D.R. dated 10/28/77: DHS-523 Weld Leak 9.5 0.D.R. dated 8/22/76: DH System Pump "B" E 9.6 0.D.R. dated 1/17/80: DHR Pump Seal E Leakage 9.7 0.D.R. dated 8/4/80: Water Leakage from Spent Fuel Pool I 9.8 0.D.R. dated 6/22/78: Decay Heat Removal Pump "B" 9.9 0.D.R. dated 8/27/81: Excessive leakage I 9.10 0.D.R. dated 9/18/81: Decay Heat 9.11 0.D.R. dated 5/12/81: Spill of [ Contaminated Liquid 9.12 0.D.R. dated 12/3/82: Decay Heat System 9.13 0.D.R. dated 11/18/82: D. G. Fuel Oil E Storage Tank Pump 9.14 0.D.R. dated 1/20/83: Miscellaneous Water Holdup Tank 9.15 0.D.R. dated 9/9/85: PLS System 9.16 0.D.R. dated 9/19/83: Decay Heat System 9.17 0.D.R. dated 12/15/85: PI 23601 Root Yalve (Make-up Pump) 9.18 0.D.R. dated 12/29/85: Decay Heat Pump P-261B 9.19 0.D.R. dated 12/26/85: P-236 Make-up Pump 9.20 0.D.R. dated 2/7/86: ECCS System TSC Water Suppression pilot valve

10. Uniform Plumbing Code 1982 Edition International Association of Plumbing and A

Mechanical Officials. g

11. Nuclear Service Electric Building Calculations 11.1 Z-CDS-M0505 Revision 0 NSEB Drain Piping M-351 SH 1 thru 3 I

I 3-2

. -.. ' A.: '.L-.--. L-g Irpn11 Report No. 01-0790-1476 Revision 0 I 11.2 Z-FPS-M0308 Revision 2 Drainage Flow Requirement for NSEB 11.3 Z-FPS-M0312 Revision 0 Determination of Available Fire Water I Supply for NSEB and DG Building

12. SMUD Calculations Z-EQP-E0197, Revision 4, I

Environment Determination for Electric Equipment Important to Safety. = 3

13. Rancho Seco Nuclear Generating Station, Plumbing i

E and Drainage Drawings. 13.1 M-340 Revision 4 I Plan Elev. 40'-0" to 60'-0" Auxiliary Building 13.2 M-341 Revision 11 E Plan Elev. 20'-0" to 40'-0" Auxiliary B Building 13.3 M-342, Sh.1, Revision 15 ~ E Plan Eley. 0 -0" to 20'-0" Auxiliary a g Building 13.4 M-342, Sh. 2 Revision 0 13.5 M-343 Revision 5 Plan Eley. (-)20'-0" to O'-0" Auxiliary Building 13.6 M-344 Revision 1 I Plan Eley. (-)47'-0" to 20'-0" Auxiliary Building 13.7 M-345 Revision 8 Partial Plan Auxiliary Building I 13.8 M-348 Revision 4 Soil, Waste and Vent Riser Diagram Auxiliary Building I 13.9 M-349 Revision 5 Cold and Hot Water Riser Diagram Auxiliary Building 13.10 M-350 Revision 7 I Contaminated and Acid Drains Riser 1 Diagram Auxiliary Building 13.11 M-351, Sh.1. Revision 0 Isometric Diagram Plumbing at Elev. 21'-6" N.S.E.B. 13.12 M-351, Sh. 2, Revision 0 Isometric Diagram Plumbing at Elev. 48'-0" H.S.E.B. 3-3

Impell R port No. 01-0790-1476 Revision 0 13.13 M-351, Sh. 3. Revision 0 Isometric Diagram Plumbing at Elev. l'-6" I and 40'-0" N.S.E.B. 13.14 M-367 Revision 7 Plan at Elev. O'-0" to 40'-0" Turbine Building 13.15 M-368 Revision 4 Plan Below Grade Turbine Building

14. Bechtel Calculation No. 991-1-2, " Equipment Qualification Outside Containment," dated October 19, 1984.

15. Bechtel Calculation No. 991-1-0, " Equipment Qualification P-T Profiles, Outside Containment," dated October 1,1980.

16. Bechtel Calculation No. M21.30-370, " Auxiliary Steam Line 61250-6"-GB Break Blowdown," M.T.

HSU, dated October 19, 1984.

17. SMUD Calculation No. Z-EQP-E0208, "HELB Conditions Above Grade Level of Auxiliary Building," Revision 1.

I

18. SMUD Calculation No. Z-EQP-E0209, " Letdown Line Break Analysis," Revision 3.

19. SMUD Calculation No. Z-EQP-E0283, "HELB I

Conditions in the Reactor Yard, Turbine Building l and Spent Fuel Building," Revision 1. l 20. Impe11 Calculation No. 221-001, " Generic Issue 77, Walkdown Data Sheets," Revision 0, 1I 3-4 c-r ---.,_.__n_.- n,, .n.._ -,. _,. -, - _ _., -., _.. -}}

ML20141D575

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ML20141D575

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1.0 INTRODUCTION

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