Text

Forwards Evaluation of Compliance W/App R to 10CFR50, Sections Iii.G,Iii.J,Iii.L & Iii.O Re Fire Protection Program.Encl Identifies & Justifies Differences Between Existing Plant Design Features & Requirement Specs
	ML20031B904
Person / Time
Site:	Sequoyah
Issue date:	10/01/1981
From:	Mills L; TENNESSEE VALLEY AUTHORITY
To:	Adensam E; Office of Nuclear Reactor Regulation
References
	NUDOCS 8110060202
	Download: ML20031B904 (62)
	v • d • e

{{#Wiki_filter:, TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II October 1, 1981 k a // (/ Director cf Nuclear Reactor Regulation g 3 p Attention: Ms. E. Adensam, Chief 007 Livensing Branch No. 4 %p*@0 (g @5. Division of Licensing 8; 44 8 g 8/ U.S. Nuclear Regulatory Commission 4fy Washington, DC 20555 g F

Dear Ms. Adensam:

c3 In the Matter of ) Docket Nos. 50-327 Tennessee Vallei Authocity ) 50-328 Enclosed is TVA's response to the Sequoyah Nuclear Plant (SNP) unit 2 operating license, Amendment 2, condition 2.C(13)c concerning TVA compliance with Sections III.G, III.J, III.L, and III 0 of Appendix R to 10 CFR Part 50. As required by condition 2.C(13)c, TVA has evaluated the plant design, and the enclosure identifies and justifies differences between existing features and those specified in III.G, III.J, III.L, and III.0 of Appendix R to 10 CFR Part 50. As previously discussed with C. Stahle of your staff, we would like to meet with your staff at their earliest convenience to discuss the enclosed recponse. Very truly yours, TENNESSEE VALLEY AUTHORITY 'Olhf { L. M. Mills, Manager Nuclear Regulation and Safety Sworn to and subsce bed before me this/ day of b 1981 00s09% 'N. WAN Notary Public ~ ' ~ ~ J My Commission Expires i Enclosure oV 68 8110060202 011001 1 4l l / PDR ADOCK 05000327 F PDR An Equal Opportunity Employer i

t s 1 of 9 ENCLOSURE SEQUOYAH-NUCLEAR PLANT 10 CFR 50 APPENDIX R EVALUATION In accordance with condition 2.C.13(c) of the Sequoyah Nuclear Plant unit 2 operating license, TVA has evaluated the plant design against the requirements of 10CFR50, Appendix R, Sections III.G, III.J, III.L, and III.O. Based on this evaluation, we contend that with one modification to the reactor coolant pump oil collection system compliance will be achieved with the intent of these sections. The following information is offered in support of our contention. A. Section III.G Reanirements 1. Fire protection features shall be provided for structures, systems, and components important to safe shutdown. These features shall be capable of limiting fire damage so that: a. One train of systems necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control station (s) is free of fire damage; and b. Systems necessary to achieve and maintain cold shutdown from either the control room or emergency control station (s) can be repaired within 72 hours. 2. Except as provided for in paragraph G.3 of this section, where cables or equipment, including associated non-safety circuits that could prevent operation or cause maloperation due to hot shorts, open circuits, or shorts to ground, of redundant trains of systems necessary to achieve and maintain hot shutdown conditions are located within the same fire area outside of primary containment, one of the following means of ensuring that one of the redundant trains is free of fire damage shall be provided: a. Separation of cables and equipment and associated non-safety circuits of redundant trains by a fire barrier having a 3-hour rating. Structural steel forming a part of or supporting such fire barriers siall be protected to provide fire resistance equivalent to that required of the barrier. b. Separation of cables and equipment and associated non-safety ~. ~ ~ " .. _ circuits of redundant. trains by a horizontal distance of. _ Z _. _. 77_ - - more than 20 feet with no intervening combustible or fire hazards. In addition, fire detectors and an automatic fire L___ suppression system shall be installed in the fire area; or o^ . +., k We

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1 g 2 of 9 c. Enclosure of cable and equipment an d associated non-safety circuits of one redundant train in a fire barrier having a 1-hour rating. In addition, fire detectors and an automatic fire suppression system shall be installed in the fire area. Inside noninerted containments, one of the fire protection means specified above or one of the following fire protection means shall be provided: d. Separation of cables and equipment and associated non-safety circuits of redundant trains by a horizontal distance of more than 20 feet with no intervening combustibles or fire hazards; e. Installation of fire detectors and an automatic fire suppression system in the fira area; or f. Separation of cables and equipmeet and associated non-safety circuits of redundant trains by a moucombustible radiant energy shield. 3. Alternative or dedicated shutdown capability and its associated circuits, independent of cables, systems or components in the area, room or zcne under consideration, shall be provided: a. Where the protection of systems whose function is required for hot shutdown does not satisfy the requirement of paragraph C.2 of this section; or b. Where redundant trains of systems required for hot shutdown located in the same fire area may be subject to damage from fire suppression activities or from the rupture or inadvertent operation of fire suppression systems. In addition, fire detection and a fixed fire suppression system shall be installed in the area, room, or zone under consideration. TVA Response TVA has performed a fire hazard analysis for Sequoyah Nuclear Plant in accordance with the requirements of Branch Technical Position ASB 9.5-1, Guidelines for Fire Protection for Nuclear Power Plants.' (BTP 9.5-1). A safe shutdown analysis was included in this process. The analysis and resulting modifications were documented in the letter from L. M. Mills to L. S. Rubenstein dated October 23, 1979. See Appendix A for a copy of this documentation. As a result of the fire hazard analysis, fire suppression and - --- -detection systems have been added, compartmentation has been improved,- - --- fire retardant cable coatings have been added, and a number of safe ~ shutdown circuits have been modified. These features were intended to - limit fire damage'so that one train of systems necessary to achieve -w . *[*. ^' r e yy --y. w ,u.r.- w - y -+------g-.-r-

t 3 of 9 safe hot plant shutdown from either the main control room or the auxiliary control stations are free from fire damage. In addition, systems requi~ed to achieve and maintain cold shutdown can either be repaired or casualty procedures implemented within 72 hours. All equipment which was relied upon to achieve safe plant shutdown in the analysis is capable of being powered from the onsite emergency diesel generators. Therefore, a fire concurrent with the loss of all offsite power has no adverse effect on the S:quoyah safe plant shutdown capability. TVA's analysis initially considered divisional circuits associated with electrical components relied on for safe shutdown. Nondivisional associated circuits have more recently been evaluated and the following has been determined. 1. All nondivisional cables associated with equipment and components required to achieve safe plant shutdown in the event of fire are isolated by coordinated circuit breakers or fuses. These devices protect the function of the safety circuit in the event of fire damage to the ncnqualified associated circuit. 2. When nonqualified signals are used in the power or control circuitry for components required for shutdown in event of fire, they provide anticipatory or interlock signals for normal plant operation. The signals are arranged such that any fail 7re of the nonqualified circuit, such as a short or open circuit, will not adversely affect the safety circuit function. 3. The only nondivisional cables routed to components required to achieve and maintain safe shutdown in the event of fire are those for monitor lights or similar functions. These cables are not terminated in the control circuits of the devices. Therefore, if these cables were destroyed by fire, the only loss would be the contacts to which the monitor lights or similar circuit is connected. The control of the safety function of the component will not be impaired. The NRC staff imposed on TVA the following separation requirements for areas outside containment during a fire protection review meeting on February 12, 1979: 1. Relocate one or both divisions of c J..its required to achieve and maintain safe plant shutdown, in the vent of fire, to mairtain a minimum of 20 feet separation between trains, or 2. Provide a minimum 1/2-hour rated barrier such a's 1-i_nch min al wool separating one safety-related train from the other or trom a _. _ common exposure fire, and 3. Provide 1-1/2-hour rated barriers on the ERCW pump power cable metal enclosure and conduits at various locations in the auxiliary building, and l 7

4 of 9 l l 4. Provide area fire detection and automatic suppression systems for protection against exposure fire at interactions between redundant trains. We have implemented these requirements. Table 1.1 in the response to question 1 in TVA's October 23, 1979, submittal identifies an*.omatic i suppression and detection systems that have been provided for areas containing equipment and circuits necessary for safe shutdown. Table 1.2 of the same submittal identifies circuits which were relocated to provide 20-foot minimum spatial separation. Tables 1.3 and 1.4 identify circuits in conduits that were provided fire barrier protection. Tables 1.1, 1.2, 1.3, and 1.4 are included in Appendia A. In the annulus area of 9ontainment, closed head fixed water spray systems have been provided ie the immediate vicinity of cables of redundant trains that come within 5 feet vertically or 3 feet horizontally of each other. The spray systems are actuated by local fire detection systems. Flammastic 77 fire retardant coatings have been applied to exposed surfaces of all cables in trays in areas outside primary containment that contain circuits of redundant trains. The application of such coatings significantly reduces the ignitability and combustibility of cable insulation such that the requirements for no intervening combustibles between redundant divisions of equipment and circuits necessary to achieve and maintain safe shutdown is satisfied. Inside primary containment, an open head fixed water spray system and fire detection system have been provided for each reactor coolant pump. Oil collection systems are described under discussion of compliance with Section III.O. The features discussed above comply with Section III.G with the following exceptions. 1. One-inch mineral wool barriers are provided in lieu of 1-hour fire rated barriers for some safe shutdown circuits located within 20 feet of redundant circuits. 2. Literal compliance with the separation requirements for safe shutdown circuits inside containment has not been provided. Justification of Excentions 1. The safe shutdown circuits which are located within 20 feet of redundant circuite have been identified in Table 1.3 in the response to Question 1 in TVA's October 23, 1979, submittal. These circuits are routed through conduit wrapped in 1-inch --- Kaowool blanket with 4-inch wide and 1-inch wide Knowool strips provided at the butt joints. As shown in Figures III.G.1 and III.G.2 the conduit travels near the 20-foot ceiling level eastward from column line Q toward the secondary containment wall l' ~ at which point the conduits travel along the containment wall at +- l*:.

l t g g 5 of 9 elevations varying from 717' to 732'. The only significant fuel load in the area is the charcoal filters in the auxiliary gas treatment system. However, this unit has been provided with an internal fixed water spray system and the room area is covered by a preaction sprinkler system. In the 1978 Babcock and Wilcoi ' Tests for Fire Protection for Complete Fire Engulfment of Cable 2 rays and Conduits Containing Grouped Electrical Conducte-s,' a 1-inch Loswool blanket wrap provided 40 minutes pro

on for the cable tray when heated in a natural gas-fired furnace according to the heating rate j

designated in ASTM E-119. TVA believes that the Sequoyah installation will provide better protection than the 40-minute endurance rating of the Babcock and Wilcox test for the following reasons. s. Conduits are used in lieu of cable trays; b. The limited exposure to the conduit from the equipment located in the area could not equal the direct flame impingement on the cable trays during the test; and c. The light fuel load in the conduit-traveled area could not produce the 2.5 million Btu per hour of the test furnace. i It is our engineering judgment that the existing installation j provides adequate separation and meets the intent of Section i III.G. 2. TVA cont nds that adequate protection has been provided inside e primary containment and in the annulus area. Fire protection features have been provided for the necessary safe shutdown conduits and protection has been provided for exposure hazards to these conduits. Suppression and detection systems have been provided in the annulus at interactions between redundant trains. For added defense, all exposed cables in this area have been coated with Flammastic 77. Inside primary containment, all circuits needed for safe shutdown during a fire are routed in conduit. An oil collection system and a suppression and detection system have been provided for the reactor coolant pumps to protect against the lube oil hazard potential. Also, cable trays in this area have, been enclosed. l TVA believes the scope and redundancy of the fire protection features provide adequate protection and meets the intent of y Section III.G. ~ 4e o Ob7 W M 4 w u g 4 ~~ 0 p N*%' .e ~ --4 I &[ ,<"",o = -.,., - ~... - -, _ _., -..,, ~., .m., ..__.m,. _.. - ~, _ _.......,... .. +., -

d e 6 of 9 B. Section III.J Reanirements Emergency lighting units with at least an 8-hour battery power supply shall be provided in areas needed for operation of safe shutdown equipoent and in access and egress routes thereto. TVA Response Fixed self-contained lighting consisting of halogen cycle sealed beam units with 8-hour battery packs are provided at Sequoyah Nuclear Plant in areas that must be manned for safe cold shutdown and for access and egress to and from all fire areas in safety-related structures. This complies with the requirements of Section C.4.e(1) of BTP 9.5-1 and exceeds the requirements for emergency liphting specified in Section III.J of Appendiz R to l' < TR Part 50. Sequoyah Nuclear Plant Special Test No. 7 ' Simulated Loss of All Onuite and Offsite AC Power' was conducted for the purpose of verifying that critical plant operation can be performed using emergency lighting. The results of the test were satisfactory and a report has been submitted to the staff by letter frem L. M. Mills to E. Adensam dated June 5,1981. a ' ~ = ..a-a+.a.,J& ,,n .,,w w 7-% m 6 y ---m.- .g y_ y._.-,,,,,,v. .,ry yy.- 9._m,,. -.., ,.w..y,_y~.,,, .-y-- -_ -,,,+ -9

i d v 7 of 9 C. Section III.L Reauirements 1. Alternative or dedicated shutdown capability provided for a specific fire area shall be able to (a) achieve and maintain subcritical reactivity conditions in the reactor; (b) maintain reactor coolant inventory; (c) achieve and maintain hot standby conditions for a PWR (hot shutdown for a BWR); (d) achieve cold shutdown conditions within 72 hours; and (e) maintain cold shutdown conditions thereafter. During the postfire shutdown, the reactor coolant systen process variables shall be maintained within those predicted for a loss of normal a.c. power, and the fission product boundary integrity shall not be affected; i.e., there shall be no fuel clad damage, rupture of any primary coolant boundary, or rupture of the containment boundary. 2. The performance goals for the shutdown functions shall be: a. The reactivity control function shall be capable of achieving and maintaining cold shutdown reactivity conditions. b. The reactor coolant makeup function shall be capable of maintaining the reactor coolant level above the top of the core for the BWRs and be within the level indication in the pressurizer for PWRs. c. The reactor heat removal function shall be capable of achieving and maintaining decay heat removal. d. The process monitoring function shall be capable of providing direct readings of the process variables necessary to perform and control the above functions. The supporting functions shall be capable of providing the process cooling, lubrication, etc., necessary to permit the operation of the equipment used for safe shutdown functions. 3. The shutdown capability for specific fire areas may be unique for i l each such area, or it may be one unique combination of systems l for all such areas. In either case, the alternative shutdown l capability shall be independent of the specific fire area (s) and shall accommodate postfire conditions where offsite power is available and where offsite power is not available for 72 hours. Procedures shall be in effect to implement this capability. 4. If the capability to achieve and maintain cold shutdown will no t be available because of fire damage, the equipment and systems comprising the means to achieve and maintain-t:he hot standby o. hot shutdown condition shall be capable of maintaining such conditions until cold shutdown can be achieved. If such ~ ~ ' ' ~ equipment and systems will not be capable of being powered b3 - both onsite and offsite electric power systems because of fire damage, an independent onsite power system shall be provided. The l,_ number of operating shif t personnel, exclusive of fire brigade j members, required to operate such equipment and systems shall *oe l-onsite at all times. l

d 9 8 of 9 l 5. Equipment and systems comprising the means to achieve and maintain cold shutdown conditions shall not be damaged by fire; or the fire damage to such equipment and systems shall be limited so that the systems can be made operable and cold shutdown can be achieved within 72 hours. Materials for such repairs shall be readily available onsite _ and procedures shall be in effect to implement such repairs. If such equipment and systems used prior to 72 hours af ter the fire will not be capable of being powered i by both onsite and offsite electric power systems because of fire damage, an independent onsite power system shall be provided. Equipment and systems used af ter 72 hours may be powered by offsite power only. 6. Shutdown systems installed to ensure postfire shutdown capability need not be designed to meet seismic Category I criterix, single failure criteria, or other design basis accident criteria, except where required for other reasons, e.g., because of interface with or impact on existing safety systems, or because of adverse valve actions due to fire damage. 7. The safe shutdown equipment and systems for each fire area shall be known to be isolated from associated non-safety circuits in ] the fire area so that hot shorts, open circuits, or shorts to ground in the associated circuits will not prevent operation of the safe shutdown equipment. The separation and barriers between trays and conduits containing associated circuits of one safe shutdown division and trays and conduits containing associated circuits or safe shutdown cables from the redundant division, or the isolation of these associated circuits from the safe shutdown equipment, shall be such that a postulated fire involving associated circuits will act prevent safe shutdown. TVA Resnonse TVA interprets Appendix R to require that alternative or dedicated shutdown capability be provided only if certain requirements of Section III.G are not satisfied. As stated previously, the current Sequoyah design meets the intent of Section III.O.2. In addition, t there are no areas of the plant that contain redundant equipment or systems required for hot shutdown which could sustain damage to both trains from fire suppression activities or from the rupture or inadvertent operation of fire suppression systems. Therefore, it is our ponition that Section III.L is not applicable to Sequoyah Nuclear Plant. 9MM -=A-4

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e a 9 of 9 D. Sectien III.0 Scanirements The reactor coolant pump shall be eggipped with an oil collection system if the containment is not it.crted during normal operation. The oil collection system shalf be so designed, engineered, and installed that f ailure will not lead to fire during normal or design basia accident conditions an*. that there is reasonable assurance that the system will withstand the Safe Shutdown Earthquake. Such collection systems shall be capsble of collecting lube oil from all potential pressurized and unpressurized leakage sites in the reactor coolant pump lobe oil systems. Leakage shall be collected and drained to a vented closed container that can hold the entire lube oil system inventory. A flame arrester is required in the vent if the flash point characteristics cf the oil present the hazard of fire flashback. Lenkaee points to be protected shall include lif t pump and piping, overflow ines, lube oil cooler, oil fill and drains lines and plugs, flanged connections on oil lines, and lube oil reservoirs where such features exist on the reactor coolant pumps. The drain line shall be large enough to accommodate the largest potential oil leak. 7YA Resnonse TVA has provided spray shields for the reactor coolant pump, oil lift pumps and associated external lubricating oil piping such that oil from the rupture of identified pressurized components line will be contained. An oil collection basin was alsc provided at the access platform elevation of each pump to collect and drain away any combustible liquid and/or suppression system discharge. The collection system is illustrated in Figures III.D.1 and III.O.2. The oil containment and collection system for the reactor coolant pumps is seismically supported and qualified to provide reasonable assura2ce that it will not f ail during the safe shutdown earthquake in a man:g r which could damage nuclear safety-related equipment to a degre. that they cannot perform their intended function. Any discharge is drained from the collection basin to the closed and vented containment floor and equipment drain sump located inside primary containment. A description of the containment floor and equipment drain sump is previded in the Sequoyah Nuclear Plant FSAR, section 9.3.3. The sump vents do not require the installation of flame arresters because the high flashpoint charecteristics (390 degrees F.) of the reactor coolant pump lube oil prec1cde the hazard of fire flashback. During TVA's review for compliance with Appendix R requirements, a pressurized oil-containing component was identified that does not have a spray shield. This component is the shell side of the upper bearing cooler which is pressurized to approximately 10 psig during reactor ~ ~~ ' coolant pump. operation. TVA commits to enclosing the cooler in a spray shield following the same criteria r+tilzed for the other oil collection system components. The shield wzil be installed by the end of the first refueling outage for each unit. With the addition of the upper bearing cooler spray shield, the reactor coolant pump oil collection system will comply fully with the requirements of Sectior. III.O.

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APPENDIX A a SEQUOYAH NUCLEt.R PLANT SAFE SHUIDOWN ANALYSIS DOCUMENTATION SUBMITTED TO THE NRC BY LETTER FROM L. M. MILLS TO L. S. RUBENSTEIN DATED OCTOBER 23, 1979 f s-... .t., / ~ l 1 } I !

W.,- { '*v 7 " p..,. g w a q...q.; g g g g. p g.p p q '.*, q q y,v', g y.*' y q m L: y 9.;.4.; - .s ... -.5

O-

,.., w.w'w, 'u :. :.2 p.. g., n a u? c ..w J O 4 x ' a ; m +.. w:. r.: :.u.et.....>... u e +w .u : fhhh b b5. b 5)- ~ Mi

11/9/78 h-4g 1 R1--12/15/78

u A

R2--l/16/79 H 5:' k AUXILIARY SYSTEMS BRANCH R3--3/5/79 h FIRE PROTECTION REVIEW R4--10/19/79 l 3@!. ; e i SEQUOYAH HUCLEAR PLANT - UNITS 1 AND 2

r...

j DOCKET NUMBERS 50-327/328 { w - ':f C., r l. Your submittal provides only part of the infomstion requested in c ? to our letter dated September 30, 1976. A fire hazards 5;n - %.. t analysis should be conducted for each plant fire area, and the p., j <J-effects of postulated fire involving pemanent and/or transient Y. e combustibles on systems, circuits, or equipenent required for 9 7y.I and primary and secondary fire suppression systems for each area safe plant cold shutdown should be evaluated. The fire detection ]j# .( Mi should also be indicated. In the fire hazards analysis you t hI -}* should identify all the redundant mechanical and electrical systems f'.' necessary for safe cold shutdown which are separated only by c O distance (no fire barriers). The fire hazards analysis should. W demonstrate that, assuming failure of the primary suppression system, p , N- ) a fire in installed or transient combustibles will not damage s3 .j redundant trains or divisions of systems reouired for safe plant Ri cold shutdown. Where this cannot be demonstrated, an alternate R5 .,-g means of assuring safe plant shutdown (cold shutdown) should be - d:: .3 4 provided. .k FILMED FROM BEST ( TVA Response MWLABLE COPY ^ b

LP Sequoyah Nuclear Plant's fire protection system design was based on the d

i k. _f results of a fire hazards analysis covering those areas where an unmitigated

e

.t fire could affect a unit's ability to reach and maintain a safe cold shutdown. y The analysis involved a detailed review of the plant design and an ]C1

jh: h}

ip evaluation 9f the effects of postulated fires. ? lty L.. ? i-The results of the analysis are provided in part in the Sequoyah Nuclear U4 ' '" h$' Plant Fire Protection Progrm Reevaluation forwarded to the NRC by -- E;.,j letter from J. E. Gilleland to R. S. Boyd dated January 24,1977. The p' T following discussion supplments the original doccuentation. yf, w,+ h-Based upon the fuel loading and cocpartmentation of fire cells, fire N. suppression and detection systems have been provided in the various $;g l?!" plant areas as identified in Table 1-1. When fixed stppression systems L,. ;l are ;'rovided in an area, they are considered the primary systems. Backup la protection is provided by standpipe systems or yard hydrants. When manual systems are used exclusively in an area, they are considered the primary c sc. - syste=s and are backed up by manual systems in ad# cent areas. I Figure 1.1 is a safe shutdown logic diagram for a fire at Sequoyah J] A* j' '. Nuclear Plant. Thf s figure and its cccinent sheet identify those plant l features necessary to achieve and maintain a safe plant shutdcwn in N. h. the event of a fire. TVA has conducted an analysis of the plant based h'I J$ ' upon this diagram and its corment sheet assuming a postulated exposure fire

i with a zone of influence requiring a minimum 20-foot spatial separation

,.i of redundant equipment; circuits, or components in all plant areas outsida ,s

i-of containment. This analysis has identified where adCtiol,al protection

r. -

i k.- ^

l. o, eg

$* t i t p{ ~ 4 S 825340 ] ^ ,$..[IS ? 5. M [3N? $ M B W,W.S & % ;lQ.& M'?.W l.i%.' M :.2%llTi;

M s vm..mmm.mm.,e..;y. a.g..,ge:.cm?g9,i * : : :M.W ;:,2: mwrvy.g.,.;y -ce ..a... ,4 f; 3 m

U.

W... i.: C ':.~

s..a.~.,. *...... w... : 2 3 i,%

.. s.:d : U 4 y. . _, f; p..v ' '. -.. y L- . 9Q..g /. p.: - y :.f) r i bswAwW.W.(MMEMMMhesMfagisT@M$:u g: O m. [.y < and/oriseparation is required to assure that the hot shutdown condition S. 7:'l. 9 is reached during a fire using only exhting hardware and no extraordinary ( operating action (i.e.. the operator's response will not be required in . /o-less than 15 c:inutes and will consist of planc mnipulations typical of ~, f a those rmuired for nomal operation). The analysis does not consider inside 'q$: primary containment because transient fire loads in this area, when y., the plant is at power, are not credible, and fixed hazards which pose. 7 V an exposure threat to equipment cceponents or. circuits rcquired.for safe ,5::t, water suppression systems, automatic detection capability, and an oil W. shutdown (i.e. reactor coolant pumps) are provided with fixed automatic y, u J, collection pan with drains to prevent spilled oil from contacting hot n-M - y/, piping. Note that tems such as inadecuate set'aration and unacceotable c....] interaction when used in this discussion refer to tne inability to J.^ j d , {>,'::- achieve 20-foot spatial separation within a fire cell. These tems do not icply violation of separation as specified in the plant design y;, of cri teria. 1't Throughout this discussion an asterisk (*) will be used to identify Je E^l:*. the title of a function block on the shutdown logic diagram (Figure 1.1). T This diagram and its keyed cements are gemane and are an integral part . d of the following discussion. $(.g v. y }.. Hot Shutdown e-r n 4 - N Each of the six conditions necessary to achieve hot shutdown are 2." 'I discussed se:arately. Refer to the six conditions which provide input .;^'j

~ J into the AND block that leads to the hot shutdown condition on the b.r ]

/ shutdown W ie diagram. $j

- . s '

w-Secondary Side pressure Control - The Secondary Safety Valves

and the

'i 7,* j - Secondary Restef valves

can satisfy this plant condition. The

? '/ spring-loaded secondary safety valves used for short-tem control are W.. 1/: . ]M{.<

1 considered imune to fire damage. The secondary relief valves used for long-tem control are adequately separated so that access to the FW TP'.

required two valves for manual actuation can be assured during a fire. T1 The redundant circuits for the steam generator pressure instrumentathn -: -) were found to be inadequately separated. TVA will provide the required .$e instrunentation integrity in accoroance with Table 1.3. Since this [..'

q satisfies the required conditier.. TVA has not evaluated control via N..

-O the Main Steam System = nor remote electrical control of the pcver-operated n' .? } secondary relief valves. Steam Generator Inventory Control - This plant condition requires an ~ -'} auxiliary feeawater p::::p capaDie of feeding any two steam generators. IcVel control for these steam generators, and suction to the pt::rp. This anlysis

u.. j j

ha.s identified areas where the postulated exposure fire described above i'- v 0 -o .-Q would affect both the A and 8 t:ain sections of the Motor-Driven Auxiliary. 'v' i ') Feedwater Pump

function. Other areas were identified s.here a separata postulated exposure fire would affect both trains of the Turbine-Driven Auxiliary Feedwater Pump
function. However, no single postulated t

fire exists which would affect both of these functions.

s. -

~ 4,j 9! j,f _ p. 4{ w.U O.- w (}5 "? 36742 , $:,CW a.m R:P.q..;yszgy.537,-5&cMW>W*'gyj;.:yg.;,7c.vv.mpydg~ f:

7. N W ,,z g.,,f 7 '; W,t W N 9 h T.$ f/. %"; xt,Q$.g$.q,,.%%.q,3.3:QMM%- x,*,y[..$,7fQf;@f ? :.. ,y ..w . (:y:['.s. &;. 2 ;g yp 1L.., - w w a. ~ _, f ':.V

1': '.'"ld.V';'f f f.,y.bf.QMf_ly NMQ:.Abtf%-j.-f%~rQ

&wf ~ t 5 .5% Q. % h? & h h & & & ?E $ b $ ! $ $ 5 N ? N Y $ I$fD Y b Y O W. l 43 F: Gr?o) ' 4. s 9: :d Interactions also exist for the automatic control of the Steam Generator ..[ i Level Contro1* function. These interactions have been deemed acceptable 3' ' " d because the control valves themselves are adequately separated and r.anual

.M-$

control is achievable. Unacceptable interactions were found to exist for q' '@*.y h the steam generator level signal which is necessary for both manual or

4

-: y automatic level control. TVA will provide the necessary protection of VY N:; '.D this function in accordance with Table 1.3. Suction from the ERCW* N (essential raw cooling water system) was not evaluated because suction .-b]. }e-) .c: from the Condensate Storage Tank

is assured due to the tank being tamune to fire damage.

..b Reactor Coolant System Inventory Control - This condition requires that

'Ei RI.S letdown ce controlled, that HCS makeup be provided, and that W ;'. reactor coolant pump seal integrity be assured. These three conditions g are discussed separately. RCS Letdown Control - This condition can be satisfied by closure 1 '7g* Q.f of any one of a number of Letdewn Isolation Valves

in each of l

two series strings of valves. Since all of the valves.innived /.r.. i, [ are air-operated valves which would fail'in the desired pcattien i 'A should their control cable be damaged, these, control circuits L. o were not evaluated for separation. m.. W. ~ RCS Makeup - This condition requires the availability of a charging f, pianp. pmp suction, and a flow path into the RCS. Of these, water, j 3 r.:. via Volume Control Tank Suctien* and Refueling Water Storage Tank i ?i j Suction *, is assured since the tanks themselves perform only a

b a

passive function which would not be.feopardizco by a fire, and { i 1 ' j..g manual handwheel operation of the RWST suction valves is acceptable. [ M: i I." { The analysis noted that the single postulated exposure fire 3 described above could cause the loss of both trains of the CVCS ' 9:.1 h ., ' A '.; Centrifugal Charging Pump

and the Positive Displacecent Charging I

Wu C". ! Pe 7 TVA will correct this unacceptable condition by rerouting 1 77,.9 tne' wiring for the positive displacement charging pump and the j hr - < positive displacement pump roco cooler in accordance with-Table 1.2. This pump was chosen for rerouting because it is b';P(:. the ptscp used in normal operation; hence, its flow path is bM already properly aligned. The ECCS charging Flow Path

associated

( b,M:' V o with the centrifugal pumps contains interactions which can affect j both A and B train sections. These interactions are acceptable j @C because they do not affect the positive displacement charging } l W* ptsnp; hence, either the positive displacement pump via the nor-mal charginf are available during any postulated fire. path or the centrifugal charging pump (s) via the b@ ECCS path (s l FE* Control of RCS makeup via either the ECCS (centrifugal) pumps or I. li..}' the normally operating (positive displacement) pumpt requires a l D... I pressurizer level signal. Unacceptable interactior.s were found y; to exist between conduits associated with the required : instrumentation wiring. TVA will correct this condition in ' l v.g-- . accordance with Table 1.3. The component. cooling water and S p;;y. - .M. - l 1@&^.f i l 2 lJ e 4.h ? I[ * &.L.['n 3=gj]zg g;;.g.Q.jR77m%.y-}7,7-Q,Wmm.$:E:.N95. Y.;.-WT ! s.' " 36741/577295 --n

.o e ' [ e*-eme A ! _ M met a *> *. N h* .,w em-e * * *. - t +r. mme;y:-mg.m:a .w:e : y;,x g.p. f ~ kf M' $h.lY ~YkY,$ hA$$i.' $h h Y'h .v .y: ;,

i,.

essential raw cooling water systems are identified in the keyed 4. - -. coceents as being required for RCS makeup. Unacceptable interactions do cxist in both of these systems. The CCS mechanical system inter-actions aid how they are resolved are discussed in the response Cf' 4 to duestion 13. The CCS and ERCW electrical system interactions @% 9 f) will be protected in accordance with Table 1.4. W--m 1 RCP Seal Integrity - Seal integrity for the reactor coolant pumps

'c can be assured if either the positive displacement charging pc.9 or the centrifugal charging pump and the associated Charging Flow c",77.

Control Valve, FCV62-93* are available to provide injection water w; q to the seals. The modifications proposed to upgrade the system in the preceding paragraph will assure RCP seal integrity. RCP W Thermal Barrier Cooling

also would assure this required condition.

-J-This path does contain interactions which would affect baith its W:. A and B train sections. These interactions are deemed acceptable P% because RCP seal injection is assured. s,'T, - V Secondary Side Isolation - The Main Steam Isolation Yalves* are stored- ~ energy, fail-closed valves which require both A and 8 control signals N to remain in the open position. A postulated fire which would affect eV '.g the control cables would cause the valves to shut, assuring this function. L Hence, these control cables and those for the parallel pat'i, Steam Losd g g.n ! solation *, were not evaluated. %h

w. v Analysis of the Main Feedwater Isolation Valves

indicated that at least

'l one of the two valves in each feedwater line could be shut for the postulated fire. Hence, the Main feedwater Pump

function, a parallel q.L.h path to feedwater isolation, was not evaluated.

- (f.;.L... g -.--. - Each steam generator blowdown line contains an A and B train blowdown ,,'1. j Isolation Valve

in series. Both valves would fail in the desired,

.e closed position if there was fire damage to the control cables; hence. V ( this feature is considered to be assured and was not evaluated. . p@ \\ j? RCS Pressure control - Trained power cables outside primary containcent

ATA, d

for the Pressurizer Heaters

were found to interact within 20 feet

' ~ ~ ' " * ' in two locations. Within the reactor butiding annulus, the two trains y,ME 7 are separated by 19 feet for most of their routing, but approach 13 --i lA feet at the primary contaire,ent penetration. This interaction has been 4 l[ deemed acceptable because of the low probability for transient fire ~ id ~# 1 i, loads within the annulus area and because all exposed surfaces of cable WM' ' ' l witi.in this area have beca provided with a flame-retardant rastic coating. MF i \\- .y l The second interaction involves opposite trains approaching to within JN l three feet at an orthoganal crossing on elevation. 759 of the auxiliary ]5.#.D : l butiding near the pressurizer transformers and switchgear..The divisional medium-voltage (6900 volts) power cables for the supply to the 6.9-kV/MOV. NUPj < li stepdown pressurizer heater transformer are routed in cable trays located 7 "~

above power cables of the redundant division. TVA will reroute the unit 1 l

and unit 2 pressurizer heater 6900Y power cables to achieve a mint:::um 20 feet sepiration from the redundant division in accordance with IJ Table 1.2. Automatic sprinkler protection will be provided in the area' .?', ' _ lp of the power cables in. trays. .CET c :-9'.. iq( for control interact within the auxiliary building. TVA will correct ' ~; n Instru:nentation conduits *hich contain the pressure signals necessary .30 l,. this condition in accordance with Table 1.3. rP 4 k' l7 .a u. 4 b'l .r 4 36740/855462 's. S' l x.W"'V"""T = h. 3.-Whm g,1?QW.Y.*~?X;Wl b W.r?f;M, - w:d @ n?WW" ^ l +nW? W-3: M. _ -nX-n.owz. mnM.Q$3nhv. +-w.mm c r %,.i.* _t t

1.. W.P W/d.',f'Mt [. MMjM {.$ .dr 2,y [ t. w.. %..a: *.; ' - ? ~ ' ' u n. ,,=M...., i { [{. h.&5 '[ .f.{5),*.&o,.s Y MN :h e * ". V .'U ~U d ,L & ' p,a*

L..r f

~ Eht ~A$ 1lY $h~.0 i ? f e: '.;-,- n G %..A M-Initial Reactivity Control - The trained Reactor Trip System

which

[ 'd provides this condition is a fail-safe system which will respond to n.. [y "j the postulated fire by causing the control rods to be inserted. I Thus, no evaluation was considered necessary. 9

W M g) g Cold Shutdown Y

!h The dashed section of the shutdown logic diagram identifies two additional F" 1 plant conditions, Long Tem Heat Removal and Long Tem Reactivity Control, J Y..% which must be established to place the plant in the cold shutdown condition. b, C? This section of the shutdown logic diagram has been analyzed to assure u Q:c.3 that all required plant conditions can be established within 72 hours Ml T-of a postulated fire having a zone of influence requiring a minimum 20-m lg foot separation. It should be noted that unlike the hot shutdown analysis, 3 ' A ::,, the cold shutdown an'alysis does take credit for damige control measures el which cannot te. considered typica*. of nomal plant operation. These extra-g. ,:, j ordinary actions are described below. g 1 + >:c. U,::@ tong Tem Fest Removal - The condition requires the Residual Heat Removal W $ fr (RhR) system to be operable. It is realized when an RHR Shutdown Cooling t'., 1 Qbc. @y Flow Path

is established and the RHR Pumps
are operational. Panual hand-

? : .p wheel operation of all required valves is acceptable with no further evalua-1} tion. All other features were found to be adequately separated except g, ,,~. :1 the cables which supply the RER pump room coolers. TVA's resolution of j I'., ::( this interaction is described in table 1.5. (Note: Unacceptable ir.ter-f{r..m actions do exist within the cceponent cooling water--CCS--system. .': k These interactions and : heir resolutions have been discussed in the hot V' N s:C1 shutdown analysis above and also in the response to question 13.) M.: long Tem Reactivity Control - To establish an acceptable shutdcwn margin 9 under cold conditions, the contents of the boron injection tank (BIT) cust ? be charged into the reactor coolant system. The Flow Path Through the l l BIT

can be established by manual handwheel coeration of the required valves and was r.ot evaluated further.

Analysis of RCS Hakeup Capability

has been p.j~,

made above as part of RCS INVENTORY C0'iTROL enalysis. Please refer to this W1 .. :-}, discussion for interactions and their resosucion. l* Conclusion A t c'. C As a result of the preceding analysis and the identification of areas I.? ' where 20-foot spatial separation of redundant circuits required for M N? safe shutdown within a fire cell has not been achieved, protective q'. . I; measures described in Tables 1.2,1.3, ~and 1.4 shall oe implemnted. E 6 .[ TVA has provided by separate submittal, marked drawings shcwing the new cable routing for relocated cables anf conduits listed in Table 1.2 d and the relative locations of the redundant counterpart cables and/or x.. conduits. These modific3tions will. assure the ability to achieve the hot L. h. h. shutdown condition as discussed previously in this response. The cold i shutdown condition can be achieved within 72 hours through the implementation 3:,. of tesporary dnage control measures and extraordinary operator actions - i p%:. described in table 1.5. I i-p.; i $trict administrative p'rocedures have been established to control m t transient coe.bustibics and are included in the sequoyah Physical Instruction / PHYSI-13. The procedure requires identification of the g. routes for transient combustibles and the procedure takes no credit L? s 'R i n. 1 3'. iLA l 0 u w* i [. 19?843 /922336 ~ } h..

77ign.Mipqp-ygg;yq92.ykyyyyp; '. *

$5 o' 'c C' u- .v. o u o o o o o c.. o o o O d h$$$ i', 1' ..jd E.- seg g D r; T5 - {$ for,the fixed suppression system in regard to its extinguishing capability v: for transient fire loads. The procedure requires provisions for p: < '- p* ; additional fire protection that is capable of suppressing the transient ) j, fire load, -o .o ! h:: With the defense-in-depth as described above, protection to redundant Sf'p-q t' .C . N ;; divisions of systems f rom installed or transient combustibles ?' W.- has been provided to ensure capability of safe shutdcwn of the plant. ','k { ; N'- -l E :, cn U . z.. A . t. -

1*j:

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*.' ~

sp .w. Q* U s.

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ge [., V' w. ? .y , Q.

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[: o-J 5/

, : ?. e l l ! Y. .r W g g* y o . P.

</...

Y-y; P2 i .[ 4 ' [f c. ! o' O 'W f:.i1 $ k w e r.: w : a.s739wa:omms#:Bd:isssnRl#.4 a ?

.5 ~. % On LH AH(,a KEY 2 voluut. REY 4 KEY S .CvCS KEYi rLOW u.Nii NWSI dTHOL CONINOL CE NTRiFUCAL SUCTON CHA%tM PLW SALVE TANK A { s FCV 62 93 SUCTION A I 9 AND pm8 TIVE KEY 3 AfD tv JtActdNT AND 10 CHARGP4 ggp 9, pggg ,gy 9 KEY 6 ECCS i BARRtR ANDIO CHARGE 3 COOLING

f FATM l_

L A e A e e ( LETDCwN FEYS F . J. RCP $EAL AND ANO ISOL ATION Ato 8 j VALVE A 8 <L:. OR ano AND PCP IICS \\ [RCS OR $EAL LEToowy } g uw NIE33I CONTROLj \\ AN3' T Re5 MAP 4 STE AM KEY 2O STEAutCAO KEY 20 WTOR Of%ENKEYl' 53tivtL FEYt2 INVE INSOLATION INSCLAT30N CCNTROL ANDl3 CONTIO. AUX FEED..e vaOTS WATER P a ie A a A l e g OR r ) l AND ~ TUAHrE Of 53 zEYg3 MAIN KEY 22 MA:N KEY 23 CMVf N AUX '4 LIE

40 16 tHIWEa6 _ A*C GNimel FEEDF aER FE N TER 6

gSctA;og g gp A 8 115 A j B vatvES q 140 COPECNSATE SUCT$Cf4 WEYt9 OR l $UCTION FM wgy a r ty FRC4 W-tilIWDC*N FEY 24 STORaw7. M* NSCLATION TANK A { 9 gpg VALVES T 1, * ^ r AND SCE '*T- '81#T*" so DNENTORT PRESSUR!ZEF KEY 28 a e HEATERS g I SECONDARY ktY2S SEC34CARY KEY 26 A le SAFETY REUEF NE TR %LVES VALVES SystEv AND RCS g 9 l "%**D l PRES $URE l CONTROL l 3 a INITIAL y* WAIN KEY OR fEACTaviTY sTEAW ZI CONTROL SYSTEW MCOP g SiOE PRE *,StAE PLANT Crp4Tp lN HOT SIUTDOwad (TPDT ^ NOTES 2 74CFTRALCNCE APARTCA AR SAFETY TRAMMASBftNiW)KETwSTEN

- * * * * * * * * "I *.". f.".! ! * !I 1.

MUST BE USED THROUGHOUT THE LOGIC EXCEP TIONSMdST BE E vM4 ATE .........m xEy FLO* PATHFEY

C3 MEy RHR MY RHR CN ACASC BASES.

SNUTDOWN 3a THROUCH 32 MA8EUP 33 CONDITION THaS'0NES AaE uSED revi PATHS tr Aoissio 30 M PS FLDw P TH ' a~~T'Ti-- YIa "$"e 5 ' EECT:CN CF T*(LOGIC DI AGNAw HASBEEN ANA 8-A i...., ..) i..., r...' ASSURE THAT ALL RLQtmeCD CONQTIONi CAN f4 Nf All2EL DUHWG A F PE. ,A 4 TM CHIT [RIA FOH ACLtP fARKIT Y IS AS 60LLLw9 QVEN A FIRE WHICH f FFECTS ANY FUCTiON 9e THE DIA*Ji AW, TPC I Apg Apg REQUIRED CON (AllON Mtt3T fiE CAf4DLE (f (TIN *,HE ACHEDEITHER 8 VIA A PARALLEL HLDUNDENT t.M CtVERSE PATH WHsCHs$ HeTCICA.Lf "T" SEPARATEDOR FRfiltCiF D FRGu 1et F**C OR tlY VINTUE OF f>r? f ACT THAT THE FLNCTsulMAf RLC0N;aQEhtO'UW'MEIO fINL DAWAGL gay ,g g yy (EA TEREFULLING nAIER STCHAGE TAh4) eE*ML TROL. Of *>t t sNrVRE U*EDT0ttPe.T PATH *.t F ADpr ff v0NDMT ........,y........ SeuTOCwN TO f tE wto tacullamN umDITION TW ',t WH*i(AN tsE ASSU5tED unOt R $0*.% f p*E COPAA TIUP6 811** N HY W# QiKIE PHT*, SCAL A80 RMWtAf f0NOH tsf ILMPOF,(AN f 8(ASUNESli flNt 0 94CK.AJALT f MCLEJssLS etANT FIGURE I.: 4 stoCxswuiCHCmTAiN A e A A,co sunotoCxuuuTE TRA.4iztorEATU Es y '*"'"#'S****'""'"*' En7' SEQUOYAHNUCLEARPLANT xCvEoc uuENTS AREloCATEc oN $tPARAtE COuutNT SHEET. r s r' SHUTDOM M-RRE m m.

kl 5 O w v.. J u a v w w (.0 V .o .o u o u O u t' .:t, Sb: -- $- .,k s i.y 5 ';.y.e. v s cQ q KEYED C0mENTS .t *. er 1 f:::' S l.- Requires auxiliary lube oil pump AND, power to pump room cooler ApD ERCW to pump oil cooler A.ND ERCW to pump room cooler AND CCS water

~/ f.

to ERCW heat exch.ingers. g td. r, . {./ 2. Requires appropriate section of pressurizer level control systen .. ~. * - AND EITHER 0 auxiliary air compressor B station air compressor. 6 f,. *. 3. Requires ERCW to pump room cooler AED power to pump room cooler AND i c(3 CCS water to pump oil cooler AND CCS water to pump speed control u

/- *#

AND ERCW to CCS exchanger ANDTl'THER automatic speed control from e7>.- b;-! ', ~ $.Q approrpriate section of pressurizer level control system M reanual g-speed control using pressurizer l' -1 instrumentation. g:. 4. Short-term make up source, normally aligned, no action requirtJ. o g, S. Long-term make up source requires opening of FCV62-135 g FCV62-136, hand whec1 operation acceptable. (- p.hs 'rz .*$ l '- 6. Flow pt,th requires opening an inlet valve.(EITHER FC\\'3-25 OR sj e X FCV63-26) A';D an outlet valve (EITHER FCV63-39 OR FCV63-4C) Tor the

d boron injection tank.

~~ ,y b d T. l:. .I;,,. 7. Termination of normal letdown requires closure of FCV62-77 OR ?: [l FCV62-74.- FCV62-70 OR FCV62-69 OR all three valves FCV62-72, FCV62-73' and $g.- s e ;,s .,~ 'd 8. Termination of excess letdown requires closure of FCV62-54 OR- u~ M, FCV62-55 OR FCV62-56. -},.>,., '*<./k 9. Requires CCS water to thermal barrier booster pump AND ERCW to CCS , 'I. . $:{.}.[( heat exchangers. .,( t Y,.~.. E ' U:

10. IF'B train is selected, an additional requirement is opening b' !s'$.

capability for FCV70-9, FCV70-10, FCV70-195 and FCV70-196. .y .r.

11. Requires automatic control AND bvdraulic motor for tv;k pressure L::

s,::f::e regulating valve'(A train PCV3-122, B train PCV3-132). -y. D .6 g;, ::-;. - c. O

12. Requires automatic control signal to level control valves (A train Q*.

' }.. ff LCV3-156 AND LCV3-164, B train t.CV3-148 AND LCV3-171) OR ster- ): :- generator level instrumentation for manuaT control (A train uam $f $g. '.)yj consists of on/off operation of the pump. -~~~ Manual control y generator 1 AND 2, B train steam generator 3 AND 4). y :r o

13. IF automatic control is selected, an additional requirement is the 0

'(: ~; ?. appropriate train of auxiliary air compressor 0,.R service air compressor.

{i:

- it

14. Not a true A and B train system--the turbine-driven auxiliary

11-feedwater subsystem may be considered to be a separate single

.v*' .v' train, which can be supplied with control and power from either of O. the traditional A and 0 trains. O. j; t.' e

..S ss 9

g . ; y;- g s..%

c h.le.,

k-INSFS$& 3 ' 92 $Gys@'.<G'.U::5}.U'N@55sNE.5NSsNssyb:.99SSSSNS';4-:M&S -

{ Ys ~h*_- 2 9. J. O ..u o 9 U u o o u u. u u s u o u 1. A. = 4;..< p; v -y h.c (g j q

15. Requires turbine trip and throttle valves (FCVl-51), AND governor P

f: S - valve (FCV1-52). s s s h.

(

16.- Requires automatic signal to any two level control valves (LCV3-172, 4 LCV3-U3, LCV3-174, LCV3-175) OR steam generator level instrumentation "Dg for manual control of any two steam generators. !!:nual operation u ccisists of handwheel operation of the level control valves. f

17. No'emally aligned, no action required.

A.* f. l .p. '

18. JF, automatic speed control is selected, an additional requirement is B C

train auxiliary air compressor O_R, service air compressor, u V- $0%;

19. Requires suction valves to open AND ERCW system availability.

e U I*,

20. Requires closure of all main stearr. isolation AND isolation bypass

' D valves (FCVl-4, FCVl-ll, FCV1-22, FCVl-29, FCVT 147, FCVl-148, FCV1-149 FCVI-150).

w' >]r a j

21. Requires closure of main steam dump valves AND main turbine trip p :Q. -

and throttle valve AND main feedwater pump turbine trip and throttle valvas. ,c $, ; [ %'s

22. Requires closure of a feedwater isolation valve (FCV3-33, FCV3-47, v

: ?t FCV3-87, FCV3-10G) OR closure of a feedwater control and bypass a

-/ valve pair in each feed line (FCV3-35 AND FCV3-35A, FCV3-48, AND ' [; y)* - FCV3-48A, FCV3-90 AND FCV3-90A, FCV3-IDTAND FCV3-103A). . ff-p%, g.\\ ' f.: :d'

23. Requires trip of main feedwater pump turbine.

"1 o u ,' I;; 7.,;.

24. Requires closure of one valve in each blowdown line (FCVl-7 OR

' I'.:- 6., - FCV1-181) AND-(FCVI-14 OR FCVl-182) AND (FCVI-25 OR FCVI-183 TAND . j K- 'e (FCV1-32 Oli_ TCVI-184). ~-- ~

25. Scif actuating, short-term control.

I-y- l'[.' P

26. Long-term control, requires operability of any two relief valves

((; 7 ' ;;." #s (PCVl-5. PCVl-12 PCV1-23, PCVl-30 manual control acceptable) AND s

f{ L pressure instrumentatier for same two ste6m generators.

,s-A

t..h

27. Requires opening of two main steam isolation OR isolation bypass K

O valves AND control of main steam dump valves liiD condenser d 3 p;c. circulating water, g'3; q.;. t

h. h

28. Manual control requires RCS wide range temperature and pressure

.g.;g instrumentation. .g, ;. I,$:q

29. Requires reactor shutdown by driving in control rods OR manual g

t ! g t, scram signal E anual opening of scram breakers O_R_ de-energizing Vp,. of rod drive motor generator. hx, l'h

30. Requires opening FCV74-1 AND FCV74-2. Handwheel operation is l.

acceptable. q-a $s:; v e-4.%.'. %*u. ?4g# )Y.% o o l'<..N ,8 ' 95? ADD 7 l. v ~ ~ 7-d' A.N f f,

,f r#'- ee- '~ ~ O v. u v v o u o Q O O O.. O O O O G O s., .s s s s s O h.'k

31. Requires Rf!R pump operability (temporary cables are acceptable) Afl0-

' 'zi, [: CCS water to RHR heat exchanger (handwheel operation of A train valve FCV70-156 or B train valve FCV70-153 is acceptabic) Arid C S }, P. M::' water to RHR pump seal cooler AfiD RHR pump room cooling (poFt'able L L(. blower is acceptable). J', ::

32. Flow path requires opening an inlet valve (EITHER FCV63-23 OR FC.V63-26) At:0 cn outlet valve (EITHER FCV63-39 OR FCV63-40) Tor s.
3

the boron liifection tank. Handwheel operation is acceptable. s. 9 , g} (key 4) or RWST Suction * (key 5)) A'iD_ (CVCS Centrifugcl Charging Pump *

33. Requires (water to charging pump via Volume Control Tank suction *

$g; (key 1) OR (Positive Displacement Charging Pump * (key 3) Att0 Charging 4 h: FlowControlValveFCV62-94*,(thisvalvemay'bemanuallyopenedby

f'

[g,, ;.;. isolating and venting control air from its operator)). g *6 't % ' $. 3'.. R T.- en

&.g.:

L; --3 a3, -t a s .' ^$ -:

' ~,

o $, l - f r.: Wj m < {h :. ~ T;.. y-s .e. -: : r

c h

.N N *$. ~g

.x 3

s ,:. X ~ O /.- -Fii*: J. C 4 .s

a 5

y O C 952298 m uum - mamaams-a-memm- .ma. .a

hId1h ! f .k f _- ~ tf G v .v v .a v o o v v v;. ~ b a u o o o I. 2 f I

p. -

'4 .( j n ,,g:::.; TABLE 1-1 1 r.- Toj The following table summarizes the fire protection systems provided ,7.: in the Sequoyah fJuclear Plant. The table covers only those areas where an uraitigated fire could af fect-a unit's ability to reach and s R.; :. maintain a safe cold shutdown cLndition.

j

.) - s. [:: :{ Netes: (1 ). Refer to the SK-1000 series of compartmentation drawings O for location of the tabulated areas. $.*". g i s } (2) The compartmentation tire rating column identifies 3- %[G.; } - the rating of the most limiting component in the compart-3 mentation boundary. Refer to the response to question 3 S [.f-for a~ 'tional compartmentation information. 1A

1, (3) Refer ts the response to question 12 for a discussion

, y; g yj .j of the fire retardant coating of exposed cable trays. y.f.: g> $g. r. { h) Legend: I - Ionization smoke detector K-f IR - Infrared flame detector d': ^ e LT - Linear thermistor PE - Photoelectric smoke detector

1 RC - Rate compensated thermal detector i ?,~

T - Fixed temperature thermal detector D' .i T,. - d 2: .gl:.:;- e.:

g. : y -

e ? W' ~ ..) I h*=], ' 'g1 W.; l *<..,pl: ' F. E. ': M. r: h::., ) :g's. er.;

@$ i h

S A hN.i 4.$5.k: .k...

.s 1o e

l .: 0 l l'.:: 'd 3,i: l :s t 1: 4 5 , s Q.' ' 'd t e o ke-36733 . I .NxNkN..*NdN? ?O:'M%RFd627".@$.':N$1N'"*'h:MN.S6I.:2:D:9MN.%W,4$NNS$$$$$$$3' e 21.I

.</4 b b b 3 v; .. '.$,'dO( t cC?.T!01 , r.. o w5 8 F,e. r!RE [$ ;. O o.- = RETAR0 ANT 55

0 M

e v. Tet Cr he' w .Q C" CD:9 ART!iENT COATif.3 CF Wr E"

- Ef5 N

E 'l g'h h gy CITICTCRS E;!LOING (LEY.

.0.

400'i NAME r!RE. RAT:% EXPOSED CA3LES yy d g p._ g ',@'3' C0:4 TROL 669. C1 t!ECHA'i! CAL EQUIPi:ENT 1 1/2 HR. X X X 4 I, RC O E Si5 E5 A uBa G5 20 IE 4 g.f. '[4 sQ t .n 4 ts.- @ O gg C t1ECHANICAL E00!Pt1ENT' 1-1/2 HR. X X X !. RC l o,>, w.

g. 79.

i ~ C' 250V BATTERY RM No. I 1-1/2 HR. j0-X X X I, RC N '?< 9(e)Ih* m8 I to 250V BATTERY ECAR3 RM N0.'1 1-1/2 t.R. s,$. g[ g g '/*.*.' '.s CE 250V BATTERY BOARD M NO. 2 1-1/2 HR. I Lu X X- .I . /$ ' ) .NM .Ud.' 1 1/2 HR. ON S O Cr 250V DATTERY RM r;0. 2 X X X I, RC lh O. ). I C: 24V & 48V BATTERY RM l-1/2 HR. 'b g X X X I, RC ' 'u *. .OW cg J Cr 24V'1 48V BAT. 80. & CHARGER O d'> (*), 4 * #.fd O RM 1-1/2 HR. X X I 4,3 W 9 .%I.S O Cr CO::U'ilCATIONS RM 1-1/2 bR X X X X ) )) I, 4 C' 0 I?ICitA*;ICAL EQUIPMENT 1-1/2 HR. X X I, RC [f,

'S

' [.- ?', ,.,., O k,4, b 'f sy Ci : C01R!COR 1 1/2 HR. X X X j 6 W C' 2 SECC::3ARY ALA M STATION 1-1/2 HR. X X X I .b .8,J$ Mjd; / C! 5TAIR 1-1/2 HR. X X S.i. kt31 .\\.' ] 9 C. STAIR 1 1/2 I!R*. X X },s* q s'g ij 685. ) C' Uf4!T 1 AUX. INSTRuttENT RM 1-1/2 HR. X X X X I, RC v'f. ' o [9f**j'[*-) C: CORRIDOR 1-1/2 HR. X X I S/*s c< .?,' N C: C0:'PUTER RM 1 1/2 HR. X X X X I, RC d j' i

Cu UNIT 2 AUX. INSTRUMENT Rrt 1-1/2 HR.

X X X X I, AC, . hj ' fA C: STA!R 1-1/2 HR. X X

p*.,

f*kj C: STAIR 1-1/2 HR. X X ,s

1,Js#lJ

'If

705. ) C:

CHART STORAGE - 1 1/2 ER.* X' X X X I , J,(, ff/: O C: SPREA0! % RM 1 1/21;R = I I X X X I

6,.
(<d C'

STAIR 1-1/2 HR. X X '[g g

#q i',s, g, C

STAIR 1 1/2 HR. X X f,o ,%,,,%g' 85414 . s s *. w

?.

n

l.

,)

J.nour separation catr.tained t:etween fire _,, area, containin,q char,t,r torage and spreading roo1: and other plant areas.

I' a'

w%R

!.Q ty:

c(g#,g s$, ' '.y. s {, g.. ,t., ' s, Y:b Q. .;'s,,w~$ <K'*z Q p !.v.I..?,1 6 %y ?.. ,p; . o.: u.

.~. {I N;l'{*I* m -r..

I* t .,N' ..... s. n wm :. r r~. pr i rs s,r. ~...,'......s ev.. * '.*

n w r t + r r t w C N.: N O Wum%N Y..w. v. c o-

.t

L / 'I LCCAT! Oft ,$;4,[, 3 PI M N ult.llu'r g,., ,4 ..e 1. _. /g f *~, ; FIRE . L .Sffj 3 J.5/* RETARDANT UO 00 t' a it?! CF

).

.C. CO:'PARTME NT C0ATir:G OF Cdx D* .-- II r I* r wp h". .(.q. ; 80% SM

i: 8' o$

DETEC:Ct1 >4 (1 I: Titt [ E'.* !L D l'i,. . LEY. f.0. R00M NAME FIRE. RAT! rig

xPOSED CA3LES MU%

Ely ..gle'.~4 ls;;2 m ig.e O. E U "2O omm um 3am

f U

" Os "e - Is'. e. 8 er mm p, v i- / ir r" f pg f) C01 TROL 732.0 C1 MECHANICAL EQ'JIPP. INT RM 1-l/2 HR. I go.e g x g ge 4 l 3 .g# #. C2 JA*;! TOR'S CLOSET 1 1/2 HR. x x x g .j. j.jp, C3 CCRRICOR 1 1/2 HR. x X X I wg s ,;RC g.- pU C4 xiTC tN i.i/2 HR. .g g C5 T0!LET 1 1/2 PR. x x x g, gg f,*' x x x ,/ I m o C6 LOCKER RM U 1 1/2 HR. X X X !. RC O N .f,? 3 C7 5HOWER 1 1/2 HR. Cf. # I[' - x x O3 C3 5H0 tE'R 1 1/2 HR . # *.[. C9 Ir.5T. CALIS. 1 1/2 hR-b X X X ! RC .I .j,%f,' ' @f CIC SHIFT ErGR. OFFICE 1 1/2 HR. 4 I I 2 ! RC N ')p p p,' }< Cll SHIFT E!;0R. OFFICE l-1/2 HR. E X x x 3, aC ,'gg D r. Cl2 PA!.1 C0!. TROL RM. 1 1/2 HR. g , /); ,s g x 3,, CIL RELAY EM 1 1/2 HR. .f pfj x x g C1c RICCRD STORACE 1-1/2 HR. x x x- !. RC N f, [ / s. n b

NN*

b,k .M.T6,, t ss J4 ., { 's. a ' LOCATED IN FILTER DUCTVORK AND GENERAL AE A. b,5

- sg "LCCATED IN CABINETS A.ND GE' CRAL AREA Ih'

. $W tv '" CLOSED HEAD SPRAY IN CHARCIAL FILTERS. m Dc - r<}.i : t. v i .,3 ss m ' m .. ~ ',, p; $,.,s.- sl7. y1 +m*!

r tt

'. w n, y m.;:. \\.H &. - &s 's ; s., 4s!..s 6 7..y i w

m...+,

. 9 1s j?<

..JFa X.

qA.g.,,,;m v.<ry.swg,y.9,w:.: w:n s.sessss.y,. ::: ass.y:,.,.s.w:,,y: ymya, c.,y.ee.tcy, w ~ wyyyn

afe. - s se

dl.,* ~ 3 f.

10 CAT!01 'l'A.. pryo ?r.., 's22*, M,?y I F IRt' d 5 kI. '/ ' S kJt*gj RETARDANT U$ 00 I' wC m TYPt Of

e, 4Q 00" CO.v.PARTMENT C0ATI:G OF Cde

~E-Er '. '%rgy su!LDI:4 Itty.

.0.

Aco't NAME Flat. RAT!hc .xposto cAatts Mis c =g M;S 7 C F:EI '8.',/ d=8 n{ r 9 y,/ r ce n sec E:= ctit TO.ts Y7,

a. m m om Bam e

e w<s -,ee*.., a:; n us

e. y.

em

e. -

,x.. j,'[t ,?.*I.'p] 's CONTROL '32.0 c15 CORRIDcR 1-1/2 HR. x .x f,f,- ?<g s;3 t., s C10 P.S.O. [NOR. SHOP 1-1/2 HR. g'd X X x

1. RC

'pj. ,E C1 STAIR 1-1/2 HR. O X X ? g U s v ty C2 STAIR l-1/2 HR. X X .9 ,sa. w.: 1,

f $a,4

!5t aa 6%a f

O

'b ff. U .f4& N.* 2 O 2. s.>. Na ow ?f .%m, }Rd We Ea S st a5 4 .v,u,,;3.s. e.

3 <<>.

.h em s- ?& t&- .:te w.: w .W: We '.W:M, f'a. n u

3,a.vj u-

,v 4,'. 't V , t.,.~n. ( r s.o n g'g .. 2: c. m* V.fi < g /g'*g* f.ef:f-o ;/(/v s 'e . c... t 9.!: ' *

d 'C

,, c.;'.; I'd "#h'# 85413 f. .pp'.) Q0@ .%').t. ) o .,.{. '.'s,' t w i' f;;,% i;,9[?;9? f ( l 4?. ,<*D'q., 'i.(fJ s. M (2g g,'. 1,' -:..l Y:s.s.% i % s. .} *;5...*f. .f,.l y . i- .,g e -

'{;'?. ih'q'

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f.~l.f '! ' e O , $, C lg.;h(.b,:,r l*'f PW@qMNf;$m$;:;$$w;5; ) ~. 3 y

ggg*3g. y. a,. 3 f'

k'OS['EN?Ndi$$p@f@!!$!!@Ndb .r z';}'$;

. 9

.,4 ydMl; p.n e;:s,;. y: . y.:;. w

+.s:;p;.y n;>;.

$MhMyx p.# pdd 3$ s $.Pv. g C'5 f.s F M nu. M L:

fT i

(, t0 CAT 101 e, ,m, 'Nf) O ' + = E h,b gd$ g FIRE , 'E' T9E OT b. ~1 RETA CA*4T 55 W. M m Z E F*AE I'

j

? 5*T COMPARTMENT CCATit.G OF Gd= 9*

- E =

Ex !53!LO!*.3 ILEV. :.3. R00'1 NAME FIRE. RATING ..'XF05ED CA3LES UQ g.] 8% y $j3 gij DETECTQ15 3 (y r /g. s bh5 Eih b5G GG PO ME 7

/

p 'y(M f { V I"l AL'X!LIARY '51.0 A1

- ASTE HOLOUP TANK X

X /,

fa3 6

Pf,. f A2 'A5TE EVAP FEED PUMP ' X X

h.,

.53.0 Al CORRIDOR X X I ee A2 HOLOUP TANK ROOM A 1-1/2 HR. ). X X }. D s s' A3 HOLC'JP T*.*:K R00M B 1-1/2 HR. m ($ X X / LA > AC Ft004 DPAITI COLL PUMP & U N = h b FILTER ROOM [ X X U 4 A A.* FLOOR DRAIN COLL TANK ROOD gQ X X ' o t. QIj A5 GA5 STRIPPER FEED PUMP .X X I I. g-4,. uc3 AS SUMP PC:P ROOM Lu < X X .'a,- 3 }m*' f0>. Q:2 A7 Sur P TANK ROOM <( 6. j X X G s ) I@ )/ g(%

.f Aa CD

!A!:::E::T SPRAY 18 8 1-1/2 HR.

U~ X X X ,iy A9 C0*iTA!!; MENT SPRAY PUMP 1A-A 1-1/2 HR. X X I ,7 / Alf PHR PUMP ROOM 18-S 1-1/2 HR. X X k k-All RHR PUMP ROOM 1A.A 1-1/2 HR. X X 'N[ ,1 Ali RHR PC'P 900M 2A-A 1 1/2 HR. X X N '-j; A1: PHR PtMP ROOM 23-B 1-1/2 HR. X E I ,.,.4 ) ; )] X X J h,' A1 C0'JTAlic:Et4T SPRAY PUMP 2A-A 1-1/2 HR. ., p. ~ f'. A1C CC'4TA!r;t1Et:T SPRAY P' MP 28-8 1-1/2 HR. X X N J c-p ,l* Alf P!PE GALLERY 1-1/2 HR. X X 7 .g 1 s A17 PIPE GALLERY 1-1/2 HR. X X b }2 ,C69.0 Al CORRICOR X X X X g 4 A2 VALVE GALLERY I I X l ' ')r'*/./ v. k, ( 6. O N.' 3 A3 GAS DECAY ROOM X X h, p %.i

.,,#',t.

e es:07 l ..,f. 3 .g* ..) r 4 ..r ; ~.,; * '/ '6. *2. %,!>lA'4,-

R,

, }3.. + - . ;. 'f$ s l s

t;;

'

l o.e u.

h @.i'.,* $ d @.*E @ $'A$s $' $*$ $, $ $ i M P$$NW,.l \\.S3(hb.y b FluL n >.l.. .f tocn:c:: r,s, .m x..,

-. i (yi 3

u

'I O FIRE m

Tr?I CF I. 's RETARDANT 55 00 0 - I' i., 3 .M E" C0:4 Pant'Etif COAT 1::3 CF ? Cf = 0* ., Il = E-M 3 IDE / s / Ji 9; S'JM!' 3 ILEV.

.0.

200:4 ftA.ME FIRE. RAT!::3 LXPOSED CA3LES yy 3y $s N $5 gg CIIICT;25 f rfN O l' h a ish 655 GG 20 "iE @Yh ,# '.9 hk ,f' AUX!LIARY 669.( A4 CHEff! CAL DRAIN TANK ROOM X X X O fd[*- N A5 GAS CECAY ROG't X X r .~#.1 t[ A6 f.UX FEE 21ATER PU'tP 1 A.A 1-1/2 HR. X X X !. RC ,' ). g .,f O A7 ?!PE CALLERY 1-1/2 HR. I.D x x x g g

(/f v l,}/,,,

F A0 P!PE C#.LERY & CHASE yg X X b. .i# # ' O A9 CHARG!!jG PU!1P 1A.A 1 1/2 HR. O-8 X X X I, RC .s O C /$V a' *}- X X X !. RC k .,. /p 9 * %,'*f y Alt. CHARG!!:G plt:P 13 8 1-1/2 HR. w X X X I, RC d/, (.f.', [. k' #h's[,sh { [d Al; SAFETY lt1JECTIC:1 PUP.P 18-5 1-1/2 HR. X X X I, RC // u Al' CH'RG!!:G PU"? IC-C 1-1/2 HR. O4 l,, ..Aj9, fy)/ 4 A1 SAFETY !?iJECTION PuriP 1A.A 1 1/2 HR. X X X I, RC ff g ff,h r / l, yk Alt CASK OLCO' TN. COLL. TANK ROOM I* X X X f 0,6l: y* Air SPE!,7 RES!'l tat < ROOM X X X

- N-w A13
'/.LVE CALLERY X

X X g g' l[. g ) A!; "A!T! EVAP PA*r.A0E X X X

/

. <j.h 7g. Al. A'JX *.:ASTE EVAP PACKAGE X X X M.

pf,

- f {*.* O J 'pf[; AIC 1ATETY !!!JECTION PUPP 2A-A 1-1/2 HR. X X X I, RC /*/ r* A2'. S AFETY !!!JECTIO's PUMP 23 8 1-1/2 HR. X X X I, RC

j

#d,['#h]!

g A21 C'IAR*! :G FLTP 2C-C 1-1/2 HR. X X X I, RC ,h 5,b ' [,f,.}'f A2:' CHARC!!.G PU:'P 23.B

1-1/2 FR.

X X X !, RC 3'/Ys A2' CHAR *!f:G PUPP 2A-A 1-1/2 HR. X X X !. AC [i ) 4 .. ;,,< \\

. r

. ~ ~ - s 6:s s A2; P!PE GALLERY & CHASE X X 4.. 4 h**h G ['I' ~4:.y{.f.3rd. A20 P!PE GALLERY 1-1/2 HR. X X X

f.,

i 2 AUX, Fi!0YMER PUMP 2A-A 1-1/2 HR. X X X I, RC 1- .femk..g i. Av Cc.sCENTRu E r! uCR X X g.- v'.s' l 85XO6 .: #s* t. y/ k.* f+.$J}z=/..s.h l- . fg: ...- L id.'<.r.: , x c v, 1 G J.!&:.jN N. '.'. e 5k.+ W O (s' s.::),.,k,:'5.'4.' {.:;.'.? ?' .M .i.02cs Q s< M '*< h.* 9..,. - j(p.-@:! e .p. ..i.,-

t..

A.;,

%t ae s 3 t CC.TIO " ' W * ** ~ -. = .w.'c

l*)'h.g j$

ti 4 o n. FIRE -gp.'j$ '.- RETAR: ANT 55 9. t' ,5 Tirt :r I l'als,i m 4 CCXPAUMEtiT COATIrG OF G If = I? "

- M =

~~ / SUILD14 ! LEV.

.0.

R00'4 NAME FIRE. RATING xPOSED CA3LES !!U W =j 8R% Pb $'?? y f*;E 5 og CETECTCAS %., *., 3 ',.., 5am t! 2' O M' a. U dN E..U.a E..t.- a m.n am ma a ld i nh eg r;.*., y j'g gati. 6,,1,/, bd. A x x g g Pr x x x r'fl 3,,/ A3 TITRATIC:1 ROCM

- =

x x x g r ), A4 RADIO CHEM LAS. "es ,s - p. x x x g s g6 AS COUNT!r:G ROGM ne* >1 c. X x x . / /,/ 3 r e.' 4g

/"f f'/

A6 P!PE CALLERy uggi 1 1 1/2 HR. A U x x* x x. g.f, pgn. l ,j . cep,'f g / if 6 A7 VOL CONTROL TANK R00Pt 1-1/2 HR. % us x x x Y/ /, k I AC REACTOR BLDC. ACCESS RCCi1 3-HR. Od 3 g g ".j.jp'j O A') valve GALLERY h y y, 5 4 I A10 SEAL ',ATER HEAT EXCHANGER 1A D ~<~ l 'f f. o us a x x < 3 a: J All NEAT EXCI' ANGERS 10 ' 1-T/2 HR. y; x [' fy* ] AR H~AT EXCHA?iGERS 1A 1 1/2 HR. d [ x x 'ff[g 3 gg A1: St# LE POOM ! 1 1/2 HR. x x x g

g/

i, ,j> A14 SfMPLE RCC'1 !! 1 1/2 HR. x x x g I g Ali HEAT ExCHA!:0,ERS 2A 1 1/2 gg-x x ..y,: a. Al" HEAT EXCHAt:CERS 28 1-1/2 HR. g y '* /'/.*.' A17 SEAL 6ATER HEAT EXCHANGER 2A l [/f.'h'*Ih k' ) AIT VALVE CALLERY /sS.j Als P!PE CAttERY UNIT 2 1-1/2 HR. x

k;p x

x g i A2C VOL C01 TROL tat:X ROCM 1-1/2 HR. x x x g*** PE*** l

3.,. '{0! e A21 REACTOR DLCG. ACCESS RM.

3 HR. $.y!.. x x . '?}.

!N CHARCOAL FILTERS r

.f 3' fa.

- LCCATED !N GEiERAL AREA.

ff[$,%', i

/.

l "LCCATED IN CHANC0AL FILTEI CUCTS. l f4e #? i ""LAGORATORY CC:4? lex SEPARA' ED FRO'i Aux!LI,RY BLDG SY A.-HR. FIR BARR!EF

y. -.

r 5' 85205 .-p r, . s;c f,@v:. s..f.*$,,'.h %l>}$.y ][dS s ...Yi" , v

. n

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h' q;.)7U//l i

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R. f.. ?

Cab 1e or y1 ;:j 1C,.. m... N.e,y (f r A (. h Conduit No. Function Reso'.ution + id r n F..~.:.. ' 3 J.W ' 1PL4742B CCS Pump 18-B Supply Relocate conduit to previde minimum 4 F,W.;) 'J. IPL4743B 20' separatloc.from train A L (Ur3 ~41 / W:D p.; 2PL4742B CCS Pump 28-B Supply Relocate conduit to provide ministan 2PL47433 ^ (A ' *l. h.,l4:!"d/ k.,ysy l 20' separation from train A w.{n:y.'j7'.l.,s IPL47483 CCS Pump 18-B Control Route in conduit from 480V S/D Brds. to r f. g );9 - . ;.. : ' Ml e 2PL4748B CCS Pump 28-B Control pumps with 20' mini:m separation from t redundant train A circuits P;,"M J. J;W p g !H ? Q..p 1PL5025 Reciprocal Charging Route in conduit from 480V S/D Brd. f .. O., I .1 Pump Supply to pump with 20' minimum separation f r W d : g;' from redundant train A circuits E Q'? O.^f Y- + ;a Jr? k 1PL5026 Reciprocal Charging Route in conduit fro:n 480V S/D Brd. 9 .' -. ? e,7 9 . ' i.? Pump Control to pump with 20' mintru.1: separation 8 ,J. t, from redundant train A circuits'. l'

.n.M f V A ' p.:.b

o 1PL3021 Reciprocal Charging Route in conduit from 480V vent Brd f.

'M M 36-l'f;l IPL3023 Pump Room Cooler to Room Cooler with 20' minicum E: y '.? gg '5 separation fra, redundant train A E.: <;*a d.C,;.J ]

J pi

2.. n circuits 1

4 ;b M, IPP800A Pressurizer Heater Route in conduit from cable trays .:t t.1;r.jp,.MT '.3... T) elev 734.0 out of area containing ? 2PP800A Transformer Supplies AT-A and AS-A at elev 759.0 to I:i ': 'Hfy. '- ; [.

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train B circuits and back up to E. V :.;~b..c, n:.~::].,. press, htrs. on elev 759.0. (-

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v 9* *n s ; Cable or 4 p'M..'.,N;p I %d Conduit No. Function Resolution .r.,. s.... ."M ~;!. ; f ('b to ptmp with 20' mintszas separation p':y'[;{.'/ 2PL5025 Recipmcal Charging Pump Supply Route in ronduit from 480V S/D Brd. ., Y...,y-F ;,7ld. ;i. j.' 3 from redundant train A circuits. ? ,g...-4 2PL5026 Reciprocal Charging Pump Control Route in conduit from 480V S/D Brd. " 17 gj-to pump with 20' minicasa separation i rf p;a.gQ,-lil from redundant train A circuits. + 1r ilO .,5.a .....c., ..s p 2PL3021 Reciprocal Charging Pumo Room Route iri conduit from 480V vent Brd. V.".r. %*M. i H d Cooler to Room Cooler with 20' minisus l k1'.lg",Q*T separation from redundant train A (. /. < -.,. circuits. . = * *' ..... N. ' y hl. '.*, m yo .] .,(,, ,;,$. ;: M.'ffs, s . tMir *ii.a.,fE' '.Q f,,. . }f.vi.o

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4..

pit..T fd.e.

$'j,.... ::f:3 auxiliary building, from the reactor building containment penetrations at auxiliary building EI. 734.0 to the .3' control building Q-line wall penetrations at auxiliary building EL 714.0. These conduits are: protected g l 9,3 by an automatic sprinkler system. ?.I y,. :t.,! ".i.s,. e r f.. s>-:!?$ ' (hj?g'r,[g,h E' Conduit No. Function 5 cW; )* '.. k~~wN T.3-S:' IPM1001I Pressurizer level and pressure indication, loops 2.and 3 IPM1002II steam generator instrumentation f, h'NDP'M)c IFM1003!II M,7 ".f.2 1PM10041V ii kd IPM10681 sl

9..1. '3

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), .. ;.3.g " *:. CIRCUITS TO BE PROTECTED BY A 1/2110t14 FIRE RATED BARRIER I f..?. ' k%.,' ..u .jr [J

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.? The following conduits for unit.2 operation shall be wrapped in a 1-inch-thick BfM Kao wool Blanket in the .'d.$ auxiliary building, from the reactor building containment penetrations at auxiliary building El 734.0 jf [.., ?: 3 to the control building Q-line wall penetrations at auxiliary building El 714.0. These conduits are '... :/.+I., l

M;

'.V. protected by an cutomatic sprinkler system. (! ,;. q a-5- b: )3 f g '- Conduit No. Function ux 5 .,d. i f.7 fM 2PM1001I Pressurizer level and pressure indication, loops 2 and 3 steam generator

h. h 3 g

instrumentation I d

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e. n- .y , (,n c o b. y :, TABLE 1.4 ti .n s,.- ,s.6 bs ':' W* ,.. M.s r CIRCUITS TO BE PROTECTED BY l-1/2 HOUR FIRE RATED BARRIERS 'd. c 7.2.[;; s (;.-- ~ p *'.] !W The following conduits shall be enclosed by 1-1/2 hour fire rated barriers utilizing a UL- [C. 20 '] I' ,M approved configuration from the junction box at UA1, auxiliary building EL 690.0 to UA6, h 1 [7.

i..lf; auxiliary building EL 734.0, or to the point where the conduits transition to cable trays 7' ' d...

Fl,; k by automatic sprinkler systems. 9 F.

W*

where 20-foot minimum separation between trains is achieved. These enclosures are protected e. O p ... t p..,.. p

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lOc 2PP785B 6900V-Power Feed to ERCW 480V XFMR 28-B c.

By. 'd! T. /Q

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r 1PP7128 ERCW Pump H-B Supply 1PP7003 ERCW Pump C-B Supply 'l L.:- Tj!.,c.,;h 2PP7008 ERCW Pump M-B Supply k.;. : - P.Q r* 2PP712B ERCW Pump F-8 Supply 4 ,A' f.i k..TW 1PP675A ERCW Pump A-A Supply ? d,. 1PP687A W ERCW Pump Q-A Supply F,'- - r.. Vk 2PP675A ?' ERCW K-A Supply 6 9.Til-if E 2PP687A ERCW H-A Supply %{; j O Vi V..-;. > :. Qy 5 f.l @ k. [% I i

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Provide portable blower for roce ca

+ r r.,a--) V. uf cooling U y

h. ;3,.,,,il. t.'d Fower to both RHR pump room IPL30415

..,.? g..,; 'g r,. s h. O h.,h t,[;i.:.' . 2.c..y(J' w-coolers IPL3031A .i. g ? t'd3 y 'L f . f;,.' [,..[. 4

Automatic and local control IPL30435 L

Ct u. i 7 '.,. ,4..... 'g j s~... } to both RHR pump rocci coolers IPL30338 P. e a_.f "..1, g,.O..N.. *:,tt; Col U.A7 E1. 669.0 Power to both RHR pump room IPL3041B y. t ,W! al -.f coolers IPL3031A l 5 4<..9 M'..f..::3l5 [.s L .'-J Automatic and local control IPL3043B l .g to both RHR pump room coolers IPL3033A c.,.,;.;, y i k 'j. bf. I. I Col. Q-S, A3-A8

Provide portable blower for room K

,( 'j.~ f,j..i.'. cooling {.

. ;%..s '(,,. -:.

-: Q*t. i., p'.d.y

.)

Automatic and local control IPL30435 k ('C.T** % y. v

.. *..- W for both RHR pump room air IPL3033A C

coolers T 'V. A. t.' J, * :.y L N (fc3... ;..g

Attachment A to Emergency.0perating Instruction E01 10 has been written to define procedures for e

r a an. r . M.%.;,./... Providing and placing into operation a portable ' slower for room cooling. { ,ll...~ :. .'..}

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ML20031B904

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ML20031B904

Text

Dear Ms. Adensam:

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