ML19274G223

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Forwards Addl Info on SEP Topic VIII-2 Re Onsite Emergency Power Sys for Diesel Generators & Comments on Draft Evaluation,In Response to NRC 780814 Request.Revision of Diesel Generator Loads Also Encl
ML19274G223
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 08/28/1979
From: Bixel D
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To: Ziemann D
Office of Nuclear Reactor Regulation
References
TASK-08-02, TASK-8-2, TASK-RR NUDOCS 7908300449
Download: ML19274G223 (54)
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Text

{{#Wiki_filter:r .m + c7, ~ CORSum8IS 1 Power ? 9( Company (dD W !r uinr General Omces: 212 West Michigan Avenue, sackson, Micnigan 492ot e Area Code S17 788-055o August 28, 1979 Director, Nuclear Reactor Regulation Att Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - ADDITIONAL IhTORMATION RELATIVE TO SEP TOPIC VIII-1, "0NSITE IMERGENCY POWER SYSTEMS - DIESEL GENERATORS" NRC letter dated August 14, 1978 requested Consumers Power Company to provide additionsl information relative to the subject Systematic Evaluation Program (SEP) topic. The NRC letter also forwarded a draft evaluation of the subject topic for Big Rock Point. Consumers Pcwer Ccmpany's comments on the draft evaluation of this topic are provided as enclosure (1) to this letter. The requested additional information is provided in enclosure (2). This enclosure also includes copies of plant operating procedures whica control loading of the diesel generator. Enclosure (3) is a revision to the tabulation of diesel generator loads submitted by Consumers Power Company letter dated January 19, 1979. This revision supercedes the previous tabulation in total and should be used in further consideration ef the subject topic. David A Bixel (Signed) David A Bixel Nuclear Licensing Administrator 2031 ~J82 CC JGKeppler, USNRC 7908800 g

CCT!ENTS ON NP.C DRAFT SER SEP Topic VIII-2, Big _<ock Point 1. Page 1 Paragrapn 4 Sentence 2 As the Big Rock Point (BRP) emergency diesel generator was not included in the electrical equipment qualifica ica lists, reference to Topic III-12 is inapp rop ria te. 2. Page 1, Paragraph 4, Sentence 3 This sentence indicates that periodic testing of the diesel generator will be evaluated as a part of SEP Topic VIII-1.A. This topic has been deleted from the BRP topic list per letter from D L Ziemann to D A Bixel dated April 16, 1979. 3. Page 4, Paragraph 1, Sentence 2 For clarity, this sentence should be replaced with the following: "Therefore, when the diesel generator tie breaker is closed, the generator must supply all of the loads on bus (23) demanded at that time, including motor starting currents. Loads from buses (IA) and (2A) are manually added by the operator." 4. Page 4, Paragraph 3 The information provided in response to the questions in enclosure 2 of NRC letter dated August 14, 1979 (forwarded herewith) will necessitate complete revision of this paragraph. 5. Page 5, Paragraph 5, Sentence 2 Sentence should read: "the review of qualification and testing of the diesel generator will be completed with SEP topic III-1." Topic VIII-1.A should not be referenced since it has been deleted from the BRP 5'P topic list. (See Comment 2 above.) 6. Page 5, Paragraph 6 The information provided in response to the questions in enclosure 2 of NRC letter dated August '. 4, 1979 (forwarded herewith) will necessitate complete revision of this paragraph. 2031 083 Enclosure (1; d

ADDITIONAL INFORMATION RELATIrr TO SEP TOPIC r ;I-2 Big Rock Point Response to NRC request for additional Information dated August 14, 1979. Question: 1. What is the maximum possible diesel generator (D-G) loading with loss-of-offsite power during accident conditions? Provide a detailed analysis to support your findings.

Response

The maximum expected D-G load with a less-of-off-site power coincident with a LOCA is approximately 215 kVA. This load will occur during the switchover to the recirculation mode for long-term cooling. The attached senario of a 3.53 ft2 LOCA describes the D-G loading sequence. Question: 2. What is the maximum step load which th D-G must assume?

Response

The maximum step load the D-G must assume is 166 kVA. This load occurs when the D-G closes ou the emergency 23 bus. The equipment that makes up this load is identified in the attached senario. Question: 3. Provide a description and the results of test (s) and supporting analysis used as the bases to demonstrate the capability of the D-G to accept the step load (s) (maintaining the voltage and frequency within acceptable limits) and supply the connected loads for the required time during accident cocdttions. If additional testing is required, it should be ,- conformance to the applicable sections of IEEE Std. 337-1977 and Tagulatory Guide 1.9. Retoonse: furing preoperational testing of the D-G in September of 1962, the D-G was loaded fer 4 hours at an avarage load of 185 kW. During the last hour of operation, a load of 340 amperes and 225 kW was applied to tne D-G for 3-4 minutes of every 10 minutes. The D-G haadled the, overload satisfactorily Currently the D-G is :ested in accordance wi.th the plant rechnical Specificacians which require that the D-G be load tested to 130-200 kk 3enerator output for a least 20 minutes during each operating cycle. A typical load test is performed as follows: - Using a 200 kW, 3 phase resistive load oank, a load of approximately 100 kW ir applied to the D-G for a period of 20 minutes. Load, voltage, current, frequer.cy, oil pressure and cooling water ter:perature readings are taken. - Load is then increased to 190 t 10 kW and is maintained for a period of 30 minutes. Load, voltage, current, frequency, oil pressure and cooling water temperature readings are taken. }, } } } fj } 1 Enclosure (2) / l T

- Acceptance criteria for a full load test is 190 10 kW at o0 F.: : 5". for 1 period not less than 20 minu:es. The test does not include atep increases. The single lar;est los: to be seen by the 0-G 13 the 100 hp electric ;re ;wne inich ta routinely connected during monthly test ng. Provide a description and the results of an ana;7sc te Questton: 4. determine if the duratton of the degraded voltage and/or f requency will impatr the periormance of the safety reiated systems and cceponents supplied by the D-G if the results c f the test (s) identified in Question 3 indicate that the vottage and frequency are not within the limits recommended in IEEE Std. 187-1977 and Regulatory Guide 1.9 during the step loading.

Response

The D-G is not step loaded during the full load test pe rfo rmed each cycle. Test results are not available to indicite the duration (if any) of degraded voltage and/or frequency due to step loading. It should be noted that the initial step loac is composed of both reactive and resistive leads. Large reactive loads, such as the electric fire pump, are not seen as vatts by the diesel engine antil such r.ime as the fire pump motor is at or near its operating speed (ie, high inrush current is reactive VARs unich establishes a magnetic field in the motor). Question: 5. If the information requested above does not demonstrate that the diesel generator has adequate capacity for a loss of off-site power coincident with an accident, describe the corrective action you intend to take.

Response

Consumers Power Company concludes that the emergency diesel generator has the capability to supply accessa ry loads that may occur during a LOCA coincident with a loss of off-site power. The senario and load v. lues used thereta are conservative as discussed below: - A large break LOCA occuring at exactly the same time as a loss of of f-site power is considered extremely remote. A smaller break LOCA could be postulated to occur which would require actuation of the reactor depressurization system (RDS). The RDS will depressurize the primary system only af ter a two-minute time delay. The initial step load will be reduced in this case (compared to the scenario attached) since the core spray /21ve load will act occur for a least two minutes and the fire pump flow demand will be low until the core spray valves open. - The single greatest load demand is the electric fire pump. For the purposes of this analysis, the nameplate rating of the electric fire pump motor was used. Unless still another failure is assumed, namely the diesel fire pump, full flow will not be required f rom the electric fire pump. 2 Enclosure (2) 203l 085

- In most cases, realistic load data is not available for this analysis. As a result, many of the loads assumed came from nameplate ratings. Since equipment is selected with operating margin, use of nameplate rating is conservative. - Instrument and control transformer 23 supplies three power panels. The load due to this transformer has been conservatively assumed to be the sum of all possible loads connected to these panels for the duration of the LCCA. Also attached for information are Operating Procedures SOP-28, " Station Power," and EMP 3.3, " Loss of Reactor Coolant." These procedures describe operator actions in the event of a loss of off-site power. It should be noted that SOP-28 requires that the load on the diesel generator not exceed 150 ampere. This ensures adequate remaining capacity to power the electric fire pump (ECCS water source) in the event of a loss of coolant accident. f hhh 3 Enclosure (2)

SENARIO 0F 3.53 FT2 LCCA* 1. At time zero, a loss of coolant vccurs coincident with a loss of off-stte power. The diesel generator starts its cranking cycle. A containment isolation signal is received and isolation starts. 2. In less than 1 second, the steam drum level drops to the RDS evacuation alarin set point of -4 inches below center line. Any personnel inside certainment would proceed to the mechanical escape lock. 3. Any personnel that may have been inside the equipment or personnel locks would be stranded until emergency bus 2B is re-energized by the diesel generator. The bus is expected to be re-energized in less than 15 seconds. 4. At 1.2 seconds, corresponding to -20 inches steam drum level, the RDS timer for automatic blowdown starts. The fire pump start signal occurs at this time as well. 5. At 11.9 seconds, the primary coolant system pressure is less than 200 psia and the reactor water level is less than 2 feet-9 inches above the core. These criteria satisfy the requirements for the core spray valves to start opening. 6. The emergency diesel generator starts and energizes 2B bus at 15 seconds. The total load on 2B bus when it is energized is: Fire Pump 108 kVA Core Spray Valves 5.3 Lighting 14 Gland Seal Exhauster 4 I&C Transformer 24.3 Air Locks 10 166.1 kVA 7. After the core spray valves open (approximately 15 seconds), the load drops to 160.3 kVA. 8. It is assumed that if any personnel are trapped in the air locks they will start exiting as soon as 2B bus is re-energized. It is assumed they will be out in one minute. The load will then drop to 150.3 kVA. 9. It is assumed that the operator will require 10 minutes in order to manually add additional loads from 1A and 2A buses. Immediate loads f ece bus IA are the battery chargers for 2 of the RDS uninterruptible power supplies (UPS). Immediate loads from bus 2A are 2 of the RDS UPSs and the station battery charger transformer. The RDS system will have been

  • Reference submittal dated March 7, 1979, frem D A Bixel to D L Ziemann,

" Big Rock Point Plant-ECCS Analysis." l ) h [ Enclosure (2) 4

operating from the CPS batteries up to this point. Each battery will have spent approximately 1.5 ampere hours. When the battery chargers are placed on the emergency diesel generator, the chargers are assumed to go to the current limit output for 5 minutes at which time the batteries are restored. Neither the RDS nor the station batteries are assumed to be discharged at the initiation of the incident. Frequent battery surveillance and DC monitoring systems are designed to prevent this occurrence. Thus, the load on the EDG is stepped up to 201 kVA for 5 minutes and then drops to 161 kVA. Refer to Figure 2 for individual loads versus time. 10. When the containment water level reaches the administrative limit of el 587' (assumed to occur in approximately 12 hours), the operator will open MO-7066 to provide fire water to the core spray heat exchanger and will start one core spray pump. Load sill increase to 215.3 kVA. 11. The operator then closes two manual valves isolating fire water supply to the core sprays. As this decreases fire water demand, it is expected that the fire pump power demand will be reduced from its maximum rating. Total generator load at this point is expected to be less than 215 kVA. 2031 088 5 Enclosure (2)

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3 STATIOM POUER Systen Operating Procedurcs - SOP 23 Rev 7 4/16/79 1.0 PURPOSE The station power procedures provide the neans of energizing or renoving from service thc.various components of the systen. In addition, it pro-vides the correct systen lineup for various evaluations. The purpose of the station power schene is to provide a reliable and stable power supply for all plant electrical loads. 2.0 TECICIICAL SPECIFICATIONS AMD ptANT P20UI?JDC3NTS 1. TECHNICAL SPECIFICATION a. Section 11.3.5.3 ...._A: % _,s m 1.- .'\\ c"= %.7 i~. n p,-r

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" - d 'i d 4 4 ij y q.y, g 2. PLAMT REQUIREMEMTS n, :f g The 125 volt d-c battery systen shall be operable at all times. a. Immediate repair or replacenent of charging equipnent should be initiated upon any failure so as to insure continued availability of the battery. Conalete breakdown of the 125 volt d-c systen would regnire shutdoun ot the reactor, b. The 200 kU cnergency diesel generator shall be available for opera-tion during all pouer and refueling operations of the reactor. An approach to criticality will not be attenpted unless this systen is in an operable condition. If this unit uust be removed fron an o; crating condition for a period in excess of 30 ninutes (because of any deficiencies), approval must be obtained f rom the Plant Superintendent. Prining unter is available for the energency diesel generator cooling c. water pump from the house service. water systen, fire protection systen, or denestic water systen. If priming uater is needed, it will be used in the above order listed. 3.0 PRECAUTf0"S AND LIMITATIONS 1. If the primary or secondary 2400 V potential fuses blou, or are renoved, the follouing vill happen automatically: No 1 and No 2 reactor recir-culating pumps, "o 1 and "o 2 condenser circulating unter punps, No 1 and No 2 condensate pumps, and no 1 and No 2 reactor feed punp breakers will trip. The 1126 0C3 uill open and 7726 will close. All rotating equipment except the reactor feed punns and reactor rceirenlating cunnn will restart, with their respective time delays uhen the 7726 closed and the funen are replaced. 2. The 2400 V potential fuses nay not he renoved or changed uhile the plant is in normal power operation. Uni n t ch in,a, of the potential fu.:e cabinet disconnectn the primary pot funes and causen nubnequent loss of 2400 V potential to the equipnent listed in 3.1. 2031 09i ~

sdD at'on Uneer - SOP 28 Rev 7 4/16/79 D PlD l' Yl" au 3.0 PDECAUTTONS A?!D T.I?f1TATIONS (Conts) 3. Renoval of or blowing of the 2400 B ground fault potential primary or secondary fuses will cause loss of ground f ault 'alarn detection. 4. If all statica power is lost, the house service unter systen vill be lost. The rubhcr spool piccc nust be inserted, service water valved out and either fire water or domestic unter valved into supuly the necessary priming and cooling vater to the diesel generator. The spool piece and necessary valving are located on the south wall of the screenhouse. 4.0 INITIAL CONDITIONS 1. Power available to 1126 and 7726 breakers with 1126 closed. 2. Station hattery availabic. 3. Emergency diesel generator available and in " auto". 5.0 REFEREMCES AND ATTACIPfENTS 1. UD740, Sheet No 1. 2. UD740, Sheet No 11.

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UD740, Sheet No 12. [Qu.:.n. Wdy r3 4, UD740, Sheet No 13. O.,, u.v q, q c-a n, :, 9 c >: e n. m 1 g... wuc 5. Print No 0740-G-30-101. ' U u un' % U.'d;> y 6. Print No 0740-C-30-102. 7. Print No 0740-G-30-105. 8. Print No 0740-G-40-123. 6.0 PROCEDURES 6.1 STATION BATTERY CUARGERS NOTE: Tuo chargers are available for service; however, only one will be in service at a time as they share the same 480 E input a-c voltage. 6.1.1 TO PLACE IN OPERATION 1. Check c-c breakers to the "off" position (both chargers) 2. Check d-c breakers to the "of C" position (both chargers) 3. Check the d-c leads connected to the batteries and d-c voltneter on cach charger cabinet readinr. upr.cale. If voltneters are not on scale, do not place systen in service. 4. Place the d-c breaker fbr the charger selected to. 'the '"on" por.i tion. 2031 092 =

3' . Station Power - S0P 28, Rev 7 4/16/79 / 6.1 STATION BATTERY CHARCER (Contd) .a 6.1.1 To Plaec in Oceration (Contd) 5 Place the a-c breaker for the charger selected to the "cn" position. 6. Check volt:eter is readinc approxirr.tely 129 volts. This voltage is the nor-'d floating voltage on the batteries.

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G.1.2 To Transter Charners i.: n *h Q:y,. (' f ? ?,?='.'. a".J" L_ "f.m,'.,.'.^;'*;.i n y' ..w .A d u,. 1. Open the a-c breaker to the charger in servlce NOTE: This vill cause a "125 V D-C Systen Trouble" alarn to be received due to loss of n-c power to the charger being removed. 2. Open the d-c breaker to the same charger. 3. Close the d-c brea%cr to the alternate charger. h. Close the a-c breaker to the alternate charger. Alarn received in Step 1 should clea ; check voltmeter readinc appror.imately 129 volts. This voltage is the nor=al ficating volta 6e on the batteries. ~ }

6. 1 3' To Alism Batterv Charcer for Ecualizine Chree 1.

Check battery dater level " normal" before placing batteries en overcharge. Turn " equalizing charge tine" clockwise to desired ti=e of equalizing 2. charce. Hor = ally, this vill be for a 2b-hour period. .. ~. 3. Check voltmeter reading approx H tely lh0 volts. At end of presee tine, charge vill automatically transfer 'cack to floating voltage. 6.1. !j Station Batterv Care 'l. Take specific gravity readings on pilot cell daily. If specific gravity of pilot cell reading is below 1.200, notify the Shift Supervisor and take specific gravity readings on nD cells. Place battery charger in use on overcharce. 9 2. Maintain level in each cell within the white band indicator. If uater is added, recurd the amount added to each cell on forn provided. ~ / 3. Enen 'oattery chargers are to be removed from service for r aintenance, t log the pilot cell readings in the Control Roon Loc. Upon returning the charger to service, log the piloc cell reading and, if belev 1.200 specific Cravity, place the battery on 2'4 hour equalizing charge. O g

3a Static .over a S0P 28, Rev. 7 r-18/16/79 6.2 E CRGEliCY GE::ERATOR 6.2.1 To Sunpon Escential Plant Load Uith 7 ercenev Diesel Generator Uith Losc of All Off-Site A-C NOTE: Generator vill be in service autcratically and supolying bus 23 and breakers 2A-23 and 1A-2B should be open. 1. Switch Channel 1 reactor protection syste= to alternate power supply (S6 switch). 2. Comect hose fro = the vell water systen to #3 air co= pressor and valve into cervice. 3 Open all breakers en bus 2A, except #3 air conpressor, RDS-UPS power supply (C and D} and Panel 2P. h. Open load center breaker 52-2A, 5 Close 2A-23 tie breaker. 3 6. Open all breakers on bus 1A, except screen structure bus 1C and RDS-UPS pcuer cupply (A cnd 3). qr W.u.- ~ c";n=a.a i. m n e .n.., % : v 'r w nrs -r u a wt;m e wn e U$$ $kMb 2031 094

h ,, Station Power - SOP 28, Rev 7 h/16/'(9 ( 6.2 ElERGENCY GEUERATOR (Contd) 6.2.1 To Succort E:sential P1r.t Load I?ith E errency Diesel Generator ! Tith Loss of All Off-Site A-C (Contd) 7. Go to screenhouse and open all breakers on bus except: The canal ca:ple pucp. a. b. The well house. 8. Open load center breaker 52-1A. 9. Close 1A-23. 10. Close station battery charger breaker.' on bus 2A. 11. Close a-c bearing and seal oil pu_.; breaker on 2A. 12. Fron control reon, start a-c oil pu=p and stop d-c pu=p. 13. Close substatica se_7 ice breaker en bus 1A. 14. Close turning gear breaker on bus 2A and place tuloine on gear when it stops rolling. t NOTE: Only if turbine has been off stean less than 2k hours. 15. Other electrical load may be placed on diesel as dee=ed necessary but not to exceed 150 amps. This will allow rcen for the electric fire pump, if needed. 16. Other leads to consider: iT.~~ n 1.u ; r;.;{ ;y.' h 'D l'A /\\ C* n.7.)s rN n%,,n% W ? ( .sn a. On bus MCC-1A: , ' n a e t..s b li '..g(Q (yf i: (1) Core spray pump Uo 1. (2) Clean-up purp. (3) Reactor cooling water pu=p. (h) Control rod drive pu=p. (5) Eearing drain enlargecent exhauster. b. On bus MCC-2A: (1) Core spray punp No 2. (2) Vapor extractor. I3) Breaher to Par.el 2P a.d poison tank heaters. On load center MCC-2C - Open all breakers except desired equiptent. c. I i i d. On load center I.iCC-2D - Cpen all brecher: except desired equipnent. l, On load center MCC-1D - Open all breakers except desired equipnent. c. 1 CH 3 ]RA, 2031 on i

^ Station Power - S0P 23, Rev 7 4/16/79 6.2 E'!ERGENCY GEMCRATOR (Contd) 6.2.2 To Reatore Station Power to Nornal , _/ 1. Open IA-2B hus tie breaker. 2. Open 2A-2B bus tic breaher. 3. Closo 52-1A and 52-2A feed breakers. 4. Place the emergency generator ACS auto selector to "of f." 5. Trip emergency generator breaker; then close bus tic 2A-2B. NOTE: The tuo tie breakers normally should not he closed at the same time unless running from one transforner. (See Note 1 on Drawing E-101) 2A-2D tic should be closed since 2A receives its ground protection from the 23 bus. lA has its own protection system. [j: ' s ? C % ~m.,, 6. Shut down emergency generator.

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[ ,j j' 7' 7. Close breakers to all MCC and breakers to equipment on these MCC. 8. Start a-c cmergency bearing and seal oil pump and stop d-c caerr,ency oil pump. a,j 9. Return reactor protection MC sets to service. 6.2.3 AUTO START ALE'?'ENT OF DIESEL GENERATOR 1. Check caergency generator ACE switch in " Trip" position in control room. 2. Check auto transfer to emergency generator switch in control room in "on" pnsition. 3. Check control switch on diesel engine control panel in screenhouse in " auto" position. NOTE: The diesel generator vill now start automatically on loss of power to the 23 buses. The 1A-2B and 1A-2B and 2A-2B tie breakers will trip open and bus 2B uill be energized by the closing of the emer-gency generator ACB uhen the gen.crator is up to spceri. Capacity of the emergency generator is 200 kU. 6.2.4 TO RETURN-SYSTEFI i'RO?! E!fERCENCY TO NORmL StTPPLY 1. Check pot cr restored to 480 V load center. 2. Check all load removed from buses IA and 2A and bus tie breahcrs lA-23 and 2A-2n open. 3. Close 480 y load center breakers 52-1A and 52-2A CAUTION: Eus 2D and the crernency generator must aluays be ir.nlated bcCora restoring out;ide feed. No prov.icion is available for nynchroninn. ,se 2031 096 'Mbkuekh,]d, li

6. Station Power - SDP 28, Rev 7 4/16/79 6.2 EMERCEfCY CEMERATOR (Contd) %./ 6.2.4 E RETURN SYSTEM FRC:f D'ERCE"CY To MOR':AL SUPPLY (Contd) 4. Place et,crgency generator ACB auto selector to "of f". 5. Open the energency generator ACE from control room. NOTE: If cmergency generator ACE is t:losed clectrically (ie, by the auto closing feature), it must then be opened electrically by use of the console scitch. Likcuise, if it is closed manually, it must be opened nanually. This provides the auto. closing feature on a poner failure and auto start on the generator. 6. Close 2A-2B bus tie breaker. 7. Stop emergency diesel at local control panel and place auto transfer switch in control room in "on" position and local control suitch on diesel engine control panel:in screenhouse to "aute". d h.y:f' I'.: " fy V -

n. ;n N N;O'n N<b"..,, d S.v D d~,a' m '.K " 7 6.2.5 DIESEL MANUAL START u

1. Turnthe diesel control selector. switch to " manual". Depress the nnual start push-butten switch intil diesel starts. "Emerg.cacy generator engine trouble" alarm vill annunciate until the selector witch is moved to " test" or " auto" position. NOTE: Limit,the manual start sequence to 30 seconds cranking tine maximum. Release the push button and allow the starter to cool for approximately three (3) ninutes before making a second 30 second attenpt. 2. 11 hen the diesel starts, release the push-button suitch and ruen the selector switch to " test" position. 6.2.6 TO STOP DIESEL CENERATOR 1. To stop the cmergency diesel, slouly turn the Eovernor control lever in the lower direction intil the lube oil pressure indicator shous 30 psig. This should be done over a one-minute interval. L"nca 30 psig lube oil pressure is reached, decrease the governor control lever to its low stop position rapidly. Do not release the governor lever until the diesel has completely stopped rolling. 2. When the dicscl stops, return the selector suitch counterclochwist to " auto". 3. Clear ala.ns and reset the undcrvoltage relay target (!:CC-2E). 6.2.7 ITEEKLY DTERCE::CY DIESEL CEMEDATOR TEST 1. Refer to test procedure T7-01.

7. StatJon Pouer - SOP 23, Rev 7 4/16/79 s 6.2 E![ERCENCY GENERATOR (Contd) ,V 6.2.8 DIESEL COOLING PATER SUCTION LINE I!F., TE", 1. Uhen freezing unether is a nossibility, niace heater control switch, located on the west side of the diesel enr.ine, in "on" position. 2. Check circuit reliability once per shif t by depressing the red push button mounted on the junction box at the north end of the diesel engine. A neon bulb located near the push button should light. Notify the Shift Supervisor of any heater failure innediately. 6.2.9 DIESEL COOT.ING UATER PU?!P SEALING UATER 1. Check prining water valve "F" closed. Valve is only opened on loss of pump prime. 2. Open service water supply valve "E". 3. Throttle overflow valve "D" to maintain a minimum constant flow. NOTE: During cooling unter pump o. oceration, the puma packing nay show slight leakage (20-30 drops /ninutef. During pump operation, slight parking leakage (5-20 drops / minute) is pernissible. 7.0 EOUIPMENT TAGGING NOTE: Thesc' tagging procedures should be used as guidelines. Depend-ing on the nature of work to be done, renuired tagging points nay be different to give working clearance. hj-?( "~; /=, t; j) e, n n.),ln 7.1 2400-VOLT EUS ge% 9 9 y '**** MIL-1 d 'iQ /' %%)l a 7.1.1 TO REMOVE FR0!t SERVICE NOTE: Plant must be in cold shutdoun, and conditions vill pernit interrupting station power. 1. Refer.to Section s.2.1 for transfer procedure of essential services to the energency generator. 2. Open 1199 and 2299 breakers and louer the breakers. 3. Open No 1 and No 2 reactor feed pump breakers; no 1, 152-103; No 2, 152-105. 4. Open recirculating pump breakers; No 1, 152-101; no 2, 152-107. 5. Place station power voltane regulator in "nanual" position. 6. Place the auto-can transfer celcetor suitch 43 in " manual" position. 7. Open 7726 breaker. 2031 098 D f P ii) OD T W slu aM b,,}(//L 1

Station Power - SOP 28, Rev 7 4/16/79 /'., 7.1 2400-Vol.T EUS (Contd) 7.1.1 TO RT.'f0VE FRO.'t SER"TCE (Contd) 8. Open 1126 breaker. 9. In the substation, check open the 1126 breaker, then open the 1124 disconnects. 10. In the substation, check open the 7726 breaker, then open the 7724 disconnects. 11. Open the 1136 breaker. 12. Remove the 2400 V bus netering and relaying potential transformer primary fuses and ground fault relay potential transformer prinary fuses (two sets of fuses). 13. Tag the following with red Workmen's Protective Tars: Bus retering and relaying potential transformer primary fuses. a. b. Ground fault relay potential transforner primary fuses. 1199 breaker. c. d. 2299 breaker. e. 1124 disconnects. f. 7724 disconnects. g n 9,,,, f ~ ; ypr{C a. 3 r.3,,,._,f'Nsil I3 .s:3 QgQ^ n. ty.p, rs s y 7.1.2 TO RETURN TO SERVICE c i-J b g.f ;'d g 1. Ee sure the 2400 V 'cus is ready for service and any grounds removed. 2. Check open reactor feed pung breakers; No 1, 152-7 03 ; No 2, 152-102. 3. Check open recirculating punp breakers; "o 1, 152-101; I;o 2, 152-107. 4. Renove red Uorkmen's Protective Tags from the following: Bus netering and relaying potential transfornar primary fuses. a. b. Ground f ault realy potcatial transformer primary fuses. 7724 disconnects, c. d. 1124 disconnects. c. 1199 breaker. ~ f. 2299 breaker. 5. Replace the prinary fuses for the netcring and relaying and the groun? fault potential transformers. 6. Clonc the 1124 and 7724 disconnecta. 7. Close the 1126 breaker. 8. Check station power vcitage rciulator ready for nervice. j

9. St'atton Pouer - SOP 2!1,fiev 7 4/16/70 /~. 7.1 2400-YOLT EUS (Contd) 7.1.2 TO RETT!P.'! TO SCftt' ICE (Contd) 9. Place voltane regulator selector st. itch in " automatic" position. ['" ';' r,.7,,,D O Check for proper coeration. Q.,)"~ve..,Qg(((-

  • n R ~,.~.,

10 Close the 1136 breaker. % 3., '~ 11. Close the 1199 and 2299 breakers. c.3 % ; y 12. Follow Section 6.2.4, to restore 480 V system to normal. l 7.1.3 TO REMOVE 1136 FR051 SERVICE NOTE: Before removing the 1136 from service, the plant must be in a cold shutdoun condition. 1. Follow Section 6.2.1, to place essential plant loads on the cmergency ] generator. 2. Open 1199 and 2299 breakers. 3. Open reactor feed pump breakers; No 1, 152-103; No 2, 152-105. 4. Open recirculating pump breakers; No 1, 152-101; !!o 2, 152-107, 1 5. Place the auto-man transfer selector switch 43 in " manual" position. 6. Open the 1136 breaker. 7. Check 1136 open; icuer breaker and tag with red Workmen's Protective Tag. 7.1.4 TO RESTORE 1136 To SERVICE 1. Remove the red Worknen's Protective Tags from 1136 breaker. 2. Raise the 1136 and close breaker. 3. Close 1199 and 2299 breakers. 4. Follow Section 6.2.4, to restore 480 V system to normal. l 5. Place the auto-nan transfer selector switch 43 in "ar.to" position. 7.1.5 To REtto"E PU'fP UREAr*F'R FR05! SERVTC 1. Open breaker frca control room. 2. Check breaker open, lower and tag breaker with red Uorknen's Protec-tive Tags. 3. Place Caution Tag on control handle in control room. h h b LJm wum:J '* ' 2031 100

0. . Station Pover - SOP 28, Rev. 7 4/16/79 ~ 7.1 2400-VOLT DUS (Contd) v 7.1.6 TO RESTORE PIUfD irtEAV.ER TO SERVICE 1. Check work completed and breaker ready for service. 2. Remove red Uorkmen's Protective Tags from breaker. 3. Raisc breaier to " operating" position. 4. Renove the Caution Tag from the control handle. u. A w".i-7 S '.

  • * ' ' t ' v :.2, e, a t: g <,g,s h2.% c t.7 4 !j ij y;,.

7.2 480-VOLT EUS

6, / 3 2

7.2.1 TO RE"0VE STATIO'! POWER TRA':STOR"ZR 11 or 22 FROM SERVICE CAUTION: The reacter must be in a shutdoun condition. Station ven-tilation will be lost. See S0P 25, Section 2.2.A. NOTE: When placing 1A and 2A buses on same transforner, reduce lead on huses to avoid exceeding breaker interrupting ability. 1. On load center to be renoved from service, shut down the condenser circulating water pump and condensate pump. 2. Reduce load on 4S0 V motur control center buses by stopping all unnecessary equienent. 3. Check other transformer in service and bus tic break'er IA-2B (2A-23) closed. 4. Open 4SO V feeder breaker 52-1A (52-2AO, drau out breaker and tag with a red Ucrkmen's Protective Tag. Open output breakers on distribution panel IF (2F). Open and drau out 52-lP (52-2F). 5. Open 1199 (2299) breakar, lower and tag uith a red Uorkmen's Protec-tive Tag. 7.2.2 TO RESTORE STATI0'! POPER TPWISFOR"ER 11 or 22 TO SERVICC 1. Check work completed and tools a,nd ground removed. 2. Check the condensate and circulating unter pump breakers open.on the dead bus. Check open output breakers on distribution panel IP (2F',0 .4 3. Remove red Uorknen's Protective Tans from the follouing: a. 1199 or 2299 breakers. b. 52-1A or 52-2A breaker. 01 4. Raise 1199 (ot. 2299) breaker and close. 5. Replace 400 V feeder breaker 52-1A (or 52-2A) and clone. Replace 430 V load center hrcaker 52-lF (or 52-2r0 and close. 6. Open hun tic 1A-23 and close bus tie 2A-2n. O O 7. Restore 480 V buses to norral load.

1 1.. station Poseer - S0p 23, Rev. 7 4/16/79 ~ r'- 7.2 480-VOLT CUS (Contd) s 7.2.3 TO REMOVE EUS 1A or 2A fro?! SEUrICE CAUTIO:f: This shall be donc only during cold shutdoun. MOTE: Ecfore isolating either bus 1A or 2A, the plant enuionent schedule should be reviewed hv the Operations Superintendent.

1. Transfer necessary services from bus to be renoved to other bus.
2. Check that bus 2B is being fed from the bus that will remain energined.
3. Open all breakers on the bus to he renoved fron service.
4. Open and tag with red Ucrkmen's Protective Tag the bus tic breaker 1A-23 (2A-2B).
5. Open and tag uith red Forkmen's Protective Tae the supply breaker to the bus to be removed fron service 52-1A (52-2A).

CAUTION: Uhen station power transformer 11 or 22 loads are above 130 anps, equipnent loads should be transf erred to achieve a balanced load condition for the two transformers.

6. Check open instrunent and control transformer breaker 52-IA-53 and tag with a red Uorknen's Protective Tag, only if bus 1A is renoved from service.

[.'k'ISgr. % amp"4 fl J %JWu,9 ((I.{,: 7.2.4 TO RETUPJI TUS 1A or 2A TO SERVICE 4

1. Renove red Workmen's Protective Tags from the followintt:

a. Bus tic breaker IA-23 or 2A-2B. h. Supply breaker 52-1A or 52-2A. c. Instrunent and control transfroner breaker 52-JA-53.

2. Close bus sunply breaker 52-1A o~ 52-2A.
3. Restore all breakers en bus to nor ;nl.
4. Close I A-2B (2A-2B0 bus tie breaker, if recuired.

7.2.5 TO RI ,i/E EUS 23 FROM SERVICE _CAUTIO?!: The bus 2B t'ny not be renoved forn service durinc: pouer operation or refueling. CAUTIO:!: '? hen taking 2B out of ser/ ice, LT3 uill be de-energized and atation battery voltage vill can to nnnunciator level of 120 V d-c in appro::inately one hour due to energencv lightin;, load. l. Check crmrcency nencrator shutdovn and control svitch in "of f" nonition. Caution Tar control sultch. ' O' J i 10c) 27 .} ,y.c a w c J

12, Station Pouer - SOP 28, Pcv. 7 4/lfi/70 y-. 7.2 480-v0LT EUS (Contd) s 7.2.5 TO RE".nVE BUS 2B F90't SERVICE (Contd) 2. Check open energency generator breaker 52 2B-27. a n,... 3. Open breakern on 2B bus. \\/ I" ,, - i u .i u olS' S y /;W:*^ C'.g I o.a . c NOTE: Inform Shif t Supervinor before opening breakers to sphere locks, and check that all personnel are out of the sphere. 4. Open lA-2B and 2A-2B breakers. 5. Tag the follouing with red Worknen's Protective Tags: a. Emergency generator breaker 52 23-27. b. IA-23 and 2A-2B tie breakers. c. Instrument and control transforner break:r 52 23-23. 7.2.6 ,TO RESTORE EUS 23 TO SER7TCE 1. Remove red Workmen's Protective Ta3s from the followinc,: a. Emergency generator breaker 52 2B-27 b. II.-2B and 2A-23 tie breakers. c. Instrunent and control transfarner breaker 52 23-43. / 2. Check energency generator breaker open. 3. Close 2A-2n bus tic breaker. 4. Place breakers on bus 23 to nornal. 5. Remove Caution Tag fron diesel generator control suitch and set generator for autonatic start. 7.2.7 To REMOVE IC. 2C, ID, 20, IE. or 2E EUS FROM RERVICE NOTE: Before isolating IC bus, check with the IIcalth Physics Dept to naintain canal namnling requirencats. Before isolating hus.ID, check stack fan requirenents. (See SOP 25, Section 2.2.A) 1. Ytansfer necessary services from bus to be isolated te another bus. 2. Open all breakers on bus to be removed from service. 3. Open and ta,3 with red Uorkmen's Protective Tages the nupply breaker of the bus to be renoved Eton service. 1C Supplied by 52-1A14 2C Supplied hv 52-2F2C ID Supplied by 52-IPID 2D Supplied bv 52-2F2D IU Supp1ted by 52-IrlE 2E Supplied by 52-2F2E

  • O D

U". 03* \\~

~ 13 Station Power - SOP 28, Rev 7 h/16/79 pr. 7.2 L80-VOLT EU3 (Contd) 7 2.8 To Return ic, 2C, lo, 2D,1E or 2E Eus to Serrice 1. Remove red Worknen's Protective Tags from the bus supply breaker to be returned to service and close breaker. 52-2F2C 1C Supplied by 52-1Alb 2C Supplied by 1D Supplied by 52-lFlD 2D Supplied by 52-2F2D lE Supplied by 52-lFlE 2E Supplied by 52-2F2E 2. Close equip ent breakers on bus. 7.2.0 To Renova Distribution Panel 1F or 2F From Service Caution: Removing these buses from service vill interrupt plant ventilation See SOP 25, Sec. 2.2.A 1. Open all breakers on the bus to be re=oved from service. 2. Open and tag with red Worknen's Protective tag, the load breaker to the bus to be removed fren service. 52-1F (52-2F) 7.2.10 To Return Distribution Panel 1F or 2F to Service 1. Check distribdtion panel 1F (2F) output breakers open. .^ 2. Recove red Work =en's Proteccive Tag and close load breakers 52-lF (52-2F) 3 Return Distributien Panel 1F (2F) output breakers to normal. h*I,$f,%,g f., 73 DIESEL GE"ERATOR , ~ ' w.'a g ~1%,a's.~f%':.q b,r.p.4S ? b 'a v a '.J 7 3.1 To Re=ove Fre: Service 1. Place diesel centrol svitch on "off " position and tas on control i roon console. 2. Open and tag 120v breaker #1h on panel 10p t a battery charger. 3. Place diesel control switch to "off" and tag. h. Recove leads to starting battery and tag. 7 3.2 To Return to Service 1. Remove red Ucr :sen's Protective Tags from starting battery cable and replace cables. 2. Remove Tag and close 1207 breaker Elk en panel 10L to battery ch1rger. 3 !!otify Ibintenance Supervixor so that a voltage drop test can be performed to verify proper connection. h. Remove Tag und place diesel cont ol switch to " auto". 5 P.cnove Tag and palce the auto transfer switch to " auto" on control room

  • OD
  • 30 30l' M console.D *JL MJU VAL 2031 104 L

__..m_- 11 S t.a t. J on lim. i sop 28 - Rev. 7 h/16/79 r 6 7.h MTil' 4 CFJsP.GER 7.h.1 T.. t... cove Fre: Service ty.-n the a-c brecher for the charger in CCTViCC .i.. 26 h..n tb-d-e bre@.er to the sa.me charcer '). ld...nh50Vsuoplybreaker,52.2A-{2...:onnect d-c leads to sostion 1'c ~.r-i 16, S.1vn t,, the following with red 'Jorkmen's Prot *CtiV* T'8 4 h80 V breaker 52 2A-32. ~ l'. Battery cables. s.."-"-" ~ ~ U d' *c'.).'J

(r
,.'s. ;;, n.jj, a c 4.v..., ;t.q gj g g. Q

'e %fh..* s.'z y. N.lj, g g m G i.*' d 7 I.? % Return to Service 6 3 --e and d-c breakers on both chargers. + s-P. I., o e e ([o 1 en's Protective Tags from 480 V breaker 2A-32 and 1.rtttery cables. 1.

'innect charger cables to station bade 4

i' Lose the d-c breaker on he c arGe. e ted for service. Check V'>ltmeters reading on scale. 's.

lose h80 V breaker 52 2A-32.

vice. 6

lose the a-c breaker on.he e.narce.

d f,Ill' KLISTS !!on a. 2031 105 k h & Ek

'l , Loss of Reactor Coolant - FJ'P 3.3, Rev. 8 I,/4/79 f* / DP 3. 3 LOSS OF REACTOR C00Lt.::T Leakage from the Pri:nry System may range fren a fraction of a gallon per ninute to a ecmplete rupture of a recirculation loop. The severity of the consequences, auto =atic actions and operation actions vill be dependent upon the sise and nature of the leak encountered. These emergency procedures are subdivided into three categories to provide broader coverage of the various leaks that may be encountered. The subdivisions are: a. Minor Loss of Reactor Coolant Inside Contairment b. Major Loss of Reactor Coolant Inside Containment c. Major Loss of Reactor Coolant Outside Containment E!:P 3.3.1 MIUCR LOSS OF REACTOR CCOLU!T, INSIDE CONTAI:! E:T DP 3. 3.1.1 Synptoms a. Daily ' Primary System leakage calculations 'h (plant limits are 0.8 gpn unidentified and 9 cpm identified). b. Increased hunidity in sphere exhaust air. (TR9623 in Control Room) c. Noise from blo. ring stean or water. y d. Increased su p pu p running ti=es. (Timers /%#\\#f . A 9',sN 'M in Control Roca) O sj h % e s q n.3,T :' U t

  • O

,m n n '/Liirl.MiU c. Pipe way steam lear,. alar = on C-20 panel. f.' Possible increased CAM readings. Constant air tonitor readings and sphere exhaust. E::P 3. 3. 1. 2 Automatic Actions There are no autc=atic actions for minor lea':s. EMP 3.3.1.3 Immediate Ocerator Action a. The on-duty Plant Superintendent shall te notified of the increased lechage. b. The Shift Supervisor shall notify Power Control that the leaktge limits have been reached. 2031 106 D**)D

  • jD 030Y @

.o o M oMu2u1LnLa

2 l Loss of Heactor Coolant - EMP 3.3, nev. 8 4/4/79 a e c. If the primary coolant system leakage exceeds 1 g;m and the source of leakage is not identified, the reactor shall be placed in the hot shutdown condition within 12 hours, and cooldown to a cold shutdown condition shall be initiated within 2h hours. d. If leakage from the primary coolant system exceeds 10 gp=, the reactor shall be placed in the hot shutdown condition within 12 hours, and cooldovn to a cold shutdown conditien shall be initiated within 2h hours. e. Shut down the reactor in a rapid orderly manner. EMP 3.3.1.h subscouant 0:erator Action n. Maintain the steam drum vater level at or above center line.

b.. Place the reactor in the hot standby
  1. "f' condition within 12 hours and cool to cold r

wJ ,. -e m 3 9 /Mc., s u_ n 1 dr*W " shutdown within 2h hours. ""#~~'~~ uJ' Hold the levels in the condensate storage, c. demin water and vaste hold tanks at maxi-num. EMP 3.3.2 MAJOR LOSS OF REACTOR C00LCT, IMSIDE COUTAIU:E!T EMP 3.3.2.1 Symptenc a. Abrupt load drop. Feed-vater flow could be b in excess of that needed to maintain a corresponding steam flow. c. Increased humidit'/ in sphere exhaust air. 2031 107

~

  • 3

, Loss of Reactor Coolant - E!!P 3.3, Rev. 8 4/4/79 /* d. Reactor building ventilating system trouble alarm. Radvaste trouble alarm (from reactor building e. sumps hi h level). 6 f. Flooding in contain= cat (LI 3400 in Control Room). g. Flooding in radvaste tanks (local recorders). h. Decreased primary system pressure. (PI/IAoS) 1. Noise frem blowing steam or water. j. Contain=ent pressurized (pressure indicator on console). k. Steam drum lov level alarm (main console). Contain=ent evacuation alarm (RDS console). 1. Steam drum lov level scram. m. Channel (A-D) steam drum level low alarm (RDS console). Channel (A-D) fire main 4 pressure available (RES console). Channel (A-D) time delay starts (RES console). n. Pos+-incident spray timer start alarm. o. Reactor lov vater level scram alarm (main console). Channel (A-D) reactor water % F tf.*'; G 1evel low alarm (RCS console). gG{l;~&.g' W p. Channel (A-D) alarm time delay trip in 3 , y w;,p",Il.9;i.3"'" 30 seconds (RES ccncole). ~ q. Channel (A-D) time delay trip (RDS console). r. Area monitor alarms. s. High stack-gas monitor alarm. EMP 3.3.2.2 Automatic Actions a. Contain=ent evacuation alarm sounds when steam drum vater level is 4" below center line. b. Steam drum lov vater level scram at 8" below center line. D* lD

  • lD

' 3 Y h M eM1AHa 2031 108

t b . Loss of Reactor Ccolant - E:2' 3.3, Rev. S 4/ '+/ 79 t' RDS channel (A-D) steam drum level lov c. alarm at 20" below center line, starts cicetric and diesel fire pu=ps and starts time delay relay. !!OTE: Time delay relay can be reset to 120 at any time within 120 seconds renaining, if desired, by operator action at RDS con-sole. This reset feature is to be used only if the RDS actuation has been inadvertently initiated or initiation has taken place but the drun level is back to ncreal or recovering, d. Channel (A-D) fire main pressure available alarm en RDS console when pressure reaches 10'O lb on main frca cither the electric or diesel fire pump. Channel ( A-D) alarm time delay trip in c. 30 seconds alarms on RD:' console, f. Channel (A-D) time delay trip alarr.s on RDS console. g. Reactor low vater level seren at 2'9" above core. h. At this point, the requirements have been met for the RDS; ie, steam drum lov level (-20") for two minutes, fire ru.in pressure ,,,95 available > 100 lb, and reactor water ,'b level lov 2'9" above core, and it vill eq.f n,; .t s., j / a initiate automatically to depressurice the "' <, ;. r ~ reactor as follows: ,,.s j r :~ L w.- (1) Channels A, D, C and D Trip ( Annunciater) (2) Channels 1.1, 2.1, 3.1 and 4.1 Output Trip (fanunciator) (3) Channels 1.2, 2.2, 3.2 and 4.2 Output Trip (imnunciator) (h) Channels 1, 2, 3 and b Isolation and Depre suriantion Valves Cpen Cinul-taneousl'y (f.nnuncia* or) D,, 2031 109 O& W .;,n

Loss of Reactor Coolant - EMP 3.3, acy. 8 p' 4/4l79 f /

i. RDS discharge pipe temperature high alarm vill come in at 187.6 + 13 F.

J. Enclosure high-pressure scran occurs at 1 5 psic and post-incident ti=er starts at 2. 2 psig. l k. Core spray valves vill open when reactor pressure is 200 peig or less and water level is 2'9" above the core, admitting fire water when primary systen pressure !s less than fire system pressure. l 1. Primary enclosure sprays vill co=e on after . i.$ A. ') +,.'

  • timer runs out.

(Approxicately 15 minutes.) g: s , f } %f m. The turbine generator vill trip en the first

c.,.<.c f,i-

?. a > a/

6.. -

scran. iT + p.y...,', :j,.c[ c. . n. Ventilation valves vill closes on the first w ;A scram. v ~ o. Isolation valves vill close on enclosure high presi tre or low reactor water level. EMP 3.3.2.3 Inmediate Operator Action a. Scram the reactor nanually if necessary. b. Initiate the RDS containment evacuation siren. c. Control Roon operator vill cound the plant emergency siren and announce the imple=enta-tion of the Site Energency Plan. d. Fire fir,hting activities using fire water are to stop until long tern cooling is establisherl (a'fter step 3.3.2.h.t). At that time, fire fighting activities can resume. EMP 3.a.2.h subsequent operator Action a. Leave feedwater controls in automatic and allow the condensate and feedvater pumps which are running to continue running until they trip on hotwell low level or low suction pressure. 2031 110 g kg m kv.,2M A, k o

6 e Loss of Reactor Coolant - EMP 3.3, Rev. 8, 4/4/79 b. Check that all control rods have been fully inserted into the core and the ventilation valves have closed. Trip reactor recirculation water pu=ps, c. (or trip pumps when severe vibration due ch to eavitaticp_nec. ural, ,,, i [,]., d.') Open the etercency condenser outlet valves. .) (Emergency condenser vent alarm may be in, oV ., due to background. radiation at the two D: ' sensor locations - do not valve out the Eq (?q '. emergency condenser on the strength that \\ (this. alarm is in.), .Q. When the enclesure pressure reaches 1-1/2 e. y" c ,' psig, Control Room operater vill check that Ed C0 the automatic isolation valves elese. s (. C. (Indicating lights en left main panel.) 1 (M

c..n

'If they don't close, attempt to close them a 2 c remote.nannav- %? / -. At 20"below stea:. drum center line, eb2ck that RD3 actuation has started; ie, t00-minute time delay timer has started, fire pumps (electric and diesel) have started. NOTE: If fire pumps have not started autc=atically, attempt to start either or both manually from the Ris concole. If unsuccessful, open I'0/7066 long enough to start the pump. If unsuccessful, send an operator to the screenhou'se nnd attempt } ~ to start them locally (Reference SCP26 procedures). u o [, q em D D o JL L 2031 111 o .oo

7 Loss of Reactor coolant - EMP 3.3,' Rev. 8 4/4/79 . r.< g. When low steam durm level, -20" below center line, two-minute t ime delay timer has timed - out, fire maf: pressure available, arid lou reactor water level, 2'9" above top of active fuel, are all in coincidence, check that RDS has actuated automatically. If it hasn't, manually place it in service usirg the manual trip switches on the RDS console. NOTE: The RDS may be initiated prior to this point, if dee=ed necessary, by use of the manual trip switches on ak .f.q the RDS console. h. As reactor pressure decays to approxicatcly ~ f3 200 psig as indicated on PI/IA05, verify: vs s. e,' MO-7070, MO-7071,. MO-7051, MO-7061 open. gk..s 3-1. As the post-incident timer timqs out, the ~ C ntrol Room operator shall check 'the 9 ~ CD enclosure spray valve FO-7064 is ontr. g.y NOTE; The breaker for 20-7068 Is locked ybf. open. M0-7068 is not to be opened 4 1 (H 3 since it could decrease core spray (( f nozz?.c flow below acceptable limiti. h.," #

j. As the watcr level in the sphere rea:hes "1

qi 587 clevation (LI/3400 and/ot thrce uhite lights en console), cl.es s MO-7064. NOTE:. Uater level must not exceed 590' elevation to protect the core spray " ^ " 's sensors ard control circuits. This ,-. e, ~ .s is accomplished in step "o". l I i p F /

8 Loss of Reactor Coolant - DIP 3.3, Rev. 8 4/4/79 .J k. Check EDS reactor water level indicators. If at least three (3) are below centerline, close M0/7051 and M0/7061. 1 Open M0/7066 to supply fire water to the core spray heat exchanger. Insure that the position indication for the valve shows open. Also, a small change in core spray flow should be seen on FR-2108 as a result jbg of opening M0/7066 which assures fire water L flow to the heat exchanger. (Do not close (. ) M0/7066 until LOCA is complete as you risk j SaE not being able to reopen the valve.) 'A 9' m. %,7 Chech M0/7072 closed and pull the RMC to the / ~, g pull-to-stop position and caution tag. (For $(-av long-tera cooling and the normal source of 44; y z, water for the PIS has been verified.) e Gf n. Start one core spray pump. The " Core Spray C2 !. c 4 Low Discharge Pressure" alarm will sound if f J {j' the pump fails. (Do not run two pumps in f;/'[ parallel.) f Close the 6" and 4" fire water supply valves o. in the nachine shop (FP29 and FP30). Dr r- ]D 6" 1 ~ 6"I' 0 n ib M.Ju di 2031 113 9:

~ 9 i

  • Loss of Reactor Coolant - EMP 3.3 -

Rev. B '. 4/4/79 f ? p. If both the ring spray and no lc spray are still operating, close M0/7070 and M0/7071. Monitor RDS reactor water level indicators closely. If a decreasing level is indicated by at least three of the four indicators, open M0/7070 and M0/7071 and close M0/7051 and M0/7061. NOTE: These levels c4ust be monitored close-ly.to prevent uncovering of the core if the wrong spray line has been isolated. q. Use enclosure spray M0/7064 intermittently g to control the sphere pressure to belou ap-p -= (S proximately 1-1/4 psi. (Approximate reset 4 (p pressure on " Post-Incident Spray Timer Start" (y alarm.) am One core spray pump shall be operated contin-(., r. A7 uously until such time as it is determined 3-that the core sprays are no longer necessary. -w [4a s. In the event that a fire system break or de-NG ficiency occurs during the long-term cooling cru c3 segment of the incident that jeopardices the .) j(,] (, ;a cooling water to the core spray heat ex- ,,7e> changer, a fire hose is stored in the screen-E7 hose and can be used to tie the hose manifold c': Ra/ on the west wall of the screenhouse to the shell side of the core spray heat exchanger. Instructions: 1. Establish dose rates in the areas of the screenhouse, the north side of the sphere and the core spray heat exchanger rcom und plan workman's time alloued in the 2031 114 a reas. y, 2. Connect fire hose between the hose cani-a fold at screenhouse and Valve PI-10 in Wd es dJ . \\. core spray heat exchanger room. 3. Open the raani fold valve and PL-10.

~ 10 i Loss of Reactor Coolant - EMP 3.3 - Rev. 8 4/4/79 4. Close M0/7066 and/or :-:0/7066 bypass manual valve. 5. It freezing weather, do not isolate this flow until LOCA is complete. I* n ': [. ' e, @/M. 6, p ' L d Y /] - s;a a'.) N(u[w.\\ Up.,7 4 4

- a

'A y Q 2031 115 O y go w gg a _ ew-wMeae

11 f Loss of Reactor Coolant - E:1P 3.3 - Rev. 8 4/4/79 v E!? 3.3.3 PAJOR LOSS OF REACTOR COOLANT, OUTSIDE CC:!TAII MENT This condition vould be defined as a major break in the rain steam piping outside the containment building. It could be in the steam line to the turbine or the bypass valve piping to the condenser. Because this type of break will cause severe blovdown of the pricary systen mad possibly uninhabit-able conditions in the Control Roo=, it cust be dealt with as quickly as possible. E!T 3.3.3.1 ~ 'Sv=ptons Extre=e level of noise from escaping stean. a. b. Rapid decrease in stea= drum water level. Decrease in reactor and steam drun pressures. c. d. Decrease in turbine load. &["' Zero pressure on turbine inlet pressure cauge. e. g( f. Increase in feed-water flow. %s[ f y) g. Pipe tunnel leak nlarm. 'c' y g,,9 h. Increase in pipe tunnel humidity reading on TR-9623. 't .u:., 1. Turbine Rocn CAM high. av 4 <> ,j. Area nenitor alarts. cr 'f EMP 3.3.3.2 Automatic Actions C.7ni C('.2 The automatic actions will be similar to the i -s. symptoms. fr J E a. Decrease in turbine load.

s. ::

i* b. Increase in feed-water flow. %if* c. Containment evacuation alarm and annuncia-tion on RD3 console if steam drun Vater level drops to h" below center line. d. Possible reactor scram frca lov stean drum water level (-8" below center line). Damper CV/h190 vill close, preventing a back-c. feed into the ventilation duct ecming frem clean areas of the plant. 203! 116 D em e w ,S. = oc e

j 12 I Loss of Reactor Coolant - E::P 3.3 - Rev. 8, 4/4/79 l l EMP 3.3.3.3 Immediate caerator Actions r - f a. Close main steam isolation valve. This vill also cause a reactor scran and a turbine trip (after approximataly 25 seconds). b. If possible, regulate feed-water flow to insure adequate vator level in pri=ary syste=. c. Initiate Site Ener5ency, conditica yellow. d. Evacuate turbine building. e. Insure the da=per CV/h190 has closed by checking indication lights in the cable penetration roo= (or the plant equip =ent 4( 'd room). If it isn't closed, close it with N* , $g' HS-7090 in the cable penetration room. {U p EMP 3.3.3.h subsecuent operator Actions n. Insure reactor is shut down. P.S$ b. Insure that there is adequate water in .) y:.1, reactor vessel and steam drun. a 4.cq c. If possible, naintain one or more reactor TI[ recire pumps for circulation. c s' c.'; d. If pessible, recove Control Room air -r /[ condi'tioning unit from service (Panel 1D). C '. ~ (." Contact Radiation Protection for assessment c. c,i l of an ai* borne radiation condition in rCyE Control Ecom and possible curveys outside the plant as prescribed in the Site Energency Plan. (Since it is possible that airberne radiation vill be high in the Control Room, come form of respiratory protection should be available as quickly as possible.) The Scott Air Packs shoald be used by two persons (a tank in cood for 25 minutes), who vould have to remain in the Control Room and full face masks with canisters for others. Entry into the Turbine Roon should only be in extreme emerconey; ie, injury, until it is pernitte1 by Radiation Protec-p**D

  • O "2"A{

tion. ~ 2031 117 =

t .:. 13 Loss of Reactor Coolant - E:'? 3.3 gey, g i i 4/4/.79 j g, f. When entry to the turbine area is permitted and turbine has stopped turning, place turbine on turning gear. 6 Place generator hydrogen syste:2 in stand-t- still condition. h. When possible, reestablish the building security syste:s integrity at the pipe tunnel blevout canel. EMP 3.3.4 LOSS OF C00 LICIT ACCID 2?IT IU C0:iJEICTIOII UITH LOSS OF OFF-SITE POTER In the event of a loss-of-coolant accident at the same time as a loss of off-site power supply, the MCC 23 bus vill be energized by the diesel generator. E!? 3.3.4.1 open Breaker 52-1A feeding power to the MCC A /'t 1A bus. A *\\ T ,'/je EMP 3.3.4.2 Open Breaker 52-2A feeding pouer to the MCC $n (v# 2A bus. 7 Ele 3. 3. h. 3 Open all breakers on MCC 1A bus. j.D EMP 3.3.h.h Open all breakers on MCC 2A bus. ^ ,, a [%.y) l'3 EMP 3.3.h.5 Close bus tie Breakers 1A-23 and 2A-23. uu ( -* E!e 3.3.h.6 Close following breakers on MCC 1A bus: c: :. i.., .." f 52-1A-64 (UPS Power Supply "A"). a. ~ ;a j b. 52-1A-13 (UPS Pouer Supply "B"). EMP 3.3.h.7 Close following breakers on MCC 2A bus: )- 2 52-2A-54 (MO/7066). ,. 4 a. b. 52-2A:65 (UPS Power Supply "C").

c.. 52-2A-16 (UPS Pover Supply "D")

,EM? 3.3.h. 8. ', For 'long-tern ecoling (acar.. sing LOCA coincident with loss of off-site p-ser): Refer to Section OUP 2.14, Loss of EnerNNh ' a. Diesel Generator, for instructions in setting up the standby diesel Cencrator. b. Close Breaker 52-2A-32, Station Battery Charger. Close Breaker 52-1A-bh (or 52-2A !.3), c. Core Spray Pump. }}}} }}@

Revision to tables submitted by letter from D A Bixel to D L Ziemann dated January 19, 1979. The attacht tabulation of diesel generator loads corrects and supercedes in total the tabulation submitted by Consumers Power Company letter dated January 19, 1979. Q' Q m3m o29J)XL 2031 i19 miO879-0450c-42 Enclosure (3)

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IsW lfCC - 2B Equipment Function

  1. 88

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  1. 88 IIP KVA AMPS Irp gyA gyp 3 LT-3 emergency lighting transformer 12; b b

ils P-6. 108( } 1) 108(2) electric fire pump 100 130 100 130 Y63 o h?'e) O 25's) W w&r 9 s C Ls' W 2

9 7 A ) C 8 3 O ( 2 . L S j P 3 8 h M 1 1 / Dl t A v i e W R re M w ) o 2 P ( A 1 e V l. 1 t K 1 is f f O fo ss P I o I L ACO L SP 4 6 1 o M N A 1 7 2 r ) e ) ) ) 2 w 5 2 ( o ( [ ( ( ) P A 5 V 2 8 8 3 1 5 7( e K t 1 0 0 2 6 1 3 is f Q) fO f ) 3 5 ) 1 s P 7 1 ( ( 5 I s 0 5 1 I L m m h se se r et et o i s i s s Y9M0??' 6. M' Wb 9l ) l y l y s e e ps ps e p p r ug ug p G sn sn m i i o rz rz c ei ei wr wr r ou ou i ps ps a s s ee ee o l r l r t bp b p i e ie r td td e p p t r ur a ano ro w n rt rt o ec ec g i t a t a n t ne ne i c i r i r l n o A u no no o3 1 F ut ut c CC i ) M p c e m i t b v a I r W e p k e S m c l M i lu t p n e I t Na6~ - NN n m o s s e a i u l ep 7 S t o l mm p I a e ou T I i l A B t W DP L u a s l q n S S b l ) ) ) E a P P u e a b c C U U S ( ( ( ,ie

h C' MCC - 2A 9 i r 7 I Equi; cent Function ~ IIP KVA AMPS IfP KVA AMPS

  1. 3 Air Compressor instrument air & service air 20(1) 22.1 (2) 4 27 UPS C un-interruptible power supplies for reactor depressurizing system O.8 (5) 1.1 (2 )

1 3(8) UFS D un-interruptible power supplies for reactor depressurizing system 0.8 (5) 1.1 (2 ) 1 3(8) Station Battery Charter Trans former maintain station battery 6.25( } 6.25( } AC Bearing and Seal Oil Pump for turbi_ne 20 22.4 27 i furning Gear for turbine 7 5( 91 H 40-7066 fire water to core spray system 0 33 0.8 -1 0.33 I) 0.8(2) ,1 dA or P2B core spray pump-50 51: 65 50 51 / 2 ) 65 Yn L_D N U O M Nu M b b I i Bev/8-23-79 i i

I D' laCC - 2A t Equipment Function L ss of Offsite Power - ITo IOCA Loss of Offsite Power With ID(A, _ IIP KVA N4PS 1[P KVA maps I80 V distribution panel in Panel 2P 4 reactor building (a) Clean Sump 6(1) 7,8(2) 3 (b) Dirty Sump 6(1 7,8(2) 9,26 (c) Poison Tank IIea te rs Trans former 5 (d ) I.T le lighting transformer 22.5( (e ) I.T-5 lighting transformer 10( 'E!59 EE59 C==a Lcra) C :=2 m F=3 b 5

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