ML20206G402
| ML20206G402 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 06/19/1986 |
| From: | Grimsley D NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Weiss E HARMON & WEISS |
| Shared Package | |
| ML20205E869 | List: |
| References | |
| FOIA-86-293 NUDOCS 8606250250 | |
| Download: ML20206G402 (3) | |
Text
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PDVW6 p reg UNITED STATES o
NUCLEAR REGULATORY COMMISSION
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o W ASHINGTON, D. C. 20555 5
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JUN 19 1986 Ellyn R. Weiss, Esquire Harmon and Weiss 2001 S Street, NW, Suite 430 IN RESPONSE REFER Washington, DC 20009-1125 TO FOIA-86-293
Dear Ms. Weiss:
I This is in regard to your request, pursuant to the Freedom of information Act, to which the NRC assigned the above number.
(
_X__
This is a partial response to your request.
We will notify you upon completion of search for and review of any additional records subject to your request.
The staff has completed the search for and review of records subject to your request, and this is the final response to your request.
The NRC has no records subject to your request.
X Records subject to your request are available for public inspection and copying at the NRC Public Document Room (PDR), 1717 H Street, NW, Washington, DC 20555, as noted on the enclosure (s).
The PDR accession number is identified beside each record description.
_X__
Records subject to your request are being made available for public inspection and copying at the NRC Public Document Room (PDR), 1717 H Street, NW, Washington, DC 20555, in the PDR file folder under the above number and your name.
These records are listed on the en~losure(s).
c i
l We are enclosing a notice that provides information about l
charges and procedures for obtaining records from the PDR.
Sincerely, M
M 7
Donnie H. Grimsley, Director Division of Rules and Records Office of Administration Enclosure (s):
As stated l
l 860625025o 860619 PDR FOIA WEISS86-293 PDR
Re: 86-293 Appendix B 1.
02/14/86 Letter to P.B. Fiedler from Richard W. Starostecki re:
Inspection Report No. 50-219/85-39 (2 pages) Accession No. 8602240614 2.
03/26/86 PN0-I-86-24 re: Contamination of Workers at TMI-1 (2 pages) Accession No. 8603280217 3.
04/15/86 Notice of Licensee Meeting (1 page) Accession No'.
8604250056 4.
04/23/86 Memo to Harry Kister from Allen R. Blough re: TMI-1 Status Report for the period April 11-18,1986(6pages)
Accession No. 8605020196 5.
04/25/86 Letter to Dr. Thomas E. Murley from H.D. Hukill re:
Meeting between GPU and NRC on April 18, 1986 at TMI (16 pages) Accession No. 8605200097 6.
04/29/86 Memorandum for Harry Kister from Allen R. Blough re:
TMI-1 Status Report for the period 04/18-25, 1986 (6 pages)
Accession No. 8605070388 i
Re: F01A-86-293 Appendix C 1.
Undated Handwritten list entitled, "Limitorque Valve Operator Inspection Utilizing the New Movats System (1 page) 2.
Undated H:ndwritten note to George (1 page) 3.
Undated Chart - Plant Modifications (1 page) 4.
Undated EFW System (26 pages) 5.
10/28/85 Memorandum for Richard W. Starosteckifrom James G. Partlow re: Peformance Appraisal Team (PAT) Inspections of TMI-1 Following Restart (2 pages) 6.
02/07/86 Inspection Plan for TMI-1 (4 pages) 7.
02/11/86 Memorandum for Richard W. Starostecki from James G. Partlow re: Safety Sytem Functional Inspection by IE Personnel at Three Mile Island, Unit One (3 pages) 8.
02/20/86 Attendance List for PAT Prebriefing IR-86-03 (1 page)
)
9.
02/28/86 Memorandum for Allen R. Blough from Leonard J. Callan re:
Safety System Functional Inspection by IE Personnel at Three Mile Island, Unit One (1 page)
- 10. 03/27/86 Attendance List for NRC PAT I Exit (2 pages)
- 11. 04/07/86 TMI-1 Persons Contacted (2 pages)
- 13. 04/21/86 Handwritten page re:
EQ of Terminal Blocks (1 page)
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g&# ##G APR 18 RECT
[+f UNITED STATES g
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g NUCLEAR REGULATORY COMMISSION S
' 7;. *
- j REGION I S4, ' b' [4 631 PARK AVENUE KING OF PRUSSIA. PENNSYLVANIA 19406 Docket No. 50-289 GPU Nuclear Corporation ATTN:
Mr. H. D. Hukill Director, TMI-l P. O. Bux 480 Middletown, Pennsylvania 17057 Gentlemen:
Subject:
TMI-1 Equipment Qualification Meeting
'nis ietter is to confirn tee clanned meeting to be held at 10:00 a.m. on April 4
18, 19S6, at Three Mile Island, Middletown, Pennsylvania.
The purpose of the meeting is to discuss the overall equipment qualification program approaches at the Three Mile Island, Unit No. 1 (TMI-1) and Oyster Creek. facilities, and, specifically, the recent Performance Appraisal Team unqualified cable finding at TMI-1.
You should be prepared to discuss the following iters:
Discuss the methods used to establish tr.e tcster lists for Three Mile
+
Island I and Dyster Cred, list the similarities and differences.
l Identify from records, to include central and site procurement files, all l
cable types recuiring qualification.
Verify and discuss wnat methods were used to establish qualification (test / analysis).
I Discuss what as-built inspections have been performed at TMI-l to verify e
the sampling process.
Discuss what other cor.nodities or equipment the nonrepresentative sampling 1
techniques were used for in cetermining the master list.
Discuss the scope of the current inspection and document review perforn'ed by your contractor and the results.
If you have any further questions concerning this matter, contact R. Blough (215-337-5051) or J. Durr (215-337-5282).
Your cooperation with us in this matter is appreciated.
Sincerely, l v (f r LuN'"
\\p h
' p, Stewart D. Ebn'4ter, Director Division of Reactor Safety 1
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1- ..c SECTION I-l REVISION 1 r A0 CR0 SRO STA g D D D
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SECTION I-l REVISION 1 III. INTRULAJCTION The emergency feedwater system consists of two motor-driven pumps powered from redundant Class 1E 4160-V buses ano one I 100-percent-capacity turbine-driven ptmp which receives steam from the main steam lines or the auxiliary steam line. Both of the motor-driven pumps ano the turbine driven emergency feedwater pu m s will automatically start on loss of both main feedwater pumps or. loss of all four reactor coolant pug s. The motor driven emergency feedwater pumps are automatically loaded on the diesel generator during loss of offsite power with or without simultaneous existence of an ESAS actuation. The three peps are located in the Intermediate Building. The turbine-driven pump is physically separated from the motor-driven units. The emergency feedwater pumps take a suction, through separate lines, from the two concensate storage tanks. The condenser hotwell can also
- p be used as a suction to the emergency feedwater peps. If the condensdr hotwell decreases, the million gallon tank can be lined up to the hotwell. Ifallthewateronsiteisusedup,riverwatercanbeusedf via the Reactor building emergency cooling water pumps. Lach of the concensate storage tanks has a level indication and two level alarms.
One alarm is at the technical specification limit for emergency feeowater which is set at 11.5 feet (150,000 gallons) and the other is set at approximately 5 feet to alert the operator that there is 20 minutes of pumpable water lef t in the condensate storage tanks at the 1 emergency feedwater design flow rate. E.ach emergency feedwater pump is protected by recirculation lines back to the "b" condensate storage tank. O~ The three emergency feedwater pumps discharge into a common header from which separate 6-in. lines deliver water to each steam generator. Each of the 6-in, supply lines contain a flow-limiting venturi and an air-operated control valve controlled by ICS. The ICS controls emergency feeowater flow after the emergency feedwater pumps have been started. IV. SYSTEM FUNCTIONS The emergency feedwater system delivers water to the steam generators during loss of both main feedwater pumps or loss of four reactor coolant pumps for the purpose of (1) removing decay heat and (2) providing a smooth reactor coolant tranrition from reactor coolant pump operation into natural circulation. The cavitating venturis installea in each emergency feedwater line to r each OTSG perform the following functions: 1. Limit the emergency feeowater flow to a ruptured OTSG in order to ensure sufficient emergency feedwater flow to the intact OTSG. i 2. Limit the mass ano energy release within the Reactor Bulloiny for overpressure prevention. 0559K tm
O SECTION I-1 REVISIGN 1 g 3. Limit the flow to the OTSG in order to reduce excessive Reactor Coolant System overcooling. V. SYSTEM UESCRIPTION A. Mooes of Operation 1. Normal The Emergency Feedwater System is a stand-by system which is not used during normal plant start-ups, shutdowns or operation. The system is maintained in stand-by during plant operations and is automatically actuated upon loss of both main feedwater pumps or loss of all four RC pumps. 2. Emergency p In the event, that both main feeowater pumps trip or all foud reactor coolant pumps trip, the emergency feed pumps will g automatically start. h = i The actuation time for the emergency feedwater pumps is indicated on the attacheo Table 1. Test data inoicates tnat 4 the turbine driven emergency feedwater pump requires 18 seconds tu reach full flow. the motor driven pumps shall be ( capable of accelerating to full speed in less than 10 seconos. Therefore, unoer the worst case conoition, emergency feedwater shoulo be established within 40 seconds. There are four sources of water to the emergency feeo purros. The normal source is supplieo from the condensate storage - 2 tanks which each holo a minimum of 150,000 gallons. The l maximum capacity of the condensate storage tanks is 265,000 gallons each. The alternate sources of water, listeo in their order of usage, are: 1. Condenser Hotwell (approximately 165,000 gallon capacity) 2. Million gallon tank via condenser hotwell 3. River water via the Reactor Building Emergency Cooling System Suction is shifted to the condenser hotwell when the condensate storage tanks level reaches 1 foot. When condenser hotwell level reaches 5 feet, suction is shifted to the million gallon demineralized water storage tank via the condenser hotwell. River water is not used unless it is absolutely necessary. The emergency feeo pumps then discharge into the respective OTSG via separate lines. Flow through the lines are controlled by the EF-V-30A ano EF-V-300 valves. The EF-V-304 and EF-V-306 valves are normally controlleo automatically by 0559K tm
SECTION I-l REVISION 1 the Integrated Control System. Emergency feedwater control valves, EF-V-30A and EF-V308, can also be controlled from the remote shutdown panels, which are located outside the control room, if the Control Room has to be evacuated. 1 Upon loss of both main feedwater punps, level will be automatically controlled at 30" on the OTSG start-up level indication. On a loss of all four reactor coolant punos, the level will be automatically controlled at 50h on the OTSG i operating level. 1 Before the emergency feedwater enters the OTSG it must pass through the cavitating venturis. Their functions are listed in Section IV of this document. l The emergency feedwater enters the OTSG through the emergency j feed ring which is located high in the OTSG. The emergency 1p feed ring has seven feed nozzles, but one of the nozzles is t blocked to prevent thermal damage to the OTSG lower ,{ tubesheet. The blocked nozzle directed emergency feea into [ the OTSG inspection lane which provioeo a direct path to the - bottom tubesheet. 1. The high location of the feed ring provides a higher thermal center in the OTSG which aids in establishing natural circulation flow. .C The feed nozzles each contain a thermal sleeve to minimize the thermal shock to the nozzles when cold emergency feedwater is injecteo into the OTSL. b. Components 1. Turbine (See figure 6) Emergency Feedwater pump (EF-P1) is turbine driven by a i Worthington Model T2RA, single stage, 2 wheel, horizontal split case turbine requiring 200 psig saturated stream at 29.5 los/hp hr with a 1 psig exhaust. The turbine is rated at 835 horsepower (H.P.) at 3800 revolutions per minute (RPM) with a critical speed of 7050 RPM and is suited for quick starts. The turbine casing, steam chest, inlet and exhaust flanges are cast carbon steel while most of the other major components are i stainless steel. Gland steam leakoff is directed to a common opening and sent to orains in the Intermediate Building. The turoine has two relief valves to protect against overpressurization. The reliefs are set at 200 psig and 220 psig. The turoine overspeeo trip is 4590 rpm. l l 0559K tm
SECTION I-1 REVISION 1 The turbine exhausts its steam to atmosphere. The turbine's two relief valves and the exhausted steam are directed outside the intermediate building near t,he. industrial cooling units. 2. Punos There are three EFW pumps including the turbine driven p mp and two motor driven pumps. The turbine driven pep (EF-P1) is a Worthington moael 4WTF-125, five stage, horizontal split case, ciffuser centrifugal pump with the following design data: Capacity (GPM).............. 920 Minimum flow (GPM)............ 174 Total dynamic head (ft.)......... 2700 Speed (RR4) 3800 Temperature Range (oF).......... 40 - 110 g .f Specific Gravity............. 1.0 NPSh requireo (ft.)........... 16.5 g-BHP required............... 835 Efficiency (x).............. 75 Critical Speed (RPM)........... 7050 Suction flange (inches) 6 (600# ASA) Discharge flange (inches) . 4 (1500# ASA) '{- The turbine driven pmp is located in the Intermediate building in a separate compartment on the 295' floor elevation. The turbine driven p mp is physically separated from the two motor driven units. The pump uses a minimum flow by-pass orifice with a locked open bypass valve. Tnis recirculation line joins those from the two motor driven feedwater pmps ano is directed to condensate storage tank B. Power to the turbine driven pump is from the safety related portion of the main steam system or the auxiliary steam system. The two motor driven. emergency feedwater pumps are Worthington Model 2-1/2 WTF-108, eight (8) stage, horizontal split case, ciffuser centrifugal pumps. Each of these pumps have minimum flow by-pass orifices and the following design data: l Capacity (GPM)..............460 Minimum flow (GPM)............ 84 Total Dynamic Head (ft.)......... 2700 Speed (RPM) 3570 Temperature Range (oF).......... 40 - 110 dpecific Gravity............. 1.0 NPSh requireo (ft.) 16.0 biF required............... 450 Efficiency (%).............. 69.5 l Critical Speed (RPM)............ 7050 i Suction Flange (inches) 4 Discharge Flange (inches) . 2.5 ........ 0559K tm
SECTION I-l REVISION 1 The motor driven feedpunps (2A and 26) are located in the Intermediate Building east of the turbine driven pump in a separate conpartment on the 295' floor elevation. The emergency fesopump turoine ano punp bearings, together with the emergency feedpump Dearings of pumps 2A and 2o are provioeo with a cooling systern of recirculated feeowater from the pump discharge to the pump suction. Tne EFW punp motors are Westinghouse type CSP, horizcntal, squirrel cage, induction, drip proof with split sleeve bearings with the following characteristics: 450 H.P., 3600 R.P.M., 4000 volt, 3 phase, 60 cycle. These punps have space heaters proviaeo in the motors to eliminate condensation. The power supplies to the motor driven emergency feeowater pumps are: e EF-P-2A - 10 4160V ES Bus i e( EF-P-2B - 1E 4160V ES Bus k 3. Valves a. Valve Operators O The motor operated valves all have a Philadelphia Gear V Corporation limit torque operator utilizing 480V, 3 Phase, 60 cycle motors, except MS-V-10A/B which utilize a 240 V DC motor. All motors are totally enclosea with a space heater to avoid condensation. ~~ Valve operators have an auxiliary manual hana wheel clutch gear train, independent of tne motor gear train which is capable of closing the valve against one ano one-half the maximum design hydrostatic testing pressure. These operators are also equipped with an AWWA nut arrangement for air-wrench operation. Each valve has valve position indicators and a pair of electrically inoependent torque switches with a single contact to open on excessive torque during opening and a single contact to open on excessive torque during closing. b. Valve Control All three EFW punps discharge into a common header. Off of this conynon header, a separate six inch line delivers water to eacn steam generator. Each of the two supply lines contains an air operatea control valve (EF-V30 A/B). under normal operations, air for the control of these valves is supplied from the instrument air system. In 0559K tm
SECTION I-l REVISION 1 ( the event that off site power is available, air can also be supplied from the station service air compressors, SA-P-1A/B, through valve IA-V-1. Valve IA-V-1 is set to open at 75 psig to 80 psig. In the event the main sources of instrunent air are not available, a back up source of instrunent air has been providea. Transfer to the back up air supply is automatic and no operator action is required. In addition, a two hour' ackup air b supply is installed for main steam and emergency feedwater system controls to provioe the motive force air for valves MS-V-4A/B, MS-V-6, EF-V-30A/B should the normal plant instrument air compressors ano the backup instrument air compressors be lost. Transfer to the two hour backup air supply is also automatic ano no operator action is required. c. Failure Modes lf The emergency feedwater control valves EF-V-30A/B will {. fail open on loss of instrument air or control power and?. half open on loss of control signal from ICS. c. Valve. operation of EF-V-30A and EF-V-30B EF-V-30A and EF-V-30B are located in the motor driven emergency feed pump room. There are five modes of control on EF-V-30A and EF-V-308. These modes are: 1. Normally the valves are controlled automatically by the Integrated Control System (ICS). l 2. The valves can be controlled via the ICS by using the EF-V-30A and EF-V-30ts Hand / Auto station. The station must be placed in the Hand position ano valve position is controlled by the toggle switch on the Hand / Auto station for EF-V-30A or EF-V-308. 3. There is a backup manual loader for the valves in the control room. To use this loader, the respective control switch (console left for EF-V-30A ano Console center for EF-V-3Ob) must be placed in the " backup" position. Valve position is then controlled from the backup manual loacer. 4. The valves may be controlled from the Remote Shutoown panels which are locateo on the secono floor of the control tower. To establish ~ control at the remote shutdown panels there are panal switches which must be operateo. These panel switches are located as follows: 0559K tm I m -,, -.. _., -,.,.. - _ _ _. _ _. _. _ _. _ - _ _ _ _ _ _, _ _ _,... -, -
SECTION I-l RE.V1SION 1 EF-V-30A - 3rd floor of the control tower in the ESAh relay room near the east wall. EF-V-308 - 2nd floor of the controf tower in the remote shutdown panel room on the west wall. The panel switches are placed in the " emergency" position which establishes EF-V-30A ano EF-V-300 control at their respective remote shutdown panel. Valve position is then controlled by the controllers which are located as follows: EF-V-30A A Remote Shutoown panel EF-V-308 B Remote Shutdown panel 5. Valves may be positioned locally with a handwheel. The valves are shifted to local control as followst a. Auto to Manual i;- T f 1. Turn handwheel to align holes 2. Insert pin ) 3. Position auto / manual switch on the control box to the manual position i 4. Cpen equalizing valve which is locatea on f: the outside of the diaphragm 5. Position valve with handwheel b. Manual to Auto 1. Shut equalizing valve ~~ 2. Position auto / manual switch to auto 3. Remove pin from hole 4. Position pointer, located on the valve stem, to the neutral position with the handwheel 6. Operation of EFW-V-30A/B Backup Air System (See Fig. 10) Under normal conditions, the instrument air supply passes thru IA-V-1434 from port "D" to port "A", and "C" port is blocked. If normal instrument air pressure drops to 60 psig or below, IA-V-1434 changes its lineup to pass air from port "C" to port "A" and blocks port "D". Emergency backup air is available at port "C". This air can be either backup air compressor air or 2 hour bottle farm air. These two emergency backup air supplies are auctioneered by check valves IA-V-1658 and I A-V-1656. The backup air will first be supplied by i 0559K tm
SECTION I-1 REVIS10N 1 ( the backup compressor, if operable, because of its higher pressure. If the backup compreswr supply 'l fails, or is faileo already, air will be suppliec by the 2 hour bottle farm supply. Wnen the air from the 2 hour bottle farm drops to 60 psig or below, l IA-V-1436 will change its porting arrangement to i port "C" to port "A" instead of port "U" to j port "A". This action vents the air supply line to the valve actuator, allowing the trip valve "V" to toggle, porting air from a storage tank directly to the bottom of the piston actuator, holding the valve in its open position, but will not allow any control action. e. Valve operation of MS-V-6 NS-V-6 is set to moculate to maintain 175 psig steam l f pressure, via pressure controller PC-5, to the steam i driven emergency feedwater pump. MS-V-6 is mechanically ' g' yagged to prevent the valve from opening more than 65% f. ?. open. This is done to limit the steam pressure to the steam lines and steam turoine chest to prevent exceeding the pressure limits of the piping and steam turbine. In accition, two safety valves, MS-V-22A/B, are provideo to prevent overpressurization. (. MS-V-6 is located in the steam driven emergency feed water pump room. f. Valve operation of MS-V-13A and MS-V-138 MS-V-13A and MS-V-13B are located in the steam driven . _ ~ emergency feed water pump room. MS-V-13A will open on an "A" emergency feedwater actuation signal to admit steam to the steam driven emergency feedwater pump turbine. Likewise, MS-V-13B will open on a "B" emergency feedwater actuation signal-to admit steam to the steam driven emergency feedwa'ter pump turbine. Both valves will fail i open on loss of instrument air. g. Valve Operation of MS-V-10A and MS-V-10B MS-V-10A anc MS-V-108 are locateo in the steam driven emergency feedwater pump room. These valves are bypasses arouno MS-V-13A anc MS-V-138. They are used to supply steam to the steam driven emergency feedwater pump turoine when steam pressure gets too low to adequately supply the steam turbine through MS-V-134 anc MS-y-13td alone. MS-V-104 and MS-V-10B are jog controlled valves which are operated from the control room on console center. Both valves are DC motor operated valves. l 0559K tm
SECTION I-l REylSION 1 h. Valve (peration of EF-V-8A, EF-V-88, ano EF-V-8C Due to earthquake considerations EF-V-8A, EF-V-86, and l EF-V-8C are administratively failed to the ppen position l for maximum recirculation to insure flow for the protection of the EFW pumps. EF-V-8A ano EF-V-8C are located near their resoective motor driven emergency feedwater pump (EF-P-2A and LF-P-28). EF-V-8B is located near the steam driven emetgency I feedwater plap (EF-P-1). I 4. Cavitating Venturi The cavitating venturi's are locateo near the "B" motor driven emergency feedwater pump. They are in the northeast corner t f near the ceiling. Figure 3 contains an explanation on how the cavitating venturi works. P V1. INSTRlNENTATION, CONTHOLS, AND INTERLOCK 5 l \\ Emergency feedwater flow can be reao in the control room on console center and console left. The emergency feedwater pumps will automatically start on: l 1. Loss of both main feedwater pumps as sensed by <50 psid l across the pumps. 2. Loss of all reactor coolant pumps as sensed by the reactor ~' coolant pump power monitor. ' 3. Control room annunciation for all autostart conditions of the EFW system is available. Each of the. emergency feeowater supply lines is proviot.d with two i reoundant Class 1E flow indication loops. For each EFW supply line, one annubar serves as the source for two redundant oifferential pressure transmitters. The differential pressure. transmitters provide flow signals, through Class lE instrument loops, to the maln control room indicators. A simplifieo locp j oiagram for the flow indicators is shown in Figure 9. These 1 annubars are located in the motor driven emergency feedwateI'pum;> ) room. upstream of the cavitating venturis. V11. LIMITATIONS AND PRtCAUTIONS 1 4. EF-V-4 ano EF-V-5 (River Water to EFP Suction isolation Valve) will be openeo only when all other sources of water have been exhausted. _ 0559K tm I i } l
SECTION I-l REVISION 1 NOTE: Prior to opening EF-V-4 ano EF-V-5 (from CC), one of the I R.B. bnergency Cooling Pmps must be running to satisfy an interlock in the valve opening circuit. Also EF-V-4 and 5 are locked closed at valve, and breakers are locked open at 480 V. Control Center ICESV. ~' B. When returning the system to standby after maintenance or extenced snutdown, thoroughly vent each punp. C. Oil should always be visible in the glass bottle on the constant level oilers on the pumps. D. MS-V-6 is normally limited to a maximum open position of 65 percent by locking the handwheel in the "21 turns out" position. This position is verified by the cotter pin thru the stem being down against the locking nut which is down against the stem guide. This is done to prevent over-pressurization of the Emergency Feed Pump Turbine Steam Chest in the event MS-V-6 should fail open coincidertt f with MS-V-10A or B failing open. 'l [ E. To prevent water carry over into the main steam lines, trip all operating emergency feedwater pumps at an OTSG 1evel of 95 percent t in the operate range during normal or emergency operation. (This guidance does not apply when performing a floodeo nozzle heat-up or cooloown operation.) (- F. Following actuation of the EFh system, an operator must be sent to the EF-V-30's area and establish communications with the Control Room. This action is necessary to ensure proper operation of the system and enhance the response time should manual system operation be required. ~# G. The emergency feea punps will not be useo to replace a main feea pump for normal operation. H. EFW THROTTLING CRITERIA To prevent RCS overcooling oue to excessive feeo rates, manually control emergency feedwater flow as necessary to maintain OTSG pressure within 100 psig of desired pressure. Monitor RCS cold leg temperatures to i ensure feed rate is not causing a significant RCS temperature transient. Sufficient flow must be maintained to remove RCS heat ano promote circulation. In the event of depressurization of both OTSGs (due to the main steam or feedwater line breaks) with only one (1) EFW pump operating to feea both OTSGs, the EFW control valves must be throttled to prevent pump runout (i.e., EFh control valves must be throttled with one (1) pump operating to feed botn ruptured OTSGs). Anytime EFW flow is actuated and automatically increases steam generator level to 50% on the operating range, it can cause significant RCS overcooling. 0559k tm
SECTION I-1 I REVISIuh 1 In order to reduce the possibility of thermal cycling of the emergency feeonater noz.zles, positioning of the emergency feedwater control valves (EF-V-30A/B) to the fully closed position should be avoiceo during the manual control of emergency feedwater flow. Overcooling can result wnen EFW injects cold water into the OTSG at high flowrates, wheri trying to obtain the OTSG 1evel setpoint. When the level increases too rapioly the inventory acetriulation is a colder heat sink than is requireo to remove core decay heat. Steam pressure drops and the RCS i.s overcooled. During forced flow, this is quickly reflected in cold leg tenperature and RCS pressure. During natural circulation the RCS indications are delayed several minutes due to the slower loop transport time and are therefore not suitable parameters to use for feedrate control. Steam generator pressure is the preferred parameter since it responds rapidly to EFW flow changes under forced flow and natural circulation. Use of this single parameter permits simpTITied guidelines. Addition of EFW at the maximum rate is not neeoed to achieve stacle natural circulation of the RCS. However, continuous flow is_ required to lf the UTSG to maintain the high thermal center in the OTS6 for natural
- i circulation of the reactor coolant water.
k I because the decay heat can be different, the amount of flow needed to remove decay heat and increase level is different; therefore, no fixed flow rate can be established. However, the maximum flow rate can be gauged by its effects. Generally, the flow rate should not drop steam (,j pressure by more than about 100 psi below the pressure setpoint. For y example, after a trip the turbine bypass set pressure is 1010 psi so the EFW flow should not cause steam pressure to drop below 900 psi. If the operator has adjusted steam pressure to a different setting the steam pressure drop should stay within 100 psi of that setting. The 100 psi change in steam pressure restricts the RCS cold leg temperature reduction to about 150F. Vill. INTERFACING SYSTEMS A. Main Steam - supplies steam to the steam driven emergency feeowater pump during an Emergency Feedwater System actuation. B. Auxiliary Steam - can supply the steam driven emergency feedwater pump via AS-V-4. C. Reactor Bulloing Emergency Cooling River Water can be used to supply suction water to the emergency feedwater pump in an emergency via EF-V-4 and EF-V-5. D. Concensate - normal supply of suction water to the emergency feedwater pumps. E. Instrument Air - normal supply of air to the air operated valves in the Emergency Feeowater System. OS$9K tm i
? SECTION I-l REVISION 1 G. backup Instrument Air - if instroent air pressure drops to less I than 70 psig the nackup instrment air system will supply the following valves associated with the emergency feedwater system: MS-V main steam supply to steam driven emergency f'ee'0 water puinp EF-V-30A - emergency feedwater pmp discharge control valve to the "A" UTSG EF-V-306 - emergency feeowater pump discharge control valve to the l "B" OTSG H. 2 Hour Air Bottles - This system is a series of high pressure air bottles which are located in the "B" QLesel Generator room. If the l instr m ent air system cannot supply sufficient air pressure, the 2 hour air bottle will automatically supply the following valves associated with the emergency fee 0 water system: f EF-V-30A EF-V-308 MS-V-6 MS-V-4A { MS-V-4B IX. TECHN1 CAL SPECIFICATION A. With the Reactor Coolant System temperature greater than 25UoF, three independent EFh pumps and associated flow paths shall be OPERAoLE with: a. Two EFW pumps, each capable of being powered from an opt.RABLE emergency bus, and one EFW pump capable of being powered from an OPERABLE steam supply system. Specification 3.0.1 applies. b. With one pump or flow path
- inopeimble, restore the inoperable pump of flow path to OPERABLE status within 72 hours or be in COLD SHUTDOWN within the next 12 hours. With more than one EFW pump or flow path
- inoperable, restore the inoperable pumps or flow path
- to OPERABLE status or ce subcritical within 1 hour, in at least HOT SHUTDOWN within the next 6 hours, and in COLD SHUTDOWN within the following 6 hours.
c. Four of six turoine bypass valves are OPERABLE. d. The concensate storage tanks (CST) shall be OPERABLE with a minimum of 150,000 gallons of condensate available in each CST. With a CST inoperable, restore the CST to operaDility within 72 hours or be in at least HOT SHUTD0hh within the next i 0559K tm
SECTIOh I-l REVISION 1 6 hours, and COLD SHUTDOWh within the next 30 hours. With more than one CST inoperable, restore the inoperable CST to OPERABLE status or be subcritical within I hour, in at least HOT SHJTDOWN within the next 6 hours, and in COLD SHUTDOWN within the following 6 hours. Specification 3.0'.I applies. b. Emergency Feedwater Pumps Periodic Testing 1. Applicability Applies to the periooic testing of the turoine driven and two motor driven emergency feedwater pumps. Ob ective 2. J To verify that the emergency feeowater pumps and associated valves are operable.
- f 3.
Specification a. Whenever the Reactor Coolant System tegerature is greater than 250*F, the EFh pu@s shall be testeo in the recirculation mode in accordance with the requirements and acceptance criteria of ASMt. Section XI Article IhP-3210. The test frequency shall be at least every 31 3 days of plant operation at Reactor Coolant Temperature A above 2500F. U b. During testing of the EFW System when the reactor is in STARTUP, HOT STANDBY or POWER OPERATION, if one steam generator flow path is made inoperaole, a dedicated qualified individual who is in comunicaton with the control room shall be continuously stationed at the EFh local manual valves (See Table 4.9-1 of Tech Spec. Section 4.9). Un instruction from the Control Room Operator, the individual shall realign the valves from the test mode to their operational alignment. c. At least once per 31 days each valve listed in Table 4.9-1 shall be verifieo to be in the status specified in Table 4.9-1, when required to be operable. i d. On a quarterly basis, verify that the manual centrol (HIC-849/850) valve station functions properly. e. Un a quarterly basis, EFV-30A and 300 shall be cheCKea for proper operation by cycling each valve over its full stroke. f. Prior to start-up, following a refueling shutdown or a cold shutdown greater than 30 days, conduct a' test to demonstrate that the motor driven EFW pumps can pump water from the condensate tanks to the Steam Generators. 0559K tm l ~ - - - - - --'~-' ~~~~~~
SECTICA I-l REVISION 1 4. Acceptance Criteria These tests shall be consioered satisfactory if control boaro indication and visual observation of the equipment demonstrates that all components have operated pfoperly. t .f 4.. i.' , 05596 tm
-l .W% 2 FIGURE-1 EMERGENCY FEEDWATER X k I' = 8A f e CONDENSATE P TANK B p HOTWELL (d 4 y 2A EMERGENCY SOA ^ 18 3 @ FEEDWATER CAVITATING u PUMP 5 2A VENTURI WATER / ( river / \\ y 1Ah 2B h h h I X v BB n B h CAVITATING Ts VENTURI - HOTWELL m A CONDENSATE TANK A O O q T T h S 5 3B X k B A 8C "y. CONDENSATE STORAGE y TANK B DE-lCE LINE v v O
.pg g
O.
FIGURE-2 STE~AM FLOW TO EF-P-1 1
MAIN STE AM LINES
<s
FLOW OF REPOSITIONING AIR Z HOUR BOTTLE AIR l
J INSTRUMENT AIR BACKUP AIR h Al TO ACTUAM REPOSITION THE VALVE 2 HOUR BOTTLE AIR m
w I
s t
N EF-V-30 A/B 55 se EE
=
em.
m
- 8
..,pw.. g O ~ FIGURE-6 EF-P1 TURBINE (WORTHINGTON MODEL T2R A) hS.,) y t_f.. P ( h, 1 s s'-.., g.'e 4 \\ g2 \\ 'a iL - i., o n. ',' s, QI ' p t. g \\ l ell i [ p' / 2 1. \\ l g gl / i . _.,, w m ,m e......, .\\ "x 'N N / l S)p':] / I,,' "N %'%.. NsJ .'f\\\\ \\ s. s /l'/ i Q p~ ~*=4 ~e-@ /') W;i ?! ~ I.3 I 4
- Wp
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l .r, m s' FIGURE-7 EF-PI PUMP (WORTHINGTON TYPE 4 WT) ..s.m,,,a.,...>,... 4, ( __.(;, m' ga: a (- () ",2'i M il"J " O fl","n.... -..-,, s 1 c -a. 1 a u yD~ 9 &kbU S$ f,l h "~ N i i + q)&( .. L li, L,9 b.i ji s oW e,, y J I d' / o' =:.=:.m. ~ v I - - 1
- . O
- " = > .,p. STATIONARY PAR;3 y ROTATING PARTS i ser. NO. mar. NO. ._ I.. _ I CA53NG--UPPf 3 HALF _. -.25 STUFflNG SOX-BE h NAAGE OF PAST NO. OE h NAAAE OF PAST I e SUCT.fMD ,_i.A CA5iNG--tOwfe Half 25 A I STUPTING SOX-2 3 5 HAFT WliH REYS 54 2 SHAff NUT g,,,,,,,,,, ,_nt,,, g ' ' -3 i ~" 5A5iNG weG. eiNG,,, _ 2 7,,', "5*~ 5 fit 5G 2 3.Al 4-Dinu$en weG. e:NG 29 I DerrUsee-2ND STAGE _ _ _, 4-A 4-imPettes-5sNGac 24 I rHsust eeG. NUr Dt5 CHARGE STAGE PifCE [ [29A_ [3
- DdU5f[
99NG CONST. ONLY 5 l I 5-A_l I CA5t_NG_ STAGE Pff CE 7 l 0 STAGE SUSHING _ 29 8 _3* RETURN CHANNf t 4-3 1 IMMitEE DOUSLE 39 3* DIFfuSEE SUSHING B0NG CONST. ONLY I 8.m9 12 79 i SEAR R$NG PACKING 4-C 4 IMPEttEE-DOUStE 28 I fee 0UST 88G. 9 ~ ' Pili 09 I NAME PL ATE 99NG CONST. ONLY LOCKWASHet 33 l 2 SE AL C' AGE 5 $ _5l 2 GR AND-5Ptli 95 I THWUsi SING e l TMgg57 g,ASING 28.A 3 BACK.UP ggNG J_ I THtUST 89G., HOU58NG 309 _,_I SALANCING DISC HEAD 17 19 I THeU5T SeG. COvf e-133 2 5ess DIFFUSER SHIM 5 g INNe t ID 2 SHAff 5tftvf 74 I OIL CleCULATOs fn 89.A B THfU5T StG. COvit-13] A 5 set THOU5T BRG. 5Hims lu.- 95, s.UST i, 3, 5,.l.5 g2 I, ,,,, t t,..,G. ,,D O ,,,,G 29 9 86Hf StG. HOUSING 157 6 5PSING 91NG 23 I ttHE StG COVER G 2 STUfflNG SOE GA5Kff 32-A 4 ##1mPEL(It WAG. 372 3* SNAP BtNG GP I BAL. HE AD DISC GA5Ktf SING NOff. Oveasse.es me.6ed g*p o, so, f. e spege pw p only. for peeps heeing. noes see es. ebene steensities see increased ecceedingly. enm
g , i gp o...eg e FIGURE-8 EF-P2 A/B PUMPS (WORTHINGTON MODEL 1/2 WTF) 20 8 #St 23 72 'S 84 9 PS 80 30 38 29 29A 7 27 4 8 77 1. A S 909 IS PS-A 22 t'9 13) 6 ISE 0F !/ / )'I /
- '\\
l 7-y 's L iF'.,_,W e ~ [. \\ I 41 4, *; -,ef p' e L ,i. ~.L bM.m_h' w:Ww m I Yt . m8%# e d .s.,M.', ,n ,e '; 17 IsF w M q'\\ t< __x g=_i a 9..,pp %m '.,s. .,,:.p,=ng, ;~.. sm. wit @y. a . c. ;L ---
- e 4
Ts t. .s. .7 \\ k,f y 7 y ( gl\\ f lI rim [D89 / r. 7 h h* )r, [i7I) - [ f I .e n ~ c C ~ E_. _ '. ~ _ Q \\. i I = =. - - t. U I \\ 133 A l-8 90 110 M A 78 95 Sw 13230SA I l STATIONARY PARTS ROTATING PARTS mF. NO. MF. NO. en. NO. en. NO. NO. BEOD NAatt OF PART NO. MOD NAmeE OF PART NO. MOD NAAAE OF PART NO. MOD NAAIE OF PART 3.A I CASING, UPPER HALF 23.A I STUFF. BOR---DOSCH. END [ t SHAFT W/KETS 22 2 WATER SHIELD ~ 3.8 I CASING. LOWER HALF 27 'S ELASTIC SEAL RING 3 1 DISCHABGE STAGE PIECE 29 I Ist STAGE DIFFUSEE 7 '6 STG. BUSH. lTAPf lNSERT) 29.A 'e DIFFUSEE-MTUSN CHAN. l 32 39 'T CASING SING 9 RONGS PACRING 89 I NAMEPLATE tOCKWAS00EE 33 2 SEAL CAGE (SPlff) 93 I THOUST N 4 I tlNE SEADING 30 t DISTANCE STEEVE IS 2 GRAND (spilt) 109 I SAtANCING DISC HEAD 10 2 SHAFT SIEEVE 76 I Ott THeOWER 3 17 I THOUST BSG. HOUSING 333 3 SET THOUST BEARING SHIMS m I t I BAL N DISC 39 8 INNES THOUST SGG. COVER 3 33. A 2 STAGE PIECE SHIMS 8 9. A I OUTER THOUST StG. COVER 933.s 2 SETS THOUST LIMIT SeelMS 28 8 LINE BEADING HOUSING ISI 2 VENT h ) INSOARD 23 I tlNE MAtlNG COVER IS7 6 SP9tNG 05 9,,, ,73 g, 23 3 STUFF. BOX-SUCTION END OUTSOA90 NO. 3803 873 NOTE: Geoa8 dies merled (*) are for sevea esoge peeps oaty. For p mps lio,ia, more (or te.er) sfoges ekse quoneities are occordi=9 y lacreased (or reduced). f
- 'i.*~%
8' FIGURE-9 EMERGENCY FW FLOW INDICATION (," _ _ _ _ _ < VE/ 7--- l Si0e At C0ii0m0isiin i ELECTR0000CS l M AsususAR m to n \\mj i J L I EF + + OTSG "B" l VITAL BUS C I (VELLOM i s e wCsaseGras I I I .____________________.A,_____ I E m ,- _ _ _ _ _ _ _ _ _ _ _ _ _ _ q - m i ELECTROIIICs 6400 GPtl (TYP) ( m" ______' 7ss FE WTAL BUS S l M AIINUSAR (GREEN) m Ml LO , COIMIOL ' + OTSG "A" N0008 EF + v I l E1 jlla e, - =9 5 T
SECTION 0-1 REVISION 1 FIGURE-10 EF-V30A/8 CONTROL AIR ( l BU
- l. A.
2H R
- 1. A.
A m _.Y m f_J ~ ~ T w DIAPHRAM \\ T ATM U rJ Yl t s* NORMAL .IL 1.A. bk 2 A FAIL POSITION AIR BOTTLE O BAILY POSITIONER t ATM x\\\\\\\\\\\\N BLACK OPEN ED BOX SUPPLY x i CLOSE db E/P gg ics > - k 3 yO gA CE B 1123 EG ATOR BEAM EF-V-30A/B NO7 MAL l.A. B.U. l.A. THIS DIAGRAM SHOWS THE PHYSICAL LAYOUT OF ALL AIR LINES ON THE EF V 30A/B VALVES.. ,m-.
._---3
'-l I a SECTION I-1 REVISION 1 TABLE 1 - TIME FOR EMERGENCY.FEEDWATER PUMPS TO REACH FULL SPEED START TIME TO FULL STAR'T TIME TO FULL EVENT SIGNAL EFPI SPEED EFPI SIGNAL EFP2 SPEED EFP2 LOSS Of FW OR IMMEDIATE 18 Sec. 5 Sec. 15 Sec. LOSS OF RCP LOSS OF FW OR LOSS OF RCP IMMEDIATE 18 Sec. 15 Sec. 25 Sec. AND LOSS of UFISITE POWER LOSS Ut IN OR LOSS Of RCP IMMEDIATE 18 Sec. 20 Sec. 30 Sec. AND ESAS BUT NOT LOSS Of OffSliE POWER LOSS OF FW OR LOSS Of RCP .IDMEDIATE 18 Sec. 30 Sec. 40 Sec. AND ESAS AND LOSS OF OFFSITE POWER -f-0559K tm u .}}