ML20070P033
| ML20070P033 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/19/1983 |
| From: | Causey J GEORGIA POWER CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NED-83-055, NED-83-55, TAC-48294, TAC-54495, TAC-98294, NUDOCS 8301260006 | |
| Download: ML20070P033 (40) | |
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{{#Wiki_filter:Georg a Power Company 333 Piedmont Avenue Atlanta, Gtc*g:a 30308 Telephone +04 52C 7895 M9ng Address Post Of' ce Bor 4545 Atlanta. Georg a 30302 h Georgia Power
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J. C. Causey we Prasdent NED-83-055 Foss;I and Hydro Generat,o, January 19, 1983 Director of Nuclear Reactor Regulation Attention: Mr. John Stolz, Chief Operating Reactors Branch No. 4 Divisior. of Licensing U. S. Nuclear Regulatory Comnission Washington, D. C. 20555 NBC DOCKET 50-321 OPERATING LICENSE DPR-57 EDNIN I. HA7CH NLCLEAR PIANT UNIT 1 AMENDfENT 70 THE HPCI AND RCIC ICO CHANGE PROPOSAL Gentlemen: By letter dated April 5,1982, Georgia Power Company (GPC) subnitted a proposed change to the Edwin I. Hatch Nuclear Plant Unit 1 Technical Specifications (Appendix A to the Operating License) . This amendment was to change the requirements for the High Pressure Coolant Injection (HPCI) system and the Reactor Core Isolation Cooling (RCIC) system so as to require that both systems be operable when reactor pressure is at or above 150 psig (113 psig is the present requirement) . GPC recently identified an error in the above-referenced subnittal, in that an additional change to the Technical Specifications was proposed which i was beyond the intended scope of that revision. The erroneous change proposed that the minimum reactor pressure operability requirement for the Automatic Depressurization System (ADS) be changed from 113 psig to 150
- psig. That change had been considered for inclusion in the final subnittal by GPC; however, it was determined that insufficient analysis existed to justify that particular revision. A document control error resulted in the i
inadvertent inclusion of the changed Technical Specification page containing the ADS operability requirement in the final subnittal. 8301260006 830119 PDR ADOCK 05000 P l
Georgia Power A Director of Nuclear Reactor Regulation Attention: Mr. John Stolz, Chief Operating Reactors Branch No. 4 January 19, 1983 Page Two Therefore, GPC subnits the following amendments to our above-referenced letter dated April 5, 1982. 'Ibchnical Specification page 3.5-9 should be deleted from the proposal, as it was not GPC's intention to request a change on this page as part of that subnittal. In addition, Attachment 1 to our earlier subnittal shoulc be replaced with the Attachment 1 enclosed with this letter so as to remove all references to page 3.5-9. GPC has implemented measures to assure similar document control problems with license subnittals will not occur in the future. The NBC Project Manager for Plant Hatch recently requested additional information regarding the designed operating range (reactor pressure) for the HPCI and BCIC systems to aid his review of our April 5 subnittal. ! Therefore, GPC is enclosing a letter, dated June 25, 1980, from General Electric Company (GE) to GPC which addresses this subject. In addition, the l GE system design specifications for these two systems are enclosed. J. C. Causey states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Conpany, and that to the best of his kncwledge and belief the facts set forth in this letter are true. i GEORGIA POWER COMPANY Bs . OMdf'/4, C C. Causey
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Sworn to subscribed before me this 19,th day of January, 1983. '
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7[//Af Notary Public. Gaorga State at large
/[ f , < ) My Commission Empires Sept. 20,1983
' Notary Public CBS/mb Errlosure xc: H. C. Nix, Jr.
Senior Resident Inspector J. P. O'Reilly, (NBC-Region II) J. T. Beckham, Jr. l l l 700775
i l l l ATTACHE NT 1 NIC DOCKEP 50-321 OPERATING LICENSE DPR-57 EININ I. HATGI NCELEAR PIANT UNIT 1 ! HPCI AND HCIC ICO CHANGE PROPOSAL The proposed changes to Technical Specifications (Appendix , A to Operating License DPR-57) would be incorporated as follows: Remove Page Insert Page 3.5-6 3.5-6 3.5-7 3.5-7 ! 3.5-8 3.5-8 ! 3.5-16 3.5-16 3.5-17 3.5-17 f I i
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GENER AL $ ELECTRIC
, SERVICE ENGINEERING GENERAL ELECTRIC COMPANY, 3565 PIEDMONT ROAD, N E., P.O. BOX 4659 ATLANTA, GEORGI A 30302. Phone (404) 262-6000 g
cc,: June 25, 1980
- Georgia L. T. Gucwa Power Company ca, po,,
auctua c,,c J. R. Jordan M. Manry R. A. Baker Mr. W. A. Widner, Vice President Nuclear Operations Southern Company Services, Inc. Georgia Power Company W. F. Garner P. O. Box 4545 T. Milton Atlanta, GA 30302 ,
Subject:
HATCH I. TECHNICAL SPECIFICATIONS CHANGE FOR RCIC & HPCI OPERABILITY
Reference:
L. T. Gucwa, letter to B. M. Matthias,
Subject:
Plant Hatch Unit 1 HPCI & RCIC Operability, dated March 4,1980
Dear Mr. Widr.er:
, The reference letter requested a licensing basis for a change to the Hatch 1 Technical Specifications (Tech. Spec.) which would change the HPCI & RCIC operability requirement from 113 psig to 150 psig reactor pressure. The Tech. Spec. changes and their licensing basis are given below. This work has been done under blanket purchase order no. B33576 release 46 as authorized.
The recommended changes .to the Hatch-1 Tech. Spec. are:
- 1. Change 113 psig to 150 psig for system availability and shutdown requirements
- as shown by the attached markup of Pages 3.5-6, 7, 8, and 9.
l l 2. Delete the last paragraph on Page 3.5-16.
- 3. Cclete the first two sentences of the second paragraph of E.1 on Page 3.5-17.
The bases for these proposed changes are as follows: The system design specifications for both Hatch 1 & 2 only require the RCIC and HPCI l to provide rated flow at 150 psig. These system documents do not require any partic-l ular system performance below this value of reactor pressure. However, it is widely understood that in practice they can deliver some reactor makeup flow at pressures below 150 psig. l u . - ~ . . . - - .
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-l. The source of the Hatch Unit 1 requirement that "some RCIC flow is required between 113 and 150 psig." cannot be determined. This Tech Spec. wording was probably included so that continued RCIC/HPCI operation down to the shutdown cooling pressure permissive interlock (135 psig for Hatch) would be assured. However, this is not an established BWR system requirement and is not a part of the RCIC/HPCI system design bases. j . The suggested wording for the Tech. Spec change submittal by Georgia Power Company to the NRC is given on the attached pages. Please verify that the FSAR sections mentioned are correct. They were taken from our FSAR copies which may not include recent revisions. This completes GE e'ffor'ts on this task. Should you have any questions, please contact us. , Very truly yours, A. L. Vest Service Manager -Nuclear ALV:JWW:jms Attachment f* l 4.g ea.v- .g
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~ 2. AFFLICARLE DOCUMENTS 2.1. The latest issue of the following documents form a part of this specificatione to the eatent specified herein.
- - - - - - - ~ - 2.2. Standerde and Specificatione Design Specification - Reactor Core leolation Cooling System, 22A1354 Design Specification - Pressure Integrity of Piping and Equipment Pressure Parte - MPLI A61-4030
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- 2.3. Drevinto Piping and Instrumentation Diagram - MPLf E51-1010
- Process Flow Diagram - MPL# E$1-1020
- Functional Control Diagram - MPLI E51-1030
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< - .. .. . . ;. . 3. DESCRIPTION - - em , % ., *.g % ,,y The RCIC System consists of a turbine, pump, piping, valves, and instrumen-
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...c tation to maintain sufficient water in the reactor veneel to prevent the reactor fuel from overheating in the svent of reactor isolation accompented by a less of
_- ,, - coolant flow from the reactor feedveter system. 2afer to base doceent (refer-enced in Paragraph 1.1. and 2.2.) for further amplification of functions and dealan parameters.
~-
w.e 4 REQUIREMENTS .
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- - ,- ..- . - a- 4.1. RCIC Ptsop Operetto_n
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ac~. .C. J .N ,:7 % : - . 2;m- .S = ygav g t. Injection Flow---400 spa
' . r . - .y .~_.;.,- _m Coolirig Water Flow - 16 spa Total Pump Discharg; 416 SPs N**' W M ~
-^ i m'*-0e..?.W-m . ~ . . (includes no margin for Pump wear)
.- . - a.e. .r vw. G . . M" 40'F to 140'F
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. n;G WATER REACTOs SYSTWS WA8MW ,,, ,,, 22A1354AN .s.. 2
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4.1 (Continued) 2800 ft 91135 pois Reactor Pressure Developed Head 525 ft 9 165 pois manctor Pressure 500 HF G 2000 feet Developed Baad BMF, Not to Exceed 80 HF G 525 feet Developed Emed 4.2. RCIC Turbine Operation L. F. Condition H. P. Condition-1135 pela 165 pela Reactor Press (Sat. Temp.)
-- 1120 pela 150 pela Steam inlet Pressure 15 to 25 pets 15 to 25 peia Turbine Exhaust Frees
- 4.3. RCIC vater Temperature
.-- ;- far e es'.auous system operation shall 4.3.1. The maximeHowever, water tesperature rangt due to Mrw.a1 shre
- eto operation at higher tempera-not exceed 140*F.
tures, piping expension calculatfore .> id . m b est.! cr ! ?O'F.
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RCIC Orifice Steing 4.4 maximum 4.4.1. Coolant Loop Orifice - S*.e e::t M* 7% L g anantAnt *totoe 981= e' .te assure oil cooler inlet, pressu u .'? (MPLi E41-D009) ira &* e5 peia at the spray and a si-:iv. r.*e. ss c w e :, condenser. noaa' e:. .;s ...%
~ ~ ^ ' ~ ~ ** 4.4.2. Minimum Flow orifice - Size with paping arrangement to ensure minimum flow of 50 ppm with Mo-F019 fully open.
- (MPLi E51-D005)
- -. I -
4.4.3. gt peturn orific_e - Size with piping discharge presure arrangemest required when to simulate the RCICpJBP (MPLi E51-D006) System is injecting design flow with the reactor vessel pressure at 165 pet a.
- Sise for 1/8 inch $ minimus, 3/16 inch $ maximum 4.4.4 Leattoff Orifices (MPL# E51-D003 s D010) .
4.5. valve Operation Deentresente_
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Steam Supply valve - Opea sad /or close against full pressure within
-_.- .. ~~~~ ~ ' 4.5.1. 15 seconde.
(MPLf E51-F045)
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4.5.2. Fmp Discharge valves - Open and/or close against full pressure within (MPL# E51-F012/F013) 15 seconde.
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, ... , . . , - ._ . 4.5.3. Fump Minimum Flow typese Valve within - Open and/or close against full pressure 5 seconde.
(MFLt E51-F019) M
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4.5.4. Steam Supply Isolatter. valves -rate Close against full pressure at a minissa of 12 inches per minute. (MrLi E51-F007/F008) 4.5.5. Cooling Water Pressure control Valve - Self-contained downstream sensing control valve capable of maintaining
~
(MPL# E51-7015) constant downstream pressure of 75 peig. 4.5.6. Fump suction Ra11ef valve -Accumiati,n 100 peig Relief setting: 10 spa at 25 percent (MPLf E51-r017)
.. c 4.5.7. Coolics water Relief valve - Size to prevent ever pressurising piping, valves and equipment in the coolant icop in the event of
( M Li E51-F013) failure of pressure control valve F015. 4.5.8. Pump Test Return Valve -differential Shall be capable of throttling against 1000 pet pressure. (brLf E51-F012)
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J ew:2-- .-a_.. -u-_,____,_ 4.5.9. Relief valve Barometric condenser - retM Relief valve shall be capable of aing 10" Hg vacuum at 140*F (MPLi E31-F033) ambiant, with a set praesure of 5.7 i l peig, 20 GrH flow at 253 accumulation. Vacuum areaker Isolstican valve - Shall open and/or close against a dif-
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$4.5.10. formatial pressure of 200 poi at a mini-
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M . TC .~.J .'. " ~ _ _ , num rate of 12 inches per minute.
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*---<M ' QawC .% s,.a-4.6. Rupture Disc Assemblies - Utilised for turbine casing protection, shall (MLi E51-D001 and D002) include a mated vacute support to prevent
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rupture disc reversing under vacuum conditions. I
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Rupture Pressure 150 pois + 10 peig
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l Flow Capacity 45,000 lb/hr 9165 pela 4.7. DC Motor Power - 3 BP or lose Cland Seal Chaaer 51ouer Motor 3 EP or lose j
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2~ ~ -J Clend Seal Condenser 3 rain Fump Motor
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100,000 gal.
~,._.a.. 4.8. Condensate Storate taeutrements
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- .af-M 4.8.1. Total reserve storage, per tait, for both EPCI eni RCIC Systems.
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BoluMG WATER REACTOR SYSTEMS DEPARTMENT o.cuuan, 22A1354AN m o. .. 2 y h
' nos no. 5 4 Final }4 4.9. Turbine Rwh b m
eust vertical Reaction Force .= w..
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p Unbalanced pressure due to open end discharge under the .,{.4((
- t' . level, which requires vertical hold down is 20 pai suppression pool water .
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, Normal Plant Operation -
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Cd.".R. FAUSnletA - 2. ENRfC0 FLR.C TITLE OF DOCUMT NT RF APOP C'utF Isr.'ATTON t'Ont.INC SYSTEM TYPE OF [] PURCHASE SPECIFICATION REPLACES DOCUMENT:F) SYSTEM DESIGN SPECIFICATION DOCUMElIT NO.
.- - -.. - - - - [] INSTALLATION $PECIFICATION a_. []
,---' PIPING OR COOLING SYSTEM INVOLVED RESPONSIBLE ENGINEEP. BL SMITH ISSUED BY TI Beg DATE ga n v . . .,
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'- RE FERENCES ~
~
- ~ ~ ~
MA5TER PARTS LIST (MPL) NOS. 5PL# ES1-4010' 1 Trio - - - - . SPECIFICATIONS DRAWINGS OTHER _.' " ^ r m.,, - . - - -- ' REVISION RECORD *+d
- REVISED PER (ECA, ECN, ETC.) ECA's 10114-4.10129-2.10106-1-EC'T NE24929
' 4
- REVISION IDENTIFIED W11 SHEETS AFFECTED _
,. . . ~ COMMENTS:
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_ . . NAME MAIL CODE COPIES NA.E " MAIL CODE COPIES
~ .. .. . . . . . TI BROOKS 750 1 yny 742 g BL SMITH 524 1 DCC 742 1 STANDARD PIANTS ENGINERIUC STA M P WT. '
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AT02 AA00 AT02
- , TOTAL 13 '!VTAL 10
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l 22A1354 PR04 ELMICO FERMI PR04 10NG TSLA:4D LICHTING TOIAI. h E6 13+1M' TOTAL 12&2k+1M 6-2R*1M Alexander 1 A4exander 366 369 1 Johnson 1 Bit.kley 3C Dalton 369 125 1 Rooi
.. PRC4 FUKUSHIMA II
- m. PR04 CAROLINA
' TOTAL 7+3R+1H 1+3R+1M 366 TOTAL 13+2R+1M 12+2R+1M Alexander 1 Alexander 366 365 1 Russ 1 Smith 385 384 1 Simons 4 A Levine 632 126 Roof PR04 LIMERICK PR04 HATCH TOTAL d+1R+1M TCTAL 6+2R+1M 3+2R+1M 366 $+1R+1M 366 Alex2 tder 1 Alexander ~1----
371 ucodvard BE d 81 1.dre RL 1 1 Gifford 632 Albert 632 O= 1 Eckert HATCH I 354 1 632 1 Cordova - Wanner HATCH 11 --- PR04 CAORSO TOTAL 10+3R+1M 14EWBOLD 366 10+3R+1M PR04 Alexander . TOTAL 5+1R+1M St Clair Alexander .~g gig , _
. . - 633 _ 3 ,
Roberts g,,y g e, 335 Eckert Eckert 663
... .w e .s cee . -* .. e.**d ZURICH 1 63? 1 Albert C Herrick g g Wanner 632 Diefenderfer 38)
PR04 CHINSilAN PR04 SU!?JEEAMA TOTAL 7+2R+1M 4+2R+1M TOTAL 3+1R+1MJos 366 1+1R+1M Alexander 1 Alexander 1 Kilsby ER 365 632 1 stove CR 1 376 Veiss ND 389 Cochran RG ~ 1 632
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- ATOMIC POWEit EQ'J;PMENT CEPAnt fmCHT APPLICAl!CN s.. J..., c 'ifmi.
@sufCIFICATION Olt AWING TYPE DESIGN REACTOR CORE ISOLATION COOLING SYSTEM DOCtJMENT TITLE
- *REvis!ONS 2 Revised per ECA 90825-3 - -- ,_ - - - - .
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CENERAL $ ELECTHIC ain*C PO*Ee CCUIPrtN1 CE PaRTutNT g a s = -e 4
,jr ..., -, 22A1314 DESIGN SFECIFICATION g.),'- ,- - 2 wa * - 3 EEACTOR CORE ISCL.A11'.d4 C0011M SYSTFM
- 1. SCOPE 1.1. This documant describes and defines both system and design requirements of the Reactor Cere Isolatim Cooling System (RCIC System) to be utilized with a nuclear boiling water reactor plant.
1.2. This design specification was prepared based upon no specifL. division of work assignment or responsibility between the General Electric Company and its custo=crs or contractors. The division of work assignment shall be specified .. . . _ _ e1sewhere. ( . i.
- 2. APPLICABLE DOCU::ENIS - - ,
2.1. Tne Data Sheets of this '3ase document c:mprise the coctrollina syften speci-ficatioas. If thers is say eccflict betueen this document and the Data Sheets, the specifications of tLe ' at Sheets shall govern. 2.2. Drawings, specifications, staaJards, and docwnents related to this specification only are referenced in Parag,raph 2. .'t -% Data Sheets. Documents showing project , - = +-%-a- w - - u requirere.cnts are listed 11 the .tst e . .i Lint for the particular project. I A= I 1
- 3. DESCRIPTION The Besctor caro 1, , . #: .'14.. > v . onsists of a turbina, pump, 3.1.
piping, valves, and 1..t.n 4..' e v. . ! m ' *
.letlin af ficicut water in the reactor vessel tu coo . e d su 'r sessel be isolated.
m M = wm : .= w .m.,. a. _; .- ~< quate core cooling takes place to 3.2, the system provid. .i. e. < prevent the resctor (*! in.c., .aeting in the event of reactor isolation [._
- t. accompanied by losa of coolant 4.ow t rum the reactor Iced rater systen.
~ .
* ~
3.2.2. Tha RCIC Systen allt,ws for conplete plant shutdwn
- t. & r conditions cf loss of tis norrat feedwater systen by staintainin;. suf ficier reactor water in-ventory until rh reactor is depressurized tn a Icyc1 w:icce the shutduun evolant
~
system can be ptaced into operatio.a. .. -. j l
- 3.3. Following a reactor scras, steam gener: tion will continue at a r.duced rate
* ~ ~ -,,
. . . .-;4 due to the core fission product occay heat. At this time the turbine bypass system will divert the steam to the main condenser, and the feedwater system
-s.._
>..* will supply the cake-up water required to maintain reactor vessel inventory.
7.7
**aa.y -e =- . - m - -.~w_A q 3.4 In the event the reactor vcasel is isolated, and the fecdwater supply is a - . .- ;..% . a r . .w
. g.f.gu.,% unavailable, relief valves are provided to automatically (or remote manually) e . o - .. -. f. , ~* . maintain vessel pressur within destsable limita. The water level in the teactor vesael will drop due to continued st am generation by decay heat. L'pon reaching m .g . p . n,..'.Lbn : w 1 .r.,~. - ~ . . . ,
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GENER AL h ELECTRIC atemc co=re touu1NT ere etutur l u . ... 22A1354 .s .. /. DESIC': SPECIFICATION .. 3 n . u,4 3.4. (Continued) a predetermined low level, the RCIC System stall be initiated automatically. The turbine driven pump will supply demineralized stake-up water from the con-densate storage tank to the reactor vessel; and alternate source of water is available from the suppression pocl. The turb*ne will be driven with a portion
. . of the decay heat steam from the reactor vessel, and will exhaust to the
, '* *; supr:ression pool.
3.5. Durirg RCIC operation, the suppressior, pool shall act as the heat sink for
~~
. steam generated by reactor decay heat. This will result in a rise in pool water tempe ratu re. Heat exchangers sh awn in the Residual Heat Removal System are used -- -
to maintain pool water temperature within acceptable limits by cooling the pool water directly or by ccndensing generated steam prior to entering the suppression pool. for plant arrangements using the steam heat exchangers, the-condansate discharge.from the heat exchangers may be used as RCIC pu p suction supply.
- 4. REQUIRD2.:;TS 4.1. Syste, 4.1.1. The components of the RCIC System include:
. .,a
- a. One 100 percent capacity turbine and accessories
- b. One 100 percent capacity pump assembly and accessories a a. v ,w.,o.m ,=
w . . 2
- c. Piping, valves, and instrumentation fort
- 1) Steam supply to the turbine
- - 2) Turbiae exhaust to the suppression p el
- 3) Make-up supply f rom the condensate storace tank to the pump suction
,,,; . 4) Make-up supply from the suppression paal to tl.a pump suction
-.7. M 5) Make-up supply f rom the RIIR steam coadci.1.y 1. cat exchangers
- 6) Pump discharge to the feedwater line, including
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, minimum flow bypass line to the suppression pool. .m ewe...n _
4.1.2. The RCIC System shall have a m.ake-up cap.. city sufficient to prevent the s3. , - . .-*mg _ _ reactor vessel water level f rom dropping to the top of the core. (The flow rate
. is approximately equal to tic reactor water boil-of f rate 15 minutes af ter shut
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GENER AL $ ELECTRIC AeC,aHC POWEe LQUIPu!NT DEPARTMENT
..u... 22.'354 ......4
.. 4 u . .. 5
.~4SICM STECIFICATIGN 4.1.3. Upon receipt of the re v. tor vessel low water level sigr.al, utillaing one-out-of-two-twice logic, tbd RCIC System shall start autmatically and deliver design flow within 30 seconds. All componenta necessary for initiation of the RCIC System shall be capable of start-up independent of auxiliary AC power, plant servica air, ar.d external cooling water systems.
- - 4.1.4. The turbine control system shall be positioned by the demand signal f rom a flow controller, and shall satisfy a two fold purpose:
a) Limit the turbine-pump speed to its maximum normal i operating value, b) Position the turbina governor valve (s) as reguired f to maintain constant pump discharge flow over the ( ' pressure range of system operation. - -. .m _ 4.1.4.1. The operator will have the capability to select manual control of the governor, and adjust power and flow to match decay heat steam generation during the period of RCIC operation.
.4 _- --_, - - . .
4.1.5. The make-up water shall be delivered into.the reactor vessel through a connection to the feedwater line and distributed through the feedwater sparger to obtain mixing with the hot water or steam within the reactor pressure vessel. 4.1.6. Automatic shutdown of the RCIC turbine shall be provided upon receipt of one of the in11owing signals:
. .. , ._.]-
_ . .o. a) Turbine overspeed f * , ccq..w;,,,* b) A high water level in the reactor vessel
~ g. 4 ma.u- _-..
I c) A low pump suction pressure C., . - . d) A high turbine exhaust pressure
,e. . _ _ . -
e) Auto-isolation signal 4.1.7. The steam supply to the turbine shall be automatically isolated upon h receipt of one of the following signals: a) A high pressure drop across a flow device in t'as steam supply line b) A high area temperature, utilizing differcatial temperature switches - -- via time delay with a manual bypass. High area temperature is also
- 3. ~ . .. .. . , . , .
alarmed in the control room.
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"' ~ ~ ' ' ~ c) A low reactor pressure, rtilizing pressure switches connected in redundant sets of two-out-of-two logic.
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ww . ... w , .-. .. w.- . j - , .P ~ d) A high pressure between the turbine exhaust rupt'are diaphragms utilizing pressure switches connected in redundant sets of-two-out-of-i.,1.,, two logic.
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ATCrt POste EcudutKT g EPMTutzt so a' 22A1354 an. =e 4 DE51rA $PEc!FicMION ~~ ~ *~~~ ~ '- '-- ."..' * .* - - * - '- ----~ ^ ~ - ' - ' - - 5 < * ** = - . <
- 6
...~ r*~.a... w m . ._n 4.1.F. In additic,n to the automatic operational features, provisions shall be _,
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included for remote-s anual start-up, operation, and shutdown of the RCIC Syste:a, e= mn" p . s .v". a?*kJ.M4TT.h provided initiation or shutdown signals do not exist. . ..
~ ~
4.1.9. A design flow functional test of the RCIC system may be performed during t
.._..c. ,a.c.:.,.,- ~.-_-- - - -
y - .. --m.~q. . -. normal plant operat.a by drawing suction from the condensate storage tank and ;QQ_;. ,r.q , p.[.3 e .-~.f ,~~ T ~.- - 7 '7 ~ ~ ,.f. ~- 29 ~ - ~ discharging through a full flow test return line to the condensate storage tank. - f ..j'M "f "O.E . - The discharge valve to the feednater lia.e remains , closed during the test, and ratctor operation remains undistr W d. Control system design shall provide auto- , . _ _ ~ , ~' . . ' g. ' natic return from test to oper.: ting neode if system initiation is required when in ? ' '* , _ . ,
. the test.made.
-- .. -- _; ~
. . , . . ~
4.1.10 All compacnts of the RCIC System shall t e capable of individual function-El testing durlug norual plant operation.- . , . .. TJ - . ~ _ -
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4.2.1. = - :. ~ ~;;;; w :a ,.. The specification data sheets define the flow, pressure, and power "*~~M'.._. - ~ rsquirements of the components of the RCIC system. ,, ,. ..
%. ._ s 4.2.2. Ti.e turbine-pump assembly and a::cessories 6 11 be located in a shielded ~--T.':4. n .L -L. , . . . ~ ' -
Arse to assure that normal personnel access areas are r:ot restricted during jM~ ~ MW]r; yTi YYU3. .. ._ . . operaton of the RCIC System. .r.~..~ - ' ' ' - '
.?.3. The pump assembly shall be located below the Acvel of the condensate w aage tank and below the minimum water level in the suppre e t a pool to r. m -- .wm " * * " = . - - - -
.ssure positive suction head to the pumps. Adequite suburgence and line size shall be provided to obtain the required pump Net P W tiv? Suction Head.
4.2.4 The turbine assembly shall include steam p.! -r.J gland seal condenser systems capable of preventing out-leakage from the turbiuc shaft scals during * - operation. ,
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signal to delivering design flow stall be within 30 cecond:. -
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4.2.6. n e RCIC turbine shall be capable of stag rup watuout prcheating anJ with _ . remote control under all operating conditions, inclue ng test mode start-up. --
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prsssure control valve shell be provided to limit time cooling water pressure per .. ^ * ' ~ - 7, [, Partgraph 4. of the Data Sheets.
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4.1.0. In addition to the automatic operational features, provisions shall be ... .w. - n.?>
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included for remote-sianual start-up, operation, and shutdown of the RCIC Systca, g h .y Gir-5eg-A.w provided initi. tion w shutdown signals do not exist. ~,s
, .- -. .~ - ~ . . .+ . , .~ ~r .t"v s 4.1.9. A design flow functional test of the RCIC system may be performed during _
normal plant operat .n by drawing suction from the condensate storage tank and - [Mi[ f.;MQid- .- .. '.f/. -y:M.W w --y discharging through a full flow test return line to the condensase storage tank. .o ,M ".- . c C'L'.* W./" *.'.~# P The discharge valve to the feedwater 11he remair.s ,cissed during P.he test, and ru ctor operation remains undistr @ d. Control system destC n shall provide auto-
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matic return from test to oper.: ting mode if system initiation is required when in ' thi test mode. ~ - "*", 4.1.10. All compa. cats of the RCIC System shall be capable of individual function-al testing during norual plant operation.- -
- --- . . . - ~..e-.- ' - .A 4.2. _ Design
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_. . ..y.'..a . 4.2.1. The specification data sheets define the flow, pressure, and power C r quirements of the components of the RCIC system. M ""#Y2%$*
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4.2.2. The turbine-pump assembly and a:cessories s;.11 be located in a shielded -
;. _ - . . . :x.
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.?.3. The pump assembly shall be located below the level of the condensate et age tank and below the minimum water level in the wpprenaion pool to - "'
.asure positive suction head to the pumps. Adequtte subraergence and line size ,_ _ .,
shall be provided to obtain the required pump Net P W tiv2 Suction llead, 4.2.4 The turbine assembly shall include steam m.! _ .. r> cland seal condenser systems capable of preventing out-leakage from the turbino shaft scals during operation. 4.2.5. The r r. aired starting timo for the LCIC Syst m ir c receipt of actuation - signal to delivering design flow stall be within 30 ceconh. U. .- . - 4.2.6. The RCIC turbine shall be capable of start-up wituout preheating anJ with . -
~." w.,. .- -
remote control under all operating conditions, including test mode start-up. -
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4.2.7. Cooling water for the pump-turbine operatJon, the l9be oil cooler, and '
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4.2.8. The steam supply line to the turbine shall be maintained at elevated temperature down to the shut-off valve directly upstream of the turbine by mnans of a drain pot and steam trap arrangement. The steam trap shall drain to the
,]
- _ main wndenser during normal plant operation and shall be automatically isolated
._ when the RCIC System is initiated.
%.2.9. Materials. Material selections shall be based ora useful life of 40 years, eith the rea115 tion, of only intermittent (app.cxinately once a conta) operation of the syctas.
4.7.9.1. The suctior. line from condensate storage shall be corrosion resistant ._ _. . A material (stairlaga ster or almi .um) in order to minimize crud deposition in the storage tank during Ll.e cast mode operation. TI.e ca. ban steel piping required in this test Icup (i.e., the conne".ticn--to the pu.pp suec4eu, and-the-pump discharge lino to the test ct,nnection) sM11 be kept to a miniess.
- 4. 2.9. 2. Turbine casir.g and turbine steam lines shall be selected to cope with conditions of corrosion during shutdown periods aad erosion during system operation.
4.2.10. Pipim. Runs of syste:n piping in the secondary containment which ara subject to damage due to possible failure of piping or :omponents of other syst.m ( shall be protected by structural steel, reinforced coners.te, or spacial separat. . 4.2.10.1. All flanged connections between the prinn/ containment penetrations
, . . . _ - _ _ w.. - '
and the first ex ternal shut-of f valve shall have double gaskets and provision = _ for inter-gasket leak checking.
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4.2.10.2. Piping and equipment, including support =trustures, (excepting the condensate storape tank) shall be designed to meet Class 1 earthquake require-i ments. (W te: The suction line from the condensate storage must satisfy Cla s 1 1 earthquake requirements). i 4.2.10.3. Systui piping and equipnent shall satirfy the requiremerts of APED Standard Design Specification - - Pressure Integrity of Piping and Equipment Pressure Parts, listed in the Data Sheets. 4.2.11. Specified on the Lita Sheet is the unk.lanc... scrtical pressuriforce
, due to the open end discharge of the turbine exhaust into the suppression pool wish 4 feet submerpfa;c helow the pool water level. The flow used in this
. . , , calculation is that i...rh the turbine would pass, assuming control styrtem f ail-ure with the re at t.
,--7 s .
4 full pressure. Mm--- NCLa====-MP~ ~,' d*W " 3 4.2.12. Reserve storace shall be maintained in the condensate storage tark mba.ei-% -.o .ecasc.u s ,-:%y/ w to satisfy the specif *r requirements of RCIC System operation shown on the Data wwm . 4 w--. , m- Sheet. In order to 3ssure tbc storage availability, other system requirements for condensate which cculd jcopardiac the reserve storage shall be capable of _..,_..t.w..- e %.. w . A-' being isolated, amJ/or a low icvel alarm shall be provided in the control raom - at this energency reserve level.
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F41-4010 227.13'.2 ; 6311-01 l 13- D 2 l SX17024 TITLE:
'tirf Pressure Coola-t Injectimi Syster-JOB ETI!' I.11A?"H :* C1. CAR PLA**T CIT 1 MFR PQ R E Q.
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EN # 234' 25 to 65 pela Turbine Exhaust Pressure Hasimum - The seminas water temperature for continuove system -~ - _ N""' 4,3, HPCI Water Temperature. opsrctiva shall not exceed 14)*F. However, due to potential short ters operation at highsr temperatures, piping erpansion calculatione shall be based on 173'F. 4.4 HPct Orifice Siaina . .. ._
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4.4.2. Minisme Flow Orifice (HPLi E41-D005). Sise with piping arrangement to assure
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. g Steas Supply Valve - Open and/or cloor against full pressusa wits.An ^V'--"f*;.J *r :.vRu s,,r *. 99.v.-* %
4.5.1. (MFLf E41.FOO1) 00 seconds. -- _ r.w _. , 4.5.2.~ Fusp Discharge Valves .open and/or.close.against full pressure within '" ' ~ ~ " "
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F 7.V 6.).3. F.:; Mininum flow Bypass Valve - Open and/or close against full pressure . 0:Fia L.1.F012) within 10 seconde. = q.~~.'.'.". . . .
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4.5.e. Steam Supply Isolation Valves -minimum Close against full pressure at a rete of 12 inches per minute.
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(3 La L.1.fou2/f003) . . 4.5.). Cooling Water Pressur.s ControA vaAve - beif contained downstream sensing
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$ 4.5.9. \a:4.s areaker Isolat:.on valves - Shall open and/or close cgainst a dif ferential pressure of 200 poi at a minimum rate of 12 C2La L.1-I W/ F M 9) inches per minute.
4.6. pupture Disc (MFL# E41. AJ03 6 D004) surbine Casing Protection kup;ure Pressures 175 pois f,10 psig ~ Flow L.apacity: 600.000 lb/hr at 200 pois ----
. 7. DC r.eter Power. Maximum . . -
Hyorculic 011 Fump Motor -. . 7.5 hp * - Jiand Seal Condenser vacuum F amp Notors 1.5 Hp .
.... wlane seal condanser Drain Fump Motors _ . 3.0 pp ., _ ,
..g. consensate storaae 100.00u Gal. [ , .
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Cenatal E1cetric C.'ese
' TRAN5NITTAL
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DUANI A3NOLD. ENRICO FERMI II. CHINSMAN. LILCO PROJECT ($) STANDARD FLANTS 236X350A.B.C.
- CON EDISON. RATCH, CAROL!!:A NS16 2 I TITLE OF -
DOCLM XT HIClf FRIS$URE a)CLMT INJECTION SYSTEM (11FCI) REFLACES DE:1GN FREEZE ... TTFE OF [] FURCHASE $*ECIFICATION DOCLE NT E0. DOCU*'. EXT:F] SYSTEM ttstGN SPECIFICATION Il INSTALLATION SFECIFICATIC:t () RFCI FIFING 01 COOLING SYSTEM INTOLTID TI BROOKS _ ISSUED ST BL $NITH DATT N I $ $ Ib e RESPONSIBl.E ENGINEER RITT*I': CTS ~
'E0I*4010 MAST [R FARTS LIST (MFL) 505.
SPECIFICATIONS . . - DRAWINGS OTitER REV13!O4 PECDRD Riv ntD Fan ( G E G . EEEIT NE23111 e REVISION ZDi.NTIFIID WITH g
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- 22A1362
* * ' * ' * ' t-jb ====4 I a . .. .-m 2 gics PR,r3St'RZ Ceci.',NT INJICTION :sYSTD1
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This document defince the design - equirements of the Righ Pressure Coolant Injection Syste's (10 CI System) to be utilised with a nuclear boiling water reactor plaut. ~ ' 1.2. < , . - work assiannect er responsibility between the Canaral Electric Company and it customers or contratters. elsewhere. The division of work assign::.est shall be specified
- 2. APPLICA3LE DOCC'MIKTS 2.1 a fications,The Data if thereSheets of this is any basebetween confitet docisacnt comprise this d oeurant the controlling s-sten spect-opecifications of the rate Sheets shall govern. and the Data Sheets, the 2.2.
Drawings, specifications, standarda, and documents related to this specification ~' on1r are referenced in Petamraph 1. of the Data She:ts. ~ requirements are lieted in the Master Parts Ltat for the particular project.Docu=enta aboving project
- 3. DESCRIPT1.M -
3.1. The HPCT System supplies make-up water to the reactor vassel is the event of a loss-of-coolant accidente or reactor isolation ana failure of the Reactor Core Isolation Cooling Systen. The make-up water le required to natatain suf ficient reactor water inventory einee steam generation vill continue at a reduced rete due ta the core fission paeduct de:ay heat even though the reactor has scra:mmed. A turbine-driven purpine enten is used ta supply deniaeralised make-up water fram , , the fromcondensate the suspresaton storere teak to the reactorg an alternate source of water is available pool. Be turbine is driven with a portion of the decay beat etess from the reactor vessel, and exhausts to the suppression poc1 3.2 The RPCI System consist
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.--* 2 ===**=-e.1 3.2 (Continued)
. ~- i Ploint, velves, and instrumentation fort g#,';;, y . . 'C .'**
(1) Steam supply to the turbine (2) Turbine erbauet to the suppression pool (3) Make-up supply from the condeneste storage tank to the pump suction __,z
- (4) "'M Q Make-up supply from the euppression poci to the pump suction (5) Fump discherse to the feedwater line, including a test N -
line to the condensate storage tank, a minlaum flow bypass line to the suppression pool, and a coolant water supply to accessory equipment. -- -
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4 SIQU11trums - ~ ~ - -
' ' ' 4.1.
The rFCI System shall provide assurance that adequate core cooling takes place to avoid overheating of the reactor fuel in the event of a lose.of-coolent accident which does not result in rapid depressurization of the pressure vessel. S-i 4.2. The RFCI Systen shall allev for complete plant shutdown by maintainian sufficient resetor water inventory until the reactor la depressurised to a level where into the low pressuse coolaat inject 1=;. system er cere sprey eyetem can be placed operation. s.3. The HFCI System shall be capable of fulfilling the objectives of the Reactor Core Isolation Coo 11ag System la the event the system falls. 4.4 . The RFCI System shall be placed into operation autcoatically (with provietone included for manual operation), and shall be capable of start-up operation indepec-dent of auxiliary AC power, plant service air, or external cooling water systems. 4.5 The tv .Se ce,ntrol system shall b9 positioned by the demand signal from a flow control .r. and shall satisfy a two-fold purposes a)
Limit the turbine-pump speed to its nazimum normal operatteg value, b) Poettien the turbine governor valve (s) es required to maintain constant pu:rp discharge flow over the pressure range of system opetetton.
4.5.1, , Manuel operatico of the control system shall be poealble when in the test 'e y.de, but automatically repositional by the demand signal from the flow controller r- ^ ' - -. ~~ i . n :-7 if systen lettiation to required. 1
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i GENERALO Eucraic A TCmC Poste 50utPythr DE PAeTesENT
..es .. .....4 s.
3 22A136.' ee .. ...4 YS!GN SFiCIFICAf!ON
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4.6. The sv ke.up water shall be delivered into the reactor vessel through a tee connection t o the feedwater line, and distributed through the feedwater sparger te obtain ac sing with the hot water or steem within the reactor presstrie vesaal.
- a- - ..v_, 3 , 4,7. All comp:>nects of the NPCI Srstem shall be capable of individual functional --- - - - - - - -
. d.
testina dursos nom:1 plant operction. 4.8. A design flow functional test of the HPCI System say be performed during normal plant operation by drawing suction from the condensate storage tank and - discharging thronh a full flew test return line to the condensate storage tank. The discharse valve to the feedveter line remains closed during the test, and ..- reactor ope ation remains undisturbed. Control system design shall provide automatic rnturn from test to operating mode if system initiation le required when in the test rode. 4.9. Me-chanical and Civil 4.9.1. De flow. pressure, and pwer requiremente of the components of th.'$.<CI '-* *-
"' System are specified on the data sheets.
4.9.2. De erstem shall be si:ed to provide sufficient core cooling to prevent clad eetting during the tine interval that the pressure in the reactor vessel tekoa to decrease to a value where Lt.e low pressure coolant injection system or de core sprey system becomes effective. 4.9. 3. De turbine-pt=. eseeably and accessories shall be located in a shie ..a , eres to assume t.het norzal personnel access areas are not restricted during e - tion of the EPCI system. e s.e 4.9.4. De pop easembly shall be located below the level of the condensate . . tank and below the etnicum veter level la the suppreeston pool to assure po.ita' 6 emetton head to the purms. Adequate submergence and line essa aball be pre obtain the required pump NPSM. 4.9. 5.' N turbine assembly shall include steen seal and gland seal condenser systems capable of preventing out. leakage from the turbine shaf t seals during operation. 4.9.6. N startina time for the RPCI System from receipt of a.tuation signal to delivering design flow shall be withis 25 seconde.
~- .?
.e _ 4.9.7. N EPC1 turbine shall be cepoble of start.up without preheating and with remote control under all operating conditions.
~ 4.9.8. Coo 11am water for the pump-turbine operettom, the the tube oil cooler, and the gland seal condanser shall be supplied from the discharge of the booster pup. n> ,.-n
. . .. .c .e. -
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4.9.10. !isterid selectier. shall to h9 ed on a useful life of 40 years rath the realtratic.: cf caly 12:4:=ttras: (aF;??si.:atdy or.cc a monte) operstice of ths . sy a t m. /* g 4.9.1".1. *te surr an !!=c f res c::Je.sats storale asJ c the test return 11ae to c&Messa:e storue metrea: ef the wtor sterated s'uteff in valves shall be corro-order to minis 1:e crud sies resta:as: ta:< rial (e:aisless steel er 41* -*) f t ;* r.i t N; h f - *
- Tage tasa Jurarg rte test =Me cperation. The camboa steel pi;nt. ret dre * . es test Ir; (f.e., :%e cansa:tios to the pucp suction, and the Hy cisc ..... .;;.a as :;e tes: cor erties) shal' be sept to a siniaa z.
4.1.13.2._ , , , , , 'titerial asle:tirl if tha' t.r'stre earlag and the turbios steam 11aes.
- v. , shall ta =2fs u .- :Te her.la. ;e :%t tress areas s!!1 he sebjected to high moisture
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hip. vQcity a tta.:. vita rcaa.1:.:: art:sica prisk.a duttaa shutdcm3 periods, and erostos prsble=* f;r h4 s rste.s e;erati.as. 4.9.11. P.1 fia::e! :ense-tions be:vaes the primary centsizment penetrations and
*** e sedf q =f m ,3,% s>,,, % , ,,
- W, the first anter*M u.ut-cf f salve s! all have dov',:e paahets and provisions for trat.rsaslet 24.i :1::11:; .sthem: remirtrg pre,vertaing the prhary contair===t.
Eure w* ., .- ,:;1: 6 is th: sece, *,gry ge=tst_eest .Afeb era seddees to 4.4.12. !al;. a :f =2 art? pt?!ss er c'.rpocents of oti.er ayat.aa alall
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.- ., - be protected by stratural steel er reis* arced ccccrete, or opacial separation.
j.. . . ,.
~~e 4.9.13. F1 ping and ev:vi;2.ea:, includiss support structures, but escludtrg the ec= der. sate storage tack (s) shall be destasei to meet Cass I earthquske requirements.
g.. ye s.s (k te LP.* sectims itse f rom cor.desaate ster *4e sust satisfy Casa I earthquake
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restresents.) g 4.9.14 System raping and ewsp:ent shall satisf y the reguire===ts of APD Standsed Ne ty,w Westic.:: s . Prasare lategrity of Pipi=g and Ir.wipment Pressure Parts.
- +* - g- -*
......,[..s ~ . . ,. . - . * * . .
.. listed la the T.ata Sheets.
4.9.15. The E?C systra pag: 3 s.all be deelstad te withstand the unbalanced
- . . . . vertical f orce ese to tan cres end 4:scherte of the turbism entswet hlate the is force
" * * ' ' - ... euppressias pool uta 4 f eet submergence colow The the flawpool moed water ti, this level. calculatsoe is
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. . . - that m'.tch the tarute would pass assuntas control system f ~ailure with the reacter
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~~' ' --m . $*""*"'t. - * *' Saalatice coolins system (Eet. applicatie :sta sheet).1.111:y, et%er syo6en retetsseemta fe 4s.re ete ats,raee a a Is erser t.
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GENEDAI h ELECTRIC Af Dn'C P0vit ECUterstNT ttPARTM!NT .... . 22A1362 ....,,4
..... 5 ......,6 DESIGN SH CIFICATION -
4.9.16. (Continued) isolated, and/or a low level alarm shall be provided in the control room at this~ ~~ ee.orgency reserve level. 4.10. Controls and instrumentetion The E?CI System shall be capable of automatic start-up The upon receipt of initiating 4.10.1. en initiatica signal, and deliver design flow within 25 seconds. signals include reactor vessel low water level and/or primary containment high dr;well pressure, both utilizing the one-out-of-two-teice logie. 4.10.2. Cc.atrois and instnisentation shall provide for autenatic shutacwn of the HFCa turbiae upon receipt et one of the following signales
- a. Turbine overspeed I
- b. Eigh water level in the reactor vessel
- - - - - - u .w.--.u c. Low pump suction pressure
- d. High turbine exhaust pressure
- e. Auto-isolation signal
~
4.10.3. la the event en initiation alrnal is received after the turbine has b [ \
... . ' ' * " ~~
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shutdown, the mystem shall be capable af automatic restart.
, The RFCI system shall be outcastically isolated upon receipt of one of
l
" ^**'* N - 2O -ww. ,'u , ,y ,_, -- - .- - 4.10.4 the following signals
" * ' ~- . -.
s. Eigh pressure drop across a flow device in the steam supply line
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- b. High area temperature, utilizing differential temperature switchesHigh via time delay with a manual bypass.
alarmed in the control roca.
" c. Law reactor pressure, utilising pressore switches connected in one-out-of-two-twice logic. ^~ ~~
- d. Eigh pressure between the turbine emhauet rupture dia
', som2 --
.- ~ - .- .-' ,
4.10.5. In addition to the automatic operational features of the system,d pro- "-
, . - - - - .~ . %.y . 3 PC "f %-ew 4 )^{,j ~ ~
-- vision shall be included for remote-mani.a1 start-up, operation, and shut own
' , (provided initiation or shutdown signale do not exist.)
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4.10.6. A flow control signal e%all be provided to automatically adjust turbine m Provisions shall also be included for remote-f turbine nw 3 s 7, M.'.m e :# - - w
- P8"er to deliver injection flow. manual overside of the control signal, and rem
. ~ . . . . . , - . .. Power to obtain the desired flow.
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4.10.7. system operation requires automatic actuation of the following valves u-.-- Fissp discharge shut,o,ff
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CENER AL O iteeraic
.- aTCulC PorLd (QUgPMcNT OtPARTENT 4
.. s e ... 22A1362 as..
....- 6 <+== +=e-es' 7 DESIQt SPECIFICATION 4.10.7. (Continued)
Turbine control valves Start-up of t..a hydraulic oil pump and proper functioning of ti.e hydraulic control system is required to opea the turbine valves. Operation of the gland seal condenser components is required to prevent out-leakage from the turbine shalt seals. Startup of the equipment is automatic, but its failure will not autonatically shutdown the EPCI systas. Make-vp water is initially supplied from the condensate storage tank. How-l 4.10.8. ever, if the water in the storage tank falla below a predetermined level, or the suppression pool rises above a predetermined level, the pump suction supply shall automatically transf er to the suppression pool. 4.10.9. A minimum flow bypass system, discharging to ne suppression pool, is provided for pump protection. The bypass valve is automatically opened on low flow signal, and automatically closed on high flow signal. ._
. ===_ . . - , _ ,
4.10.10. Tbs shutof f valves in the system test line shall be sequenced closed from the system actuation signal, and shall be interlocked closed when either suction valve from the suppression pool is open.
- ,. .__~ , , _ ,
s . - , . l,,. ".. ,. _ 4.10.11. The steam trap drain from the steam supply line shall be autcoatically 96.. .^~ .s m . ..
^ " - 1solated from the main Steam condenser upon activation of the system.
i - 4.10.12. All automatic-operated valves shall be equipped with a remote-eanual
.: w'.ww cw.-.
. .* e- . % .. s .ec in functional test feature, with interlocks supplied as required to assure proper
* * "" - sequence of operation in the test ande.
- m. c. 4.10.13. We electrical components of the RPCI System required for system activation call be operated by DC power (station battery system).
*m + 4.10.14. In addition to the DC power required for valve actuations and instru-
.1. --
mentation operation, the following DC motors are required for systes operation. Their power regairements are included in the specificatica data saeet.
~ ";vs Shall operate for approziantely 1/2
. ;,, ,, (1) Bydraulic oil pump untor
- ~.- RJJL,. , . % : _ ;.,c- minute each time the HPCI turbine is started to supply hydraulic
_...A. . '. . oil and bearing oil tatil the turbine reaches sufficient speed
.[~ QQL'TY, 5; s' %'* and the shaf t driven oil pump delivers.
~ - .:f""- t T n '
(2) on each turbine shutdown, the hydraulic oil puep-motor will re-start
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as turbine speed decays, and the shaft-driven pump fails to deliver sufficient hydraulic e4 pressure. The motor will continue to run
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until operator action is taken.
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- v (3) Cland seal condenser blower motorg Shall operate during turbine s
i,.. . '7 * * .. ~<M start-up, operation, shutdown, and approximately 15 minutes af ter
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ohutdown to void the turbine casing of steam. -~
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