Text

Third Partial Response to FOIA Request for Documents.Encl App D Records Being Partially Withheld (Ref FOIA Exemption 5).App C Records Being Made Available in PDR
	ML20151K341
Person / Time
Issue date:	07/28/1997
From:	Racquel Powell; NRC OFFICE OF ADMINISTRATION (ADM)
To:	Barry D; PIERCE, ATWOOD, SCRIBNER, ALLEN, SMITH & LANCASTER
References
	FOIA-97-154 NUDOCS 9708060061
	Download: ML20151K341 (50)
	v • d • e

{{#Wiki_filter:~ U.S. NUCLEAR RbuLAiORY COMMISSION NRC FOIA HEQUES1 NUMBE NS FOIA 'f7-/d) , yes k RE SPONSE 1 YPE / 1 h RESPONSE TO FREEDOM OF l FINAL % PARTIAL JM 3 INFORMATION ACT (FOlA) REQUEST DA1E ese../ W.2E W DOCKET NUMBE FqS)(If apphcatile/ REQUESTE R A W / 4 ART I.-AGENCY RECOF3psRELEASED OR NOT LOCATED (See checkedboxes) l No agency records subject to the request have been located. No additional agency records subject to the request have been located. Requested records are available through another public distribution progrkm. See Comments section. Agency records subject to the request that are identified in Appendix (es) are already available for public inspection and copying at the NRC Public Document Room. 2120 L Street, N.W., Washington, DC. Agency records subject to the request that are identified in Appendix (es) are being made available for pubhc inspection and copying /Y at the NRC Public Document Room,2120 L Street. N.W., Washington, DC,in a folder under this FCIA number. The nonproprietary version of the proposal (s) that you agreed to accept in a telephone conversation with a member of my staf f is now being made available for public inspection and copying at the N RC Public Document Room,2120 L Street, N.W., Washirgton, DC, in a folder under this FOI A number. Agency records subject to the request that are identified in Appendix (es) may be inspected and copied at the N RC Local Public Document Room identified in the Comments section. Enclosed is information on how you may obtain access to and the charges for copying records located at the NRC Public Document Room,2120 L Street, N.W., Washington, DC. j Agency records subject to the request are enclosed. Records subject to the request have been referred to another Federal agency (ies) for review and direct response to you. i Fees You will be billed by the NRC for fees totaling $ You will receive a refund from the NRC in the amount of $ In view of NRC's response to this request, no further action is being taken on appeal letter dated , N o. PART 11. A-INFORMATION WITHHELD FROM PUBLIC DISCLOSURE Certzin information in the requested records is being withheld from public disclosure pursuant to the exemptions described in and for the reasons stated X. in Part 11, B, C, and D. Any released portions of the documents for which only part of the record is being withheld are being made available for public InspIction and copying in the NRC Public Document Room,2120 L Street, N.W., Washington, DC in a folder under this FOI A number, COMMENTS // C y V Dft Q FREED 04INF MATION AND PUBLICATIONS SE RVICES . p' RE,DIRECTOp Q w ?$iek.j@un,h f@' .wtW y s. Of R

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^" RESPONSE TO FREEDOM OF = INFORMATION ACT (FOIA) REQUEST FOIA -f/ // 4 b g (CONTINUATl*JN) i l PART 11.8-APPLICABLE EXEMPTIONS Records subject to the request that are described in the enclosed Appendix (es) are being withheld in their entirety or in part under the ] Exemption No.(s) and for the reason (s) given below pursuant to 5 U.S.C. 552(b) and 10 CF R 9.17(a) of N RC regulations. l

1. The withheld information is properly class #fied pursuant to Executive Order. (Exemption 1)

2. The withheld information relates solely to the internal personnel rules and procedures of NRC. (Examption 2) l l3. The withheld information is specifically exempted from public disclosure by statute indicated. (Exemption 3)

Sections f 41+145 of the Atomic Energy Act, which prohibits the disclosure of Restricted Data or Formerly Restricted Data (42 U.S C. 21612165). Section 147 of the Atomic Energy Act, which prohibits the disclosure of Unclassified Safeguards information (42 U.S.C. 2167).

4. The withhold information is a trade secre't or commercial or financial mformation that is being withheld for the reason si indicated. (Exemption 4)

The information is considered to be confidential business (proprietaryl mformation. 4 The enformation is considered to be propnetary information pursuant to 10 CFR 2.790(dH11 The information was submitted and received in confidence pursuant to 10 CFR 2 7C:C2s

16. Thwethheld mformation consists (Exemption $1. Applicabie Privilegii; Dehberative Proceas: Disclosure of predeciseonal information would tend to inhibit ' he open jind franit enchange of ideas essential to the deliberative process t

Where records are withheld in their entirety, the f acts are mentricably intertwmed with the predecisionalinformation There also are no reasonably seJregable f actua! portions because the.elease of the facts would permit an mdirect mouery mto the predecisional process of the agency Attorney work product pnvilege IDocuments prepared by an attornes m contemplation of litigation 6 Attorney client privilege. (Confidential commumcations between en attorney and his/her client.)

6. The *vithheld mformation is exempted from pubhc disclosure because its disclosure would result m a clearly unwarranted mvesson of personal privacy (Exemption 6)

I

7. Th3 withheld mformation consists of records compiled for law enforcement purposes and is being withheld for the reasonist mdicated. (Exemption 7)

Disclosure could reasonably be expected to interfere with an enforcement proceeding because it could reveal the scope, direction, and focus of enforcement afforts, and thus could possibly allow recipients to take action to shield potential wrongdoing or a violation of NRC requirements j from investigators. (Exemption 7 (AD i Disclosure would constitute an unwarranted invesson of personal privacy. (Exemption 7(C)) The information consists of names of individuais and other er= formation the disclosure of which could reasonebsv be espected to revealidentities o' confidential sources. (Exemption 7 (DD OTHER l PART ll. C-DENYING OFFICIALS Pursuant to 10 CF R 9.25tbl and.or 9.25(c) of the U S. Nuclear Rec 'atory Comm ssion regulations, t has been determined that the information w thheld is exempt from pre duction or disclosure, and that its production or disclosure is conti.. to the pubhc emerest. The persOMs responsible for the denia, are tnose afhClats identified below as cenying g officials and the Director. Division ot Freedom of Information and Pubhcat ons Services. Office of Administration. for any den,als tnat may be appea:eo ao the Executive Directr for Operations IEDOL l DENYING OFFICIAL TITLE / OFFICE l RECORDS DENIED APPELLATE OFFICIAL ! Y, b Y m - lmAA $w~/ ,A,o D Y WMM l I / l E, 5 5 2 AS l I l PART 11. D-APPE *.c l'JGHTS l The denial by each denying official identified in Part it.C may be appealed to the Appellate Official identified there. Any such appesi must be made in writmg wathm 30 asys of receipt of thb response. Appeals must be addressed, as appropriate, to the E mecutive Director for Opweoons. to the Secretary of the Commission, or to the inspector General, U S. Nuci aa' Regulatory Commission, Washington, DC 20555, and should clearly state on the envelope and in the letter that it is an "Appeel from an initial FOI A Decas on? l NRC FCM 464 (Part 2)(191) U.S. NUCLEAR REGULATORY COMF4tS$10N L

Re: FOIA-97-154 APPENDIX C RECORDS BEING RELEASED IN THEIR ENTIRETY RQ, DATE DESCRIPTION /(PAGE COUNT) 1. 3/90 Reference material from NUREG/CR-5640, (SAIC-89/1541), " Overview and Comparison of US Commercial Nuclear Power Plants"(14 pages) 2. 12/91 Reference Material from SAIC's Nuclear Power Plants Source Book, Maine Yankee 50-309 (1 page) 3. Undated Calculations related to Small Break Loss-of-Coolant Accident (11 pages) I ) I a

l l o.- Re: FOlA-97-154 APPENDIX D RECORDS BEING WITHHELD IN PART l fEL DATE DESCRIPTION /(PAGE COUNT)/ EXEMPTIONS 1. 12/18/95 Handwritten Note of Steve Lewis of a meeting 12/18/95 (10 pages) EX. 5 2. 12/26/95 Handwritten Notes cf G. M. Longo of a meeting held 12/26/95 (6 pages) EX. 5 i i i i I a 1

UNDATED REFERENCE MATERIAL FROM: NUREG/CR-5640, (SAIC-89/1541),"0VERVIEW AND COMPARISON OF US COMMERCIAL NUCLEAR POWER PLANTS": 3 l 1 1 I I i l 1 P i I

5.4 3-Loon Combustion Encineerine PWR Maine Yankee is the only 3-loop C-E PWR built in the United States. 5.4.1 Reactor Core and Fuel Asses.Wlies The Maine Yankee core is rated at 2440 MWt, with an approved " stretch" rating of 2630 MWt. The core is comprised of 21714 x 14 fuel assemblies, with an active core length of 136.7 inches. Core average power density is 74.6 kW/ liter. 5.4.2 Reactivity Control System The Maine Yankee reactivity control system is comparable to the system in Combustion Engineering pre-System 80 2-loop plants. 5.4.3 Reactor Coolant System In the Maine Yankee RCS, each primary loop is comprised of one hot leg that enters the bottom of a U-tube steam generator, and one cold leg that return flow to the reactor vessel. One reactor coolant pump is in each cold leg, for a total of three reactor coolant pumps. The pressurizer is connected to one of the hot legs. This arrangement is '1 generally similar to that of a Westinghouse 3-loop plant. The Maine Yankee reactor vessel is shown in Figure 5.41, the U-tube steam 1 generator in Figure 5.4-2, and the pressurizer in Figure 5.4-3. 5.4.4 Shutdown Cooling Systems Shutdown cooling is provided by a multi-mode system that also performs the low-pressure safety injection (LPSI) function as part of the ECCS. The shutdown cooling heat exchangers can also be shared by the containment spray system. 5.4.5 Emergency Core Cooling Systems The Maine Yankee ECCS consists of high-pressure and low-pressure safety injection pump subsystems and three safety injection tanks (accumulators). All of these ECCS subsystems inject into the three RCS cold legs. There is no pmvision for injecting into the hot legs as in Westinghouse PWRs (i.e., during the latter phase of ECCS operation in the recirculation mode). The Main Yankee ECCS is significantly different than all other C-E plants in that the HPSI pumps also serve as charging pumps and are capable of providing makeup t the RCS at the PORV setpoint pressure. The HPSI pumps at Maine Yankee cannot be aligned to take a suction on the containment sump. A recirculation flow path can be established with the LPSI and HPSI pumps operating in tandem as in Westinghouse PWRs. In this alignment, the LPSI pumps take a suction on the containment sumt and deliver water to t: ,uction of the HPSI pumps which complete the injection path into he RCS. 5.4.5 Containment The Maine Yankee plant has a large, dry cylindrical containment constructed of reinforced concrete with a steel liner. The general arrangement of the Maine Yankee containment is shown in Figures 5.4-4 to 5.4-6. 5-37 3/90 w--

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==ar l LUS ucma A-A h p j ,g mm u o Figure 5.4-1. Maine Yankee Reactor Vessel r l-I

.7' 1 t s l i l Steam 1" Eight Banks of PEED)lATER INLET N0ZZLES l Outlet instrument \\ NozzW '" Steam Dryer i vanes -28 3-inch 90 elbows-SCH. 80 j All nozzles and drains in 1 . M Sless { 3eparders bottom of ring header have DWiector been blocked. Secomlary team { )[\\ / / / i T_ C vb5%"'"' I Normal l "II' l l water -I L*"' N4 A N# fl p,i,,, l [ \\h En fe 'a**'aat 187-vr ao -- l g/- EYr4 :... ....V py V l i / nitru /; sws i Fr ao l Neule sm.my --' \\ / j,Handhels w w 1 l o.- sien. l Bloudous a omm flattle m-vr omr.n a. $$3'Y z*- p Priewy tage Noam """*r IW headwy j view e-8 Hauhk ( j l n A ip Secondary N-- / Orsin ' (.s; h W i, Marsei. 41 lb V Nank M2s T V/##M sottom sn-i

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1 Table 5.5-1.. Design Parameters for Representative Combustion Engineering PWRs REACTOR FLANT C.E C.E C.E CHARACTERISTICS

2. LOOP PLANT

2. LOOP SYSTEM 88 PLANT

3. LOOP PLANT SAN ONOFRE 2 AND 3 FALO VERDE I,

2. AND 3 MAINE YANKEE i

O perell Nwnber of loops 2 wiehout isolmion 2 widious isolmson 3 wahout isolamon 1 O Dennel r=pacey 3930 M Ws 3800 M Wt 2630 MW Deeric capaaty I a 1070 MWe / I a 1080 MWe 1221 MWe 810 MWe Elficuncy (net) 27.35 % 32 13 % 30.80 % Coolant pressee un pnmary crcast at exit frcen reacsor 2235 psig 2235 psig 2235 psig Content tesupsakre at inlea 553*F 564.5'F 538.9 F Coolse amigerature at ena frcen reassor 6t l.2*F 621.2*F 592.8'F Coolant flow rese through rescaers (tonal) 148 E6lbAv 164 E6 bhe E6i Core N Ileight of acssve core 12.5 ft. 12.5 ft. 11.39 ft. i 1 Egsivales &arnener 13.33 ft. 11.97 ft. 11.33 ft. Number of fuel assembises 217 241 217 Number of control rods assenblies 83/8 76 85 Nanber of fuel elemmes in assenbly 236 236 166 Dianmer d fuel elamma 0.325 in. 0.382 in. 0.3793 in. L Area of heat vansfer meface 62.000 sq.ft 68,600 sq11. 47,000 sq fL. Mean spects heat than 182,400 BeuAr.sq.ft 182,400Baalhr-sq.ft. 182,460 Btu /hr-sq ft. Number of fuel rods 49,580 58,876 36.352 Ccee loadng 3 bandi mtmed central aane 3 batch mined omeral mone 3 beach rnized censral anne Average bumig(rena cyde) 12,731 mwd /MTu Unit. 13.795 MW4Mns Fuel weigla (as UU2) 233,900 lbs. 257,100 lbs. 203,934 lbs. l 4O b i

Table 5.5-1. Design Parameters for Representative Combustion Engineering PWRs (Continued) l REAUTUR FLANT C-E C-E C-E CHARACTERISTICS 2-LOOP PLANT 2-LOOP SYSTEM 88 PLANT 3-LOOP PLANT I SAN ONOFRE 2 AND 3 PALO VERDE 1, 2. AND 3 P %INE YANKEE I Ie 3 er Veseal Vessel heWa 43.54 ft 48 ft 42.11 ft. buur eissneser 14.33 fL 15.19 ft. 14.33 ft i Nwnter of Opegs for inlet and audes nozzles 2a2 2a2 2a3 5seems Genermer Neuber of waits 2 2 3 1hermal power per unit 1965 MWs 1900 M Wt 813.3 MWt Shell side opersamig presswe (seesm) 985 pag 1055 psig ( 885 peg w-Tube side opersung pressee 2235 pois 2235 psis 2235 psig Tube side design flow 74 E6 IWhr 82 E6lbAir 40.67 E6 IWhr Firing lies leg ismier dia. 42 in. 42 irL 33.5 in. Cold leg iruur dia. 30 in. 30 in. 3L5 in Besween purnp and seenrn gaursnor 30 in. 30 in. 33.5 in. Safety Valves First apesung pressure 2485 psig 2485 psig 2485 psig Capaaey Unk.endiof 2 Unit each of 4 228,I00ItWhrendiof 3 i 57 IWhr/MWs eachIMVof 2 ? Friamary Cee&ans Fnaspe Nusnber 4 4 3 Pump y*y 111.400 gym 108,000 spin 88,000 spers Coolamiempersome 553 T 564.5 7 538.9 T Pressure rise 310 fLhead 363fLhead 290 fLhead j Design presswe 2500 psia 2500 psia 2485 psig C Design ternperamme 650 7 650"F 650 T i Moser reung(nameplane) 9,700 1. I2,000 hp. 9,000 hp. 9 I

Table 5.5-2. Comparison of Combustion Engineering PWR "essel and Core Parameters

e PWR PWR Reactor Plant Core Reacter Core Core Core Average Number Fuel Number of Vendor Type Nome Power Vessel Equivalent Active Power Donelty of Fuel Element Control Rode (MWt1 1.D.

(In) Diem. (In) Heleht (In) (h W/llte r) Elemente Geometry (Fto"Part Length) C-E 2-loop Fort Calhoun 1 1420 140 106.45 128 80.40 133 14 x 14 45 F/4 P C-E 2 loop Pahsades 2530 172 136.7 132 79.80 204 15 x 15 41 F/4 P C-E 2-loop Calvert Cliffs 1 & 2 27sJ 172 136 136.7 78.5 to 82 8 217 14 x 14 77 F/ 8 P C-E 2-loop Mdistone 2 2560 172 136 136.7 78.50 217 14 x 14 73 Fm P CE 2-loop St Luce 1 2560 172 136 136.7 83.20 217 14 x 14 73 F/8 P C-E 2 loop St Lucie 2 2560 172 136 150 83 20 217 16 x 16 73 F/8 P C-E 2-loop ANO2 2815 171 123 150 96.60 177 16 x 16 73 F/8 P tA C-E 2 loop San Onofre 2 & 3 3390 172 136 150 94.90 217 16 x 16 83 F/8 P h" C,E 2-loop Waterford 3 3390 172 136 150 94.90 217 16 x 16 83 F/8 P C-E 2-loop Sys 80 Palo Verde 1,2 & 3 3800 182 143.6 150 95.60 241 16 x 16 76 r/13 P C-E 3 loop Mane Yankee 2630 174 136 136.7 74.60 217 14 x 14 77 F/8 P WD o _.,._..__.-_m.__._____-._.__-__.-_________._____m_- a -m

_w.% 3' Table 5.5-3. Combustion Enginct .g PWR System Comparison - RCS, AFW, Charging and HPSI t neem.,y ee e sy se Cw.ine sy.iem av Pre = wi.e..,s.em eete, C- .,s. ore I 80808 Co,e e RCS e MCS siG e A,W Type Capseny e Type : Cepest cepe4 sty e Type Capecity Cepecety Plant Name Vender WW1 Lesme POEV/SV Model Pusese D,8ve mese S mais Pumme Puma amm & ' som S M r Ptsame Pues mese S me;.;a aam S PORY No.es 44 3 Care 300 $ 1214 0 /A AN42 C-E 2015 2 012 UT 1 M 575 @ 1214 3 PO 44 o 1 - T 575 e 1214 Cervert CWie 1 & 2 CE 2F00 2 2/2 UT 7 T F00 91100 3 PD 44 44 3 Cerg 345 9 10s4 0 Fort Carmun C-E 1420 2 212 UT 1 M 200 @ 10e0 3 PD 40 40 3 Core ISO @ 1214 0 1 T 2e0 S 1040 .ams,e Yersee C-E 2030 3 2/3 L, # 2 M 500 $ 1100 3 Car ( 150 $ 2950 150 Same os energmg p qgg i T 500 S 1100 1 PO 5G 30 amessono 2 C-E 25eo 2 ft2 UT 2 M 300 $ 10ee 3 PD 44 44 3 Core 315 @ 10e4 l 0 1 T e00 e toss C-E 2530 2 2/3 UT 1 M 415 9 Ite3 3 PD 40 40 3 Cars 300 910e4 0 (g) 1 T 415 e 1103 Pese veros 1. 2 & 3 C-E 3000 2 ove UT I M F50 @ 1422 3 PD 44 N/A 2 Care e14 @ 123J 0 i T 750 e 1422 Sen Onales 2 4 3 C-E 3300 2 0#2 UT 2 M seo @ 1232 3 PD 44 44 3 Core 415 @ 122F 0 t T 300 S 1232 Ss. Luce t & 2 C-E 2560 2 2/3 UT 2 M 250 @ 1200 3 PD 44 44 3 Core 345 9 tose 0 1 T 500 S 1200 waterford 3 C-E 3300 2 012 UT 2 M 350 $ 2673 3 PO 44 @ 2324 44 3 Care 3eo @ 1227 0 y i T M S MM g i WDo e b 4 _,_______.___.___.____.________._._____.-_________._____.._____.___.___.__________.____.______.__m___ m m

. m... s+1.=_;;;rrW %._r___ P M ?d ! m_ -.-. _.7t -u g i 3 Table 5.5-3. Combustion Engineering PWR System Comparison - RCS, AFW, Charging and HPSI-I -(Continued) General Note: All pump capacities are stated on a per-pump basis. AFW pump capacity is stated in terms high pressure injection pump capacity is stated in terms of rated capacity and approximate cap! the PORV setpoint (i.e. for " feed and bleed" operation). Codes used in this table include: Type drive: M = elec:r.c motor T = steam turbine Type pump: PD = positive displacement Cent = centrifugal i RCS PORV/SV: number of RCS power-operated valves (first number) and safety valves (second number). {' S/G model: UT = U-tube o OT= once-through i 4 Notes: 2 i (f) Maine Yankee has a variable capacity auxiliary charging pump (10 to 30 gpm) in addition to pumps. i (g).At Palisades, two charging pumps are fixed capacity and one is variable capacity. 'Ihe turbin Palisades is not safety related. t i w 8 l i l i t . I

-~ Table 5.5-4. Comparison of Combustion Engineering PWR Pressurizer Relief Capacity NSSS

RCS Ma nu f act ure r Capacity Lowest
RCS Capacity Lowest Plant Name Vendor PORV's (lb/hr/MWt)

Setpoint (psla) SV's (KIb/hr) Setpoint (psig) ANO-2 C-E 1 Nore 2 280.6 2500 Calvert Cliffs 1 & 2 C-E 2 Dresser 56.7 2385 2 222.2 2485 315 33VX Fort Calhoun C-E 2 Dresser 69.7 2392 2 281.7 2485 315 33VS Maine Yankee C-E 2 l'. sser 57 2385 3 228.1 2485 315 ;t3VS-30 Millstone 2 C-E 2 Dresser 59.8 2380 2 231.3 2485 315 33VS-30 Palisades C-E 2 Dresser 60.5 2385 3 272.7 2485 315 33VX Palo Verde 1,2 &3 CE O Nons 4 Unk. 2485 w* tn San Onofre 2 & 3 C-E O Nore 2 Unk. 2485 ~ St. Lucie 1 & 2 C-E 2 Dresser 59.3 2385 3 234.4 2485 315 33VS-30 Waterford 3 C-E O None 2 420 2485 Kib/hr rating wD o t m.

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agr-e y. _m t l Table 5.5-5. Comparison of Combustion Engineering PWR Containments } NSSS A rc h./ Prim. Concrete Internet Contelnment Doolen Design - Enclosure Plant Nome Vendor Engineer Cont. Construction Construction Diameter Free Volume Pressure Leek Rete Building? Type Subtvoe fleet) f f t3) (sola) % vol/ der ANO-2 C-E Beechel Dry Concrete Cyhnder w/ 3-D 116 1.78 E + 06 54 0.1 m Steel Liner Prestressed Calvert Cht!s 1 & 2 C-E Botchel Dry Conaete C)" e w/ 3-D 130 2.00E + 06 50 0.33 m W Steel Liner Prestressed i Fort Calhoun 1. C-E Gbbs & Dry Concreto Cvise w/ 2-D Dia0 110 1.05E+06 60 0.2 m Hill Steel Liner Prestressed Mane Yankee C-E Stone & Dry Concreto C);se w/ Reinforced 135 1.86 E + 06 55 0.1 m i Webster Steel Liner Millstone 2 C-E Beechel Dry Concreto Cy;se w/ 3-D 130 1.92E + 06 54 3 yes A Steel Unor Prestressed Pahsades C-E Beechol Dry Concreto Cy;se w/ 3-D 116 1.60 E + 06 55 0.2 m I Steel Liner Prestressed Paio Verde 1. 2 43 C-E Beechel Dry Concreto Cyhnder w/ 3-D 146 2.60 E + 06 60 unk. m Steet Liner Prestressed San Onotre 2 & 3 C-E Beechel Dry Concreto CyLe w/ 3-D 150 2.34 E + 06 60 0.3 m i V' Steel Liner Prestressed d St. Lucie 1 & 2 C-E Fhemm Dry Steel Cyhnder 140 2.50 E + 06 44 unk. Yes Wate ivid 3 C-E Fhamm Dry Steel Cyhnder 140 2.68E,06 44 0.5 Yes i I 8 + l I

^ Table 5.5-6. Comparison of Combustion Engineering PWR Backup Electric Power Systems Shared Dedicated Continuous

of NSSS Diesels Diesels Rating Diesel Batteries Reactor Plant Vendor per Plant per Unit (kW)

Manuf acturer per Plant Voltage Notes ANO-2 C-E None 2 2850 Fairbanks-Morse 3 125 Calvert Cliffs 1 & 2 C-E 3* 2500 Fairbanks-Morse 4 125 'One diesel is swing between units Maine Yankee C-E None 1 250 unk. 4 125 2 2500 Gen. Motors Millstone 2 C-E None 2 2750 Fairbanks-Morse 2 125 Palsades C-E ftne 2 2500 Ako 2 125 Palo Verde 1,2 & 3 C-E ftne 2-5500 unk. 4 125 'i San Onofre 2 & 3 C-E tene 2 6000 DeLavale 4 125 tn St. Lucie 1 & 2 C-E None 2 3500 Gen. Motors 2 125 Waterford 3 C-E None 2 4400 unk. 3 125 i w

. - - ~ Table 5.5-7. Comparison of Combustion Engineering PWR Power Conversion Systems P NSSS Architects TurWne Gen. TurWeve Gypees Consoneer sceneet a teein FW FW Puenp Stutoff Head Cepecsty Pione Nenne Ventler Enaineer Cenetructor Cas. (IfWe) Casability t%) Ceeena Twee Hoot sent Pumee Ortve Tyse fasial taomt ANO2 C-E Bechtet Sectaal 858 32 e w toop Peat. Ceehng Tooer 2 turwne 1,170 14.500 Ca# vert CW?s 1 & 2 CE Bechtes Bectnel 825 40 Once Through CW ar=== Bay 2 (50%) turbme 1.174 15.000 ro,1Caroun 1 C-E Gbbe & He Gbbs 8 Hg 418 unk. Once Through h6secun Arver 3 AC 1.021 8.000 6 754 pea m Yanswe C-E Seons & Sone a 810 50 Once fhrough

.^
Boy 2 (60%)

AC 1.543 14.000 webster webster eiO3i.a j omastone 2 C-E Bectdel Bactsel 857 43 Once Through tearac 8ay 2 (55%) turbee 810 15.000 p* =a== C.E Bechtet Secreel 130 5 Casedtsco Moch. Coahng ioners 2 turbine 1.144 13.500 @t144 os.a PWo Verde 1. 2 & 3 C.E Bechtel Bechtet 1333 55 r w Leap Moch.Coahn8 owers 2 (85%) turkne unk. una. i T San Onotre 2 & 3 C-E Bechtet Bechest 1080 unk. Once Though Pacdc Ocean unk-unk. unk. unk l St. Luce 1 & 2 C-E Ebmaco h 838 5 Once Through Amores Otw 2 AC unk. unk. Waterford 3 C-E P==na h 1075 83 Orun Through heesseggu R,wer 2 (63%) turtune 1,18 ', 11.940 u l o 932 se a l bt A r + P I t>>Do i l f I

t 4 6 EFER f4CE MATERIAL FROM SAIC'S NUCLEAR POWER PLANTS SOURCE BOOK, MAINE YANKEE, d/ 1

J Maine Yankee 3.4.4 System Success Criterin LOCA mitigation requires that both the emergency coolant injection and large LOCA are the following (Ref.1): emergency coolant recimulation func l 2 of 3 safety injection tanks provide makeup as RCS pressure drops below tank I pressure, and One HPSI (charging pump del' vers 67% ofits rated flow to the RCS, and One low pressure sa)fety injection pump delivers 67% of its r RCS. If the ECI success criteria are met, then the following large LOCA ECR success criteria will apply (Ref.1): At least one high pressure safety injection pump is realigned for recirculation and takes a suction on the containment sump and injects into the RCS cold legs. l Success criteria for a small LOCA are not clearly defined in the FSAR: however, it should be noted that the HPSI pump shutoff head is greater than normal RCS operating pressure since they also function as charging pumps. Also, the FSAR mentions l that the total capacity of the HPSI pumps is enough to maintain system RCS coolant inventory and pressure for a break equivalent to a 1 1/2" diameter break (Ref.1, Section 6.2.2). 3.4.5 Comnonent Information l A. High Pressure Safety Injection n., s 14AJ4_Batqd 14S (spare) J B

1. Rated flow:

2. Ratedcapacity:150g-0 ft head (1,235 psid)~

~ 1

3. Type: horizontalcentrifugal B. AuxiliarychargingpumpP7

1. Rated flow: 10 to 30 gpm @ 2,300 psig I

2. Type: variable speed positive displacement

3. Design pressure: 3,700 psig C. Low Pressure Safety injection pumps 12A and 12B I

1. Rated flow: 3,000 gpm @ 350 ft. head (152 psid)

2. Rated capacity:

3. Type: venicalcentrifugal100E _ _ g 7 44;

4. Shutoff head: 440 ft.

D. Safety injection Tanks (3)

1. Volume: 3500 ft3 l

2. Minimum water volume: 1,500 ft3

3. Normal operating pressure: 225 psig i

4. Minimum boron concentration: 1,720 ppm E. Refueling water storage tank

1. Capacity: 375,600 gallons 3l

2. Minimum allowable volume: 300,000 gallons

3. Design pressure: Atmospheric

4. Boron Concentration: 1,720 ppm 3.4-2 12S 1

i 4 i CALCULATIONS RELATED TO SMALL BREAK LOSS-0F-COOLANT ACCIDENT: l i l. I i I i r V\\

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i FOINPA REQUEST ~}~? ? M:o Ho: il-LS 4/ l-J Tc Roc'd: 9l 4i [MI l'cton 0;: V4d Dcacd Cc:3: ATTORNEYS 4 3 DAVID E. BARRY April 30,1997 y E+ M Alt, VIA UPS OVERNIGHT MAIL DBarrve PmAtmiam Director, Division of Freedom ofInformation and Publications Services l Office of Administration U.S. Nuclear Regulatory Commission Washington,DC 20555 Re: Freedom ofInfonnation Act Reauest

Dear Sir or Madam:

Pursuant to the Freedom ofInfomiation Act,5 U.S.C. 552, and the Nuclear Regulatory Commission's implementing regulations,10 C.F.R. Part 9, I hereby request copies of or access to any information, including but not limited to: notes, letters, memoranda, drafts, minutes, diaries, logs, calendars, tapes, transcripts, summaries, interview reports, procedures, instructions, analyses, drawings, files, graphs, chalts, maps, photographs, agreements, handwritten notes, studies, data, notebooks, telephone messages, computations, interim and/or final reports, status ) reports, and any and all other records or documents related to and/or generated in connection with: 1 The Yankee Atomic Electric Company RELAP5YA emergency core cooling system (ECCS) evaluation model;

2. Application of the RELAP5YA ECCS evaluation model to the Maine Yankee plant;

3. Three Mile Island Action Items II.K.3.30 and II.K.3.31 as applied to the Maine Yankee plant; and One Monument

'4. The 2630 MWt power uprate for the Maine Yankee plant and the 2700 Portian taine onol-iuo MWt power uprate for the Maine Yankee plant. j voict 207,791.1100 FAE 207.791.1350 E* M All - infv*herceAtwood.com. & ji $_O N

.I'~ -s . Director, Division of Freedom ofInformation and Publications Services l April 30,1997 ) Page 2 Pursuant to 10 C.F.R. 9.23(b)(4)(i)(C), I specifically accept the cost involved in l searching for and duplicating the information I have requested, and do not require advance notice l-of costs exceeding $25. l t I look forward to hearing from you within the ten days required by statute. ery truly yo rs, \\ f gh ( i David.I. Barry i i DEB:bjf l i i I l' 1 l l t I-l i}}

ML20151K341