ML19263A964
| ML19263A964 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 12/18/1978 |
| From: | Whittemore F HUNTON & WILLIAMS |
| To: | |
| Shared Package | |
| ML19263A941 | List: |
| References | |
| NUDOCS 7901040016 | |
| Download: ML19263A964 (26) | |
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. 12/18/78
- MC PUBLIC dog ,,. ,.. ... , _
-.-.. , _ r UNITED STATES OF AMERICA s @M 'Os s
NUCLEAR REGULATORY COMMISSION N 33 e v+ b h ,- Before the Atomic Safety and Licensing Board C Q ,@' L k N % In the Matter of ) . M ./ , . , ,
) .s\/
LONG ISLAND LIGHTING COMPANY ) 'on t #
) Docket No. 50-322 (Shoreham Nuclear Power Station, )
Unit 1) )
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Motion for Summary Disposition of SC Contentions 4a(vii) and 7a(ii)
- 1. Suffolk County (SC) contentions 4a(vii) and 7a(ii) were accepted by the Board only for purposes of discovery be-cause they wcre insufficiently particularized.1/ SC conten-tion 4a(vii) is as follows:
4a. Intervenors contend that the Applicant and Regulatory Staff have not adequately considered individually a number of generic light water (re-actor] safety issues raised by NRC staff members and applicable to Shoreham in accordance with the backfitting requirements of 10 CFR Part 50.109 and/or the general design critaria of 10 CFR, Part 50, Appendix A. This contention includes . . . 2/ the following design features for structures, sys-tems, and components:
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vii. Interpretation of NRC General Design Criteria [ sic] 19, " Control Room." SC's Amended Petition to Intervene at 4 (Sept. 16, 1977). And
]./ See Board Order of March 8, 1978 at 2; Tr. 72-73.
2/ This ellipsis represents language deleted by the Board. IIee Tr. 72-73. 79010400/6
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SC contention 7a(ii) reads: 7a. Intervenors contend that the Applicant and Regulatory Staff have not adequately de-monstrated that the Shoreham nuclear system meets the requirements of 10 CFR, Part 50, Appendix A, General Design Criteria for Nuclear Power Plants, with regard to the de-sign adequacy of the following system and response characteristics and/or criteria:
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ii. Criterion 19 requires equipment be p'rovided outside the control room with the design capability for prompt hot shutdown of the reactor, including necessary instru-mentation and controls to maintain the unit in safe condition." This ccpability has ~ not been adequately demonstrated. Id. at 10.
- 2. These contentions were clarified in SC's Response to Applicant's Second Set of Interrogatories at 20 (Jan. 31, 1978) and SC's Particularized Contentions at 4-7, 7-3 (Nov.
30, 1978). From these documents it appears that these con-tent! .s are virtually identical and that they are raising the following issues:
- a. That the description in the FSER regarding the remote shutdown capability is cursory and incomplete;
- b. That the remote shutdown procedures are inade-quate;
- c. That the remote shutdown capabili.y may fail due to system interactions; and
- d. That the Shoreham design does not meet the re-mote shutdown requirements in 10 CFR, Part 50, Appendix A, Criterion 19.
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. 3. For the following reasons, these contentions raise no material issues of fact:
- a. Contrary to SC's allegation in the first of the above issues, the FSAR adequately describes Shoreham's remote shutdown capability. See FSAR SS 3.1.2.19 , 7.4.1.4, 7.4.2.4, and 7.5.1.5. In addition, specific design details of the re-mote shutdown panel were provided in LILCO's responses to Staff questions. See LILCO letter SNRC-252 from Mr. T. J. Burke to Mr. K. Kniel, Attachment 3 (Jan. 31, 1978): LILCO letter SNRC-344 from Mr. J. P. Novarro to Mr. H. Denton, response to URC ques-tion Ell (Dec. 11, 1978). The pertinent parts of these letters are attached to this motion.
- b. SC's second issue, which alleges that LILCO's remote shutdown procedures are inadeqdate, is also incorrect.
The remote shutdown procedures are adequate as described in da-tail in FSAR S 7.5.1.4.5. See generallv id. S 7.5.1.4. Furthermore, the adequacy of these procedures'and the remote shutdown capability will be demonstrated during startup and power ascension testing, as described in FSAR S 14.1.4.8.25.
- c. In the third issue, SC alleges that the remote shutdown capability may fail because of system interactions.3/
3/ SC attempted xo support this allegation by citing Task Ac-tion Plan A-17 in NUREG 0410, which addressed the question of system interactions. SC's Response to Applicant's Second Set of Interrogatories at 20 (Jan. 31, 1978). However, Task Ac-tion Plan A-17 identified no specific system interaction prob-lem that concerned the remote shutdown capability.
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The remote shutdown panel is designed so that once the con-trols and instrumentation are transferred to the remote panel, they will operate independently (without interaction) of the main control room. See Affidavit of G. R. Heine II at 7 5.
- d. Contrary to SC's fourth issuc, the Shoreham de-sign meets the requirements of Criterion 19 for the following reasons:
(1) The remote shutdown controls and instru-mentation are located in an area physically isolated from the normally-used control room. (2) The remote shutacwn controls and instru-mentation have the capability to accomplish a prompt hot shat-down of the reactor. (3) Equipment is located at appropriate points throughout the plant to permit the reactor operators to accom-plish a cold shutdown using suitable procedures. As to all three of these reasons, see Affidavit of G. R. Heine II.
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- 4. For the above reasons, Shoreham's remote shutdown capability is adequate and complies with Criterion 19. There-fore SC contentions 4a(vii) and 7a(ii) raise no genuine issues of fact. Accordingly, under 10 CFR S 2.749, they are ripe for surmnry disposition in favor of the Applicant. We request that disposition.
Respectfully submitted, LONG ISLAND LIGHTING COMPANY
/ f' DATED: December 18, 1978 F. Case Whittemore Hunton & Williams P.O. Box 1535 Richmond, Virginia 23212
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January 31, 1973 SHnc-252 Mr. Karl Knici, Chief Light ! Tater N.3 actors Granch 2 Division of Project .'ianacjorr.cnt Of fico of ?Iuclear Regulatory Conmission
*1as53ugton, D. C. 20555 S horehar.t :uclear Po*7er Station - Unit 1
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C._oc::o t' '.'o . 30 _'32_2~~~~~~ _ =
Dear Mr. I'niel:
Enclosed is infornation provided as a recult of the '.mC fire protection plant visit conducted on Novenbor 15-17, 1977. As a result of discuccion: hold Curing the vicit and the
'in.C review of our Fire Hazard Analycia necert, we are providing '
five (S) copics of the following information:
- 1. Attachment #1 - Responses to sp.'cific questions raised during the visit.
- 2. Attachment
- 2 - Overview of the 3:iPS Fire Pro tection Progran. .
- 3. Attachment 13 - Remoto Shutdown Panel.
In addition, uo have included or copy of drawing: FE-273, FE-27A and a Functional Diagram s f the Fire Dc cction/ Protection. This information docuncnts our position on the various issues discusced durine the visit and clarifics in foruation aircady contained in the Fire Hazard Analysis naport. Very truly yours,
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T. J.- Burio, cc: H. Chau Project ' tanager Dist. List #14 Shorcham '!uclear Power Station Eng. File #A21
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.. F 2-ATTAC'IMENT 3 REMOTE S!!!'TDONN PANEL
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- INTRODUCTION
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The Remote Shutdown Control System provides remote control for the reactor systems needed to carry out the shutdown function from outside the main control room. This system includes the Remote Shutdown Panel (RSP) IC61*PNL-001.
. Normal reactor cooldown is accomplished by controling the various system components from the Atain Control Room. The RSP provides an alternate location from which a reactor cooldown operation can be conducted if the Main Control Room becomes uninhabitable. Cooldown can be accomplished from the RSP when feedwater is unavailable and the reactor is isolated from its normal heat sink, the condenser.
The Remote Shutdown Control System is not designed to be operated coincident with a Loss of Coolant Accident condition. ANALYSIS OF DESIGN The following sections of the FSAR pertain to the Remote Shutdown Systen Instrumentation and controls:
- 1. Sections 7.4.1.4 through 7.4.2
- 2. Section 7.5.1.4 a Section 7.5.1.5 4 Ficures 7.4.1-5A through E
- 5. Figures 7.4.6A and B The operator has the capability to control various components of the following systems from the RSP. Table I lists each component with its corresponding transfer switch and control switch.
- 1. 1321: Nuclear Roiler System
- 2. 1331: Reactor Recirculation System
- 3. lE31: Residual IIcat Removal (RIIR)
- 4. 1E51: Reactor Core Isolation Cooling (RCIC)
- 5. 1G41: Fuel Pool Cooling System (FPCS)
- 6. 1P41: Service Nater System (S"S)
- 7. 1P42: Reactor Building Closed Loop Ccoling Mater System (RSCLCMS)
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TABLE I
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RE140TE SHUTEC'..'II pat!EL 1C61*P!;L-001 COMPO:fE:IT TIV tlSFER .
!.i:D C0t! TROL SWITCH TAEULAT.TO?;
[ n ... m . w , u o.... Cv.anOL COMPOIIEUT TRAIi3FEP ." WITCH
, . . SWITCH (CS)
.., w Reacter RV S-15 S 48 1321*EV-002C .
Recctor RV S-15 S-49 1321*RV-092D Reactor RV S-15 S-61 1321*RV-092F Reactor Rdeirc. Pump 3 Suction S-16 S-50 1331*MOV~00.13
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PRES P'r.p ' S-9 S-31 1 Ell *P-OllG -
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PRR Pump B Suetien S-9 O-32 1 Ell *MOV-0313
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PRR Shutde.:n Cooling S-2 S-33 1E11*MOV-032A ]
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EHR Shutdoun Ccoling S-1 S-34 1 11 *MOV-0323 FRR Shutde.-. Ccoling S-2 S-47
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lEll*? TOV-0320 RER Shutdcun Cooling S-1 S 41 lEll*MCV-032D -
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.=u.~a .=.~.sc:'. . a. _n _ s a a- e -.._ c ~o S _n .'.- a - *n 'o 1E11*MOV-0333 RER HX Shell Side Bfpan: S-14 S 25 !
1E11*MOV-0 '.3
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FRR HX Shell Side Cutlet S-12 S-40 1EllW.CV-0 53
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RHR Catboard Injection S-13 S-42 1E11+:M0'7-00 E B
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TADLE 1 (CO:IT'D.)
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. REMOTE SHUTCC';IN PAMEL 1C61*P!it-001 CCMPCM7.UT TibMISFER AMD CO?! TROL S' DITCH TASUU. TION I;'. "n . :mn n . :;
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- Ta'.A;..W ::: 3 c."1Tc;I CWITcII (CS)
COMPC:.2NT (HST.O l FR? Inboard Injection S-12 S-39 lIll*MOV-0373 S-57 S-56 FRR Dn .rall Snrav. Outboard 1E11*M07-03dB'
?RR S? Snre.?? /: Coolint; S-13 S h4 -
1 Ell *MOV-0403 FRR SP Snr?.it S-57 S-58 1211*MOV-OulB RHR S?. Cooling S-ll S-37 lI11*MOV-Oh?3 - PRR HX Drain to RCICS S-11 S-38 lEll*MOV-0333
?RR HX Drein to SP S-ll S-36 1 Ell *"0V-044B PRR Shutdo.in Cooling Suction S-78 S-51 1511*MOV-Oh?
FER Shutdcwn Cooling fuction S-77 S-35
., IIlleMOV-Ohd S-10 S-64 RHR Crocs Hecdcr Shutoff 1 Ell *MOV-O'O -
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FRR C nbcard He.?dspray C-1 S 43 1 Ell *MOV-053 RHR Inbosrd Headspray S-78 S-63 1 Ell *".07-054 RCIC Scrc=etric Condenc.'r Vacuum Pump S-6 S-30 1551*?-076 ROIC Baremetric Condencer Condennete P':mp :-6 S-29 lE:1>P-077
?.CIC ?.:np Luction Cendensnte Utorage T nk S-3 S-21 1E:1 +"O7-0 1
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c..;!; .:U.. n .v b .'.. . a re . > a _2 .. . CO'.;T ROL RDtOT: SiOTLC'.RI TRAM:,W.E .T.! ITCH S'.! ITCH (CS) CCMPONENT ( F^ ?r. ) S-3 S-22 RCIC Pump Suction SP 1E51*MOV-032 S-52 S-54 RCIC Fump Discharge i lE51*MOV-03h . S-52 S-53 RCIC Pump Dischcrge lE51*MOV-035 .
- RCIC Pu:$[ Minimum Flow Lypass S-52 .
5-55 _ lE51*:10V-05,6 - . RCIC Pump Discharge to Condensate Sh S-23
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S crece Tank - 1E51*MOV-037 S-5 S-26 RCIC To Lube 011 Cooler I 1E51*M07-018 S-17 S-19 RCIC Stccm to Turbine 1E51*MOV-Oh1 S4 S-24 s RCIC Stcan to Turbine i i
1E51*MOV-Oh2 S-5 S-25 RCIO Stea= to Turbine
- 1E51*MOV-Ou3 I
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S-5 5-28 RCIC Titrbine Stop Valve . 1251*M07-034 - RCIC W rbine Ey.haust to S? S-3 S67 1E51*MOV-Oh; I S-79 i S-c0 RCIC Vacuu: Pump Discharce to S? l~ 1EE1*MOV-Cu6
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S-17 S-62 II51*MOV-041 Dypass IE52*MOV-Oh7 l S-79 S-20 RCIC Turbine Rxhaust Vacuum Drcaker 1E51*MOV-Oh9 S-83 S-Th FFCS Pu:. 1Ghl*?-02 0.3 -. M
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TA N.M 1,(CONT'Dd RE!10TE .*iitUTD0'!!T PATIF.L 1C01 X"i!f.-001 "* : C'i 'f!T TP.AIISFER AND CO:: TROL SWITCit TArUTJ.T:'0:I FIMOT.: SIUiTDC'dU CCMTRCL CCM?OliENT ThA::SI .:H :.~.IITCli SWITCH (CS) (k3TC)
!; PO S-71 SWS Puno 1Phl*P-CO3B SMS Pump S-81 S-72 1?al*P-003D
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SW Pump 3 DischcrCc 0- P.O S-65 1Phl*MOV-031B S*.T Pump p Di::cherco S H1 S-67 1?c.1*MOV-031D . S fig
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Service Unter *Iecdei- S-82 i IPhl*.' ICV-0923-
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RER HX 1E11*3-0343 Dischnrce S-57 S-59 l?hl*MOV-0343 To TECLCW HX S-82 S-66 1P41*"OV-0353 RECLC'.T EX Discherge S-82 S-68 1?al*MOV-0373 RECLOW Dump 3-80 S-71
< 1?!'.2 *P-00 SD R3CLCW EX E-ll3 Inict S-83 S-70
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l?u2*MCV-04P3 , , i EHRih.CShellCutlet S-8 II/eA j CI-Ol$ i. S-8 N/A d RHR 31ain Flow ;l
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RCIC Flou Indicator Controller S-7 N/A fj i
*FIC 001 (GF.) ,
S-7 G/A v RCIC Turbine Soced ' I
- I R-CO3 (GE)
- 1 h F7 : tor Vencel '.!: tcr Level S-1B T/A
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TAllLE I.. (C0!!T' D . ). l
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R2:10TC SitUTDC'.R! PAMEL 1Ctly:lL-001 CC.'!PCI! .;iT TIU" SFEi? l' _AMD CO:iTROL S*dI'i'CH TAEULATIO:i i i, P2:"OTP. SHUIDO*.IN CONT:iCL COMPCNENT TiU.USFSR S'4 ITCH S*.1 ITCH (CC) (itST::) ,' Suppression Pool S-ld IT/A '. LI-026 - ' Nuclear Press".re 3-18 N/t.
!?!--006 Service ' dater Header Pressure S-8 N/A.
- PI-011 Drpsell Pressure
S-18 N/A PI-012 . Drprell Temperature . S-18 N/A TI-021 i - Suppressien Pool S-18 N/A
.TI-022A&3 4
3RCIC " Turbine 3 earing Oil Low Pressure" S-7 N/A
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Amber Indicating Light RCIC " Turbine Cou
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Temocrature Mich"pling S-7 U// Amber End DearingLizht Indicating Oil PCIC " Turbine Governor End Bearing 011 S-7 N/A
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_ Temaerature High" Amber Indicating Linht RCIC " Turbine Tripoml" S-7 N/A Amber Indicatine Litrht .
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r NOTIS: All RSTS, C3, Instrumentation, and Indicatin;; Lights are located on Remote Shutdown Panel 1C61*PiiL-001. LEGEND: S = Switch RV = Relief Velve EX = Heat Exchanger SP = Cuppression Pool FPCS = Fuel Fool Cooling System S'45 = Cervicu ' dater System G3 = General Electric Nuclecr Energy Diticion
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CABLING AND CONTROLS: All controls on the RSP are independent of the normal shutdown controls in the Main Control Room. The Remota Shutdown Transfer Switch (RSTS) provides the capability of disconnecting controls and instrumentation for remote shutdown from those r.ormally used in the Main Control Room. Control and instrumentation cable from the RSP to the cc:tponents listed in Table 1 are routed such that they do not pass through the Relay Room. As an example, the control wiring for the RHR fl Pump (Ell-C0023) is presented in Figure 1 and Table 2.
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- REACTot CORE CDOUNG DEMcsoDoAto -
t Hil-Pc.,o/ '
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59- REn,ure snuwoun TRMsrcK SusTeil (Smowsi sd MottnAL PoseTioA3) 531- Courns,t. sullrcal lbg k;lt S Rj.np p,(,g g , f
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CABLE ROUTING: Control Cable from Recote Shutdown Panel to 1R22*SWG 102 for RIIR B Pump * *
,s (Ell-C002B). Cable ilEllBBC023
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LOCATION PROM TO VIA RACEWAY IDENTIFICATION Control Building El.25 1R22*SWG 102 Duct Bank Conduit & Tray 1CC400 BAG, 1TC400B, Emergency Swgr. Rm 102 ITC401B, ITC4028, ICC402BA6, ITC445B, 1TC412B, 1TC413B, 1TC441B, 1TC440B Control Bldg. Reactor Duct Bank IDC900B28, ITC902B, Bldg. El.8 1DC901B28 Reactor Building Duct Bank El.8 RSP EL.63 Tray ITC700B, 1TC720B, 1TC740B, 1TC751B
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LONG ISLAND LIGHTING COM PANY
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SHOREHAM NUCLEAR POWER STAT!CN P.O. SDX 618. NORTH COUNTRY ROAD
- WAQiNG RIVER. N.Y.11792
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Decerter 11, 1978 SNRC-344 Mr. Harold R. Denten, Director Office of Nuclear Reactor Regulaticn U. S. Nuclear Regulatory Cc:::nission Washington, D. C. 20555 SHOREEAM NUCLEAR PCb .s ai.sTION - UNIT 1 DOCEIT NO. 50-322
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Dear Mr. Denten:
Enclosed are Ic-ty (40) ccpies of responses to additional requests for fire analysis infer.ation contained in Mr. Steven A. Varga's letters cc Mr. A. W. Wofford, dated June 27, 1978 and August 9, 1978. Very truly ycurs,
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-/ Project Manager Shorehan Nuclear Power Station .
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Question E11: Provide the following information pertaining to the design of the remote shutdown system: (1) For each device listed in Table 1 of Attachment 3 of your letter of January 31, 1978 (SNRC-252) , identify the division supplying power to the device before and after control of the device is transferred to the remote shutdown system. (2) For those devices listed in Table 1 of Attachment 3 of your letter of January 31, 1978 (S'TRC-252) which are used to control the operation of components such as valves and pumps, identify the power division and type of current (alternating or direct) assigned to the component if they are different than those of the controlling device. (3) Supporting information which may be used to conclude that for a postulated fire event, the required power to components necessary for safety shutdown will not be lost. Resoonse:
- 1. Table E11-1 incoroorates the information from Table 1 of f and the information g, Attachment 3 of our letter (SNRC-25 2) requested above on the remote shutdown system.
- 2. ~Same as item 1 above.
- 3. The remote shutdown siitem is designed to provide safe shutdown capability from outside the control room, for an event which will cause uninhabitability of the control room.
Power required for those ecmponents necessary for safe shutdown which are provided on the remote shutdown panel (RSP) will not be lost due to a postulated fire event in the control room because (a) power independently fused from the control room is provided at the RSP and (b) the power in the control room is switched out for the RSP components when the transfer switches at the RSP are turned to " emergency". t
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RFtWYrE S!!13TDOWt: PAtJ F1, IC61* Prit,-RSP mMinotWtrl' Ti<At:SFFR At3D CottrHOI. SWITCil TAHilt.ATIOte Regnote Shutdown Control Division and Transfer Switch Suit ch tint ive Power Controlling Component t hM.TSI JCJ_ Norina l M Power
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Itcactor RV S-15 S-48 I I In21*RV-092C DC DC Reactor RV S-15 S-49 I I - 1U21*RV-092D DC DC Reactor RV S-15 S-61 I I - 11121*RV-092F DC DC Reactor Recirc. Pump D Suction S-16 S-50 II II HCC it31*HOV-031B AC AC RIIRS Purnp S-9 S-31 II II DC IE 11
- P-01415 AC AC SWGR RitR Pump B Suction S-9 S-32 II II HCC IE11*MOV-031D AC AC RilR Shutdown Cooling S-2 S-33 I I HCC 1E11*MOV-032A AC AC RilR Shutdown Cooling S-1 S-34 II II ICC 1E11*HOV-032D AC AC RitR Shutdown Cooling S-2 S-47 I I HCC 1 Ell'MOV-032C AC AC EllR Shutdown Cooling S-1 S-41 II II HCC 1E11*HOV-032D '
AC AC
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RilH IlX Shell Side Inlet S-14 S-46 II II HCC 1E11*MOV-033D AC AC Ritit IlX Shell Side bypasa S-Ito S - 88 5 II II HCC IE11*MOV-034tt AC AC Rlllt ItX Shell side outlet S-13 S-40 II II HCC IE11*MOV-035B AC AC i<tlit Outtumrd Injection S-12 S-42 V V HCC IE l l *l10V-03 6D AC AC RllH Inlioard Injection S-12 S-39 V V ICC 1E11*MOV-037b AC AC RilR Drywell Spray Outboard S-57 S-56 II II HCC I t.11
- MOV-0 3 Bil AC AC 1 of 5
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Ig]x E11-1 ((ultr*D1
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Homote Shistdown Control Division and Transfer Switch Switcli ttgt ive Power controlling Component II4STS) ICS]_ Ik se m il Erd Prue r ItifR SP Spray and Cooling S-13 S-44 II II HCC 1E 11* HOV-040lt AC AC HilH SP Spray S-57 S-58 II II HCC 1E 11 *tK)V-0 41B AC AC HilH SP Cooling S-11 S-37 II II HCC 1E 11* HOV-04 215 AC AC HIIH llX Dralin to HCICS S-11 S-38 II II HCC IE 11 *MOV-Ose 3B AC AC I<llH IIX Drain to SP S-11 S-36 II II HCC IE11*HOV-044D AC AC HilH Shintdown Cooling Suction S-78 S-51 I I HCC IE11*HOV-047 AC AC HitH Shtstdown Cooling Suction S-77 S-35 II II HCC IE11*HOV-048 DC DC RitR Crosa IIcader Shutof f S-10 S-64 II II HCC 1E 11 *tKW-050 AC AC Hlin outixiard lleadspray S-77 S-43 II II HCC 1E11*HOV-053 DC DC HitH Intuard ifeadspray S-78 S-63 I I HCC IE11*HOV-054 AC AC HCIC Darometric Condenser vacuura Pump S-6 S-30 I I HCC IE51*P-076
- DC DC HCIC narometric Condenser Condensate Pump S-6 S-29 I I flCC IE51*P-077 DC DC HCIC Pump Suction Condensate Storage Tank S-3 S-21 I I HCC 1E51*HOV-031 DC DC HCIC Pump Suction SP S-3 S-22 I I HCC IE51*HOV-032 DC DC itCIC Pump Discliarge S-52 S-54 I I HCC IE51*HOV-014 DC DC I4CIC hunn Dischar ge S-52 S-53 I I HCC IE51*HOV-035 DC DC I4Cic Pump Minimum Flow Dypatsu S-52 S-55 I I HCC IE51*HOV-036 DC DC 2 of 5
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Remote Shutdown Control Division and Transfer Switch Switch Motive Power Controlling Comionent (RSTS) (CS) tionnal ESP __ Power RCIC Pump Discharge to Condensate Storage S-4 S-23 I I HCC Tank - 1E51*Mov-037 DC DC RCIC to Lute Oil cooler S-5 S-26 I I HCC IE51*MOV-038 DC DC RCIC Steam to Turbine S-17 S-19 II II HCC 1851*HOV-041 AC AC RCIC Steam to Turbine S-4 S-24 I I HCC IE51*MOV-042 DC DC RCIC Steam to Turbine S-5 S-25 I I HCC 1E51*MOV-043 DC DC RCIC Turbine Stop Valve S-5 S-28 I I Hrc 1E 51*tt0V-044 DC DC RCIC Turbine Exhaust to SP S-3 S-27 I I HCC 1E51*MOV-045 DC DC ItCIC Vacuum Pump Discharge to SP S-79 S-60 I I HCC 1E51*MOV-046 DC DC IE51*Mov-041 Bypass S-17 S-62 II II HCC 1E51*MOV-047 AC AC RCIC Turbine Exhaust Vacuum Breaker S-79 S-20 I I HCC 1E51*MOV-049 DC DC FPCS Pump , S-83 S-74 II II HCC IG41*MOV-023B AC AC SWS Pump S-80 S-71 II II DC 1P41*P-003B AC A2 SWGR SWS Pump S-81 S-72 III III DC 1P41*P-003D AC AC SWGR SW Pump D Discharge S-80 S-65 II II HCC IP41 *MOV-0.t lls AC AC SW Pump D Discharge S-81 S-67 III III h.T. 1P41*MOV-031D AC AC Service Water lleader S-82 S-69 II II HCC IP41*MOV-032D AC AC I<ltit itx IEl1*E-034n Discharge S-57 S-59 II II HCC IP41*MOV-034D - AC AC 3 of 5
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- TAnLE E11-1 (COffr*D] ,
- i Remote Shutdown control Division and Transfer Switch Switch Hotive Power Controlling Component (PSTSI (CS) Norm.n l KR Power To TUCLCN liX S-82 S-66 II II MCC
' 1P41*HOV-0358 AC AC RDCLCN llX Discharge S-82 S-68 II II HCC 1P41*HOV-037D AC AC BBCLCN Pump S-83 S-73 II II MCC 1P42*P-005B l.C AC RDCLCN llX E-11B Inlet S-83 S-70 II II MCC 1P42*MOV-042B AC AC RIIR llX Shell Outlet S-8 N/A N/A II DC Power CI-016 AC Supply RIIR Main Flow S-8 N/A N/A II DC Power
*PI-001 AC Supply RCIC Flow Indicator Controller S-7 N/A I I Inverter and
*FIC-R001 (GE) DC DC DC Power Supply RCIC Turbine Speed S-7 N/A I I -
R-003 (GE) DC DC Reactor Vessel Nater IArvel S-18 N/A N/A I DC Power
*LI-H010 (GE) AC Supply Suppression Pool Level S-8 N/A N/A II DC Power LI-026 AC Supply Nuclear Pressure S-18 N/A N/A I DC Power
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*PI-006 AC Supply
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Service Hater lleader Pressure S-8 N/A N/A II DC Power PI-011 AC Supply Drywell Pressure S-18 N/A N/A I DC Power PI-012 AC Supply Drywell Temperature S-18 N/A N/A I DC Power TI-021 AC Supply Suppression Pool S-18 N/A N/A I DC Power TI-022A & B AC Supply RCIC " Turbine bearing Oil low Pressure" S-7 N/A - I - Amber Indicatinq Light DC RCIC
- Turbine Coupling End Learing 011 S-7 N/A -
I - Temperature Ifigh" Anber Indicating Light DC 4 of 5
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TAB 12 F11-1 (Corrr *D) .
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Remote Shutdown Control Division and Transfer Switch Switch Hotive Power Controlling Comronent fl<STS) (CS) flormal ffP Power RCIC
- Turbine Governor End 13 earing Oil S-7 II/A -
I - Temperature Iligh= Amber Indicating Light t>C I<CIC = Turbine Tripped" S-7 N/A - 1 - Amber Indicating Light DC Lube Oil Cooler W S-79 11/A I I I - DC 1E51 *101- III 2 AC AC Ingic J Notes
- 1. The RSTS, CS, Instrumentation, and Indicating Lights are located on ReN>te Shutdown Panel IC61* PN L-RS P .
- 2. The Controlling Power and the Motive Power for either Normal or Emergency Mode for each component is always fed fross the same Division.
Icgend: PJ = Switch SP = Suppression Pool itX = Ileat Exchanger SMS = Service Water Systtsu RV = Relief Valve FPCS = PNel Pool Cooling System GE = General Electric Nuclear Energy Division MCC = Motor Control Center (AC or DC da defined under Motive Power Columns) Divisions: I - Red IV - Green II - Blue V - Yellow III - Orange
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SC 4a(vii) 7a(ii) UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Atomic Safety and Licensing BoaId In the Matter of )
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LONG ISLAND ,IGHTING CCMPANY ) Docket No. 20-3,,_,,
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(Shoreham Nuclear Power Station, ) Unit 1) ) AFFIDAVIT OF G. R. HEINE II G. R. Heine'II, being duly sworn, states as follows:
- 1. I as a Senior Control Engineer in the Control Systens Division of Stone & Webster Engineering Corporation. A state-cent of my professional qualifications is attached.
- 2. Criterion 19 of 10 CFR Part 50, Appendix A requires in part that Equipment at appropriate locations outside the control room shall be provided (1) with a de-sign capability for prompt hot shutdown of the reactor, including necessary instru=entation and controls to maintain the unit in a safe con-dicion during hot shutdown, and (2) with a poten-tial capability for subsequent cold shutdown of the reactors through the use of sui:able proce-dures.
- 3. The remote shutdown capability is required by Criterion 19 to persi the safe shutdown of the reactor in the unlikely event that the control room becoces uninhabitable. The Shorehan design complies with Criterion 19 because the necessary instru-ments and controls exist outside the nain control room to acccc-plish p cept hot shutdown, to =aintain :he reactor in that con-
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dicion safely, as well as to bring the reactor to and maintain cold shutdown conditions through the use of appropriate pro-cedures.
- 4. In the unlikely event that the main control room becomes uninhabitable, the operator is instructed to scram the reactor before leaving, thereby achieving prompt hot shutdown. However, if the reactor is not scrammed from the main control room, that can be accomplished by opening the output breakers of the reactor protection system busses.
Shoreham is designed so that all other necessary remote controls and instrumentation have been centralized on a remote shutdown panel. This panel is located in the reactor building where it is physically separated from the main control room but still readily accessible from the control room. At the remote shut-down panel, the operator has control of sufficient equipment to maintain the plant in a safe hot standby condition or, if desired, bring the plant to and maintain cold shutdown condi-
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tions.
- 5. The controls and instrumentation available on the remote shutdown panel are completely independent of those normally employed in the main con, trol rocm. Control is established at the remote shutdown panel by means of transfer switches on the panel. When these switches are operated, the controls and instrumentation at the remoce shutdown panel are isolated from the main control room. They use separate control anc instru=entation cable not routed through the main control room. This design independence precludes any inter-
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action between the no mal and remote controls for equipment being operated from the remote shutdown panel.
- 6. In addition to being accomplished at the remote shutdown panel, the necessary shutdown functions can also be performed locally at the component level. Communications would be provided between local control points and the re-mote shutdown panel to allow proper coordination if local control is performed for any reason.
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G. R. Heine II Subscribed and sworn to before me this _ / c/ day of December 1978. 7/ NotaryvPublic My Commission Expires: 4/cd/
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QUALIFICATIONS OF G.R. HEINE II My name is G. R. Heine II. My business address is Stone & Webster Engineering Corporation, 245 Summer Street, Boston, Massachusetts. I am currently a Senior Control Engineer in the Control Systems Division of Stone & Vebster's Engineering Department. I am the Lead Control Engineer for the Shoreham Project, responsible for the engineering and design of the instrumentation and control systems. I received a Bachelor of Mechanical Engineering degree from Georgia Institute of Technology, Atlanta, Georgia, in 1958. After receiving my degree, I was employed by Tampa Electric Company for five months and then served in the U.S. Army Chemical Corps for six months as a Second Lieutenant at Fort McClellan, Alabama. I then returned to Tampa Electric Com-pany as an engineer temporarily assigned to General Nuclear Engineering Corporation. In this position, I assisted in the design of a proposed 50 Mw, gas cooled, heavy water moderated
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nuclear power plant. In 1961, I joined Stone & Webster Engineering Corporation as an Engineer-in-Training in the Mechanical Division. I was subsequently appointed to the positionc of Engineer, Nuclear Division in 1964; Construction Engineer in 1965; Mechanical Engineer in 1967; Control Engineer, Control Systems Division in 1970; and Senior Control Engineer, Control Systems Division, in 1972. Since 1970, I have been responsible for instrumentation and controls engineering and design on the Shoreham Nuclear Power
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Station. I have been an Associate Member of the American Society of Mechanical Engineers since 1958. I am c. licensed Professional Engineer in the Commonwealth of Massachusetts.
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