ML20009B254
| ML20009B254 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 07/10/1981 |
| From: | Pollock M LONG ISLAND LIGHTING CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.D.3, TASK-2.E.4.1, TASK-2.K.1, TASK-TM SNRC-591, NUDOCS 8107150174 | |
| Download: ML20009B254 (15) | |
Text
M LONG ISLAND LIGHTING COM PANY FLd'O SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER, N.Y.11792
.m July 10, 1981 SNRC-591 Mr. Harold R.
Denton, Director Office of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 SHOREHAM NUCLEAR POWER STA'.? ION - Unit 1 Docket No. 50-322
Dear Mr. Denton:
Enclosed herewith are sixty (60) copies of LILCO responses to specific NRC concerns which were previously identified as requiring additional information to complete NRC review.
Attach-ment A provides a list of the specific responses included.
If you require additional information or clarification, please do not hesitate to contact this office.
Very truly yours, h ') f glj'
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Pollock fjv 4~'
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Vice President - Nuclear j-/
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PDR ADOCK 05000322 T
L;:RC-591 ATTACHMENT A Responses to the following are enclosed:
1.
Clarification for SER Open Item No. 26 - Suppression Pool Bypass.
2.
Supplemental Information for SER Open Item No. 38 - Contain-ment Pressure Boundary Materials.
3.
Clarification to NUREG-0737 Item II.E.4.1 - Containmer;t Dedicated Penetrations.
4.
NUREG-0737 Item II.D.3 - Relief and Safety Valves Position Indication.
"5.
Supplemental Information for NUREG-0737 Item II.K.1.22 -
Auxiliary Heat Removal System Procedures.
A
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Clarification for SER Open Item No. 26 - Suppression Pool Bypass Vacuum breaker leakage will be included when determir.ing if the 2
acceptance criteria (10%
of A/K =0. 9 f t ) is mec for the preoperational high pressure leakage test.
At this time, however, a decision has not been made whether to expose the down-stream side of the vacuum breakers to the test pressure or to test them separately.
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SUPPLEMENTAL INFORMATION FOR SER OPEN ITEM NO. 38-CONTAINMENT PRESSURE BOUNDARY MATERIALS 1.
Mill test report for containment top head flange ring 2.
Heat treatment chart (normalizing) for Main Steam Isolation Valve 1B*21AOV-082c 3.
Mill test report for the sleeve material for main feedwater penetration X-2A 4.
Main steam isolation valve body wall thickness This docur.ent should also serve to confirm that the outboard isolation valves for the main steam and main feedwater systems are welded directly to the containment penetration process pipe with "c intervening pipe spools.
Two branch connections are welded to each feedwater line penetration process pipe size).
In addition, each outbard main steam isolation alv has a 2" branch connection welded to it on the upstream
---a of the valve.
The small size of these lines excludes them from consideration relative to brittle fracture.
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@.A.e Rockwe00 t.tAttufAcTurtt:G cc:.tPAt Y 4,00 ff.tExtNGTCt2 AVENUE. PITTSCURG,(,PErJtJSYLVAtJIA 15XJ. TEl.EP!{0tJE: (412 2414100 Department 40-SMS CUSTOMER REFOR- ~
Repori No. 2'J[A -0 2.- C C WXI1
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SUBJECT Calculetion fer Reckwe!!-Edward 24X30X34. Fig.1612 JMM Flite-Flow volve. Per General Electric, P.O. No. fib -31 '7 g
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Specificcticn No. 21/i 73 30 NEMI pE 73EOS Rev 2 o uT',
Plant: / LLC,0 g
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I ABSTRACT This enclysis demonstrctes thet the subject vcive fulfills cil dcsign requirements relotive to
'siress Icvels frem seismic !ccds (c.G G verticcl end/. 6G 1.cricental) cnd funcrice.cl performence. Cc!culcriens were 'cesed en the maximum cpuoting ccnd;tiens of /2.50;. (J' a PJ,?
ond envirenmen:ci ccnditions ci 77..lt@, 310 F. A!!cwc.ble strc::es wer.: determined from Section ill er Vlil ci ti e ASME Ccde.
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. KEY WORDS General Electrie, Seismic, Estanced Volve, Design Cciculatien DISTRliUTION c
unen (} usssur "2
2/18/74-TEK
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Fogo No.1 INTRODUCTICN
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.The Rockwell-Educrd 24.Y 30 K 24 inch cig.1612 JMMY ~ equipped with
, on cir cylinder cpercter fcr cpening end closina the valve. Springs cre
>.sist.
which will close the vcive with cr without cir cylinder
.ch providcs i!.c speed centrol A hydrculic cylinder is incerpercted irrthe system v function. This control is previded by use c;, resuie cen.penscred cdjusicEle floa control volves. These velves provide c constcnt ster.1 speecl throughcut the strcke ~
of the vc!ve during flouing cad r.ca-ilowing condificns.
The volve d: sign ellcws removcl cf the entire y:.he esserr.biy (cylindus, sp.ings, c os o unit in c minimum ci spcce. The cyliners ccn be rerr.oved withcut unlccjing the springs. The spring fler.ge is net directly ccnnected to the ::cm coupling ti.us allowing the cir cylind;r to c!c;e the velve even if s;.ririts I.sve icilcd cau;ir.g binding of the spring guides er the sciety pir.s cre ir.cd/crt.ntly Icit in the yche tubes.
This report covers cil the ' design cnd perictmence enclyses requircd by G-E specificctier.s.
II, BODY MIN!!.'.UM WA'.l. THICKNESS The design eendition es given in the GE specificction is 17f0.F equivelent prirr. cry f *vice pressure reting is Gf.f. Since this is c Ecsic %Chlv
~
with2.1" ends,two crr es will be checked (cr minin.um wc!! thichnuss.
One chcck is where the !crgest inside dicmetur to t!.ichness cccurs. This is in the guide rib cree of the vc!ve neck whcre th* dicaster is 13.7 7 inches,
~
The second check is necr the wcld ends, where the dicmeter is 21.G inches (cssumed equel to the pipe ir. side dicmeter).
The cetect well thickness shculd be grecter cr equel to the value obtained frcm the following cquction.
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Pd
+C t = 1.5 20 - f.2 ?
wherc:
t a ccIculoted thickncss, in inches P = primcry service pressure rcting
~
a d56 psi
~
d.= 1.D. cf vcive where ccicuicticn is mcde t
5a stress = /0C0 psi C = corrosion c!!cwcnce = 0.120 inches
Report No. 2E].c2-c6 PcDeNo.2 49 7,,
Nect Weld'End Neck Section Actue! Thickness Costing r.cminal
. 2.60 "
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Jhichnus Required Th.chness 2 /. 83
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In both ccscs the cetuel minimum pressere contcining wc!! thickness is equal to $r c then !!.c required minimum wcIl thickne:s.
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DI5!' STr':ESS Gencrol E!cettic Comp ny engineering data sheet No. H1165-5 recomtr. de use of equ:.ficns frcm Chcp;ct X, 'Formulcs fer Stress cnd Strain" by Ec.:, for cc.fculatir.g dith strcsses. A summetica cf Ccse 13 cnd 14 is used t'cr c'.
t.nining tenacntic.! srrt.:s er the pilot sec diamcrer. Since the cish thicknc:s
. 4, on overcae thic' nu.s cf the.heded pcrtica (shown in Figure 1) cf 6,13 h.4.s 4 used Ic,r "t" in the cquetion.
in addifica, Ccse 22 is used to de:ccmine stresses where o reduced thMuto is
, incorporated to inercose the dia i!cxibility et the secting creo, thie.l.ncss used fer
.colculclien is on evero3e of this crcss helched crea shcwn in the dis;; sketch. This overe v thichness is2,;2 inches.
Mosth", Cl.cpter X, Ccse 13.
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Clarification to NUREG 0737 item II.E.4.1 - Containment Dedicated Penetrations Isolation valves for the primary containment penetrations serving the hydrogen recorbiners are administratively controlled by means of keylock control switches in the main control room.
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6 SNPS-1 FSAR II.D.3 heller and safetv Valves Position Incication NRC Position Reactor coolant system rellet and sarety valves snall be proviceo with a positive indication in the control room derived Irom a rellanie valve position detection device or a reliable indication or Ilcw in ene cisenarge pipe.
The paragrapns that rollow clarify the above position.
The basic requirement is to provide the operator with unamniguous indication or valve position (open or closed) so tnat appropriate operator actions can ne taxen.
The valve position should ne inoicatea in tne control room and an alarm should be provlaed in con 3 unction with tnis indication.
Tne valve position incication may be sarety grade.
II tne position incication is not safety
- grade, a
rellanle single-enannel direct incication powered Ircm a
vital
. instrument bus may ce provided if backup nernods or determining a valve position are available and are discussed in the emergency procecures as an aid to operator alagnosis of an action.
The valve position indication snoula be seismically gua11rleo consistent witn the component or system to wnicn it is attachec.
It also snoulo Le qua11ried ror its appropriate environment (any transient or accicent wnicn would cause tne reller or safety valve to liit) and in accordance with Commission Order, May 23rd, 1960 (CL1-2 0 -
al).
It is important that une displays and controls addea to tne control loom as a result of tnis requir ement not increase tne potential ror operator error.
A numan-ractor analysis should De performed taking into consideration:
the use or tnis inrormation by an operator curing totn normal anc annormal plant conditions, Integration into emergency procecures, integration into operator training, anc other alarms auring emergency ana need ror prioritization or alarms.
LILCO Fosition Tnere are a total or eleven (11) cual runction sarety relief valves (SdV) in the snoreham xeactor System.
Tne SRVs 11.D.3-1 i
SNPS-1 FSAR installed in this facility are of the Target Rock two-stage pilot operated design.
Direct main stem position indication is not accessible in a valve of this type.
Accordingly, positive position indication is provided utilizing pressure transmitters on each SRV discharge line.
The discharge of each SRV is independently piped to approximately five (5) feet from the bottom of the suppression pool.
The calculated steady state pressure near the v31ve discharge is in the range of 300 psig when the valve relieves at set pressure.
This pressure is sufficiently high that a positive and unambiguous signal is available with ample margin for tolerances in calibration and variance in line pressure.
When a
valve
- recloses, pressure will return to normal in a fraction of a second.
Thus, pressure measurement does not have the slow response l
time which characterizes discharge pipe temperature monitoring instrumentation.
Since each valve discharge is independently
- piped, the pressure signal provides unique indication for the associated valve.
Eonredundant safety-grade instrumentation is provided to monitor pressure in the discharge pipe of each SRV.
The transmitters are located in the secondary containment and connected to the SRV discharge piping by instrument lines penetrating the primary containment.
Individual display and trip set point instrumentation is provided for each SRV in the main control room.
The range of instrumentation allows for a trip setpoint of 10-50 percent of rated flow.
This gives a positive open position indication and also provides sufficient sensitivity to detect a partially open SRV.
A common alarm is also provided in the control room to promptly alert the operator when any SRV is open.
The display instrumentation is located as close as possible to the SRV control station in the main control room.
A human factor analysis was performed to assure that the indicators and alarms are integrated with existing instrumentation in the main control room in a manner to minimize the potential for operator error.
In
- addition, operator training and emergency procedures will address the utilization of these indicators and alarms.
This instrumentation has been qualified in.accordance with IEEE 323 for the environment expected during events resulting in SRV discharge to the suppression pool, and it is included in our program to upgrade the qualification of all safety-related equipment to the requirements of NUREG-l 0588.
In addition, it meets Seismic Category I requirements in accordance with IEEE 344-1971 and is powered from a Class lE power su ply.
e II.D.3-2
SMPS-1 FSAR The existing temperature monitoring instrumentation is retained for its original
- function, detection of valve leakage conditions as backup / confirmatory indication for the pressur instrumentation.
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II.D.3-3
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TMI Item II.K.l.22 NRC Request Describe why the CRD pumps are tripped on Level 1.
LILCO Response The control rod drive (CRD) pumps are fed from 4160 7 emergency buses 101 and 102.
These buses also supply power to the residual heat removal
( RHR), core spray (CS), and service water (SW) pumps.
Upon a
LOCA signal (Reactor Water Low Level 1 and/or Hi Drywell, Fressure),
the RHR, CS, and SW pumps are sequenced onto the bus.
If these pumps are already on the buses and a
loss of off-site power occurs, these pumps are stripped from the bus and resequenced on after the buses are re-energized by the emergency diesels.
The i
CRD pumps are also tripped by the above mentioned LOCA signals to facilitate sequencing of the large safety related loads, (RHR, CS, and SW).
Manual override is provided to enable the CRD pumps to be restarted 1 minute after the respective diesel generator accepts loads.
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