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Forwards Revised Final Draft Responses to Power Sys & Reactor Sys Branch Questions,Per 820825 & 1115 Requests.Only Mods (New or Revised) to Responses of Referenced Ltrs Provided
	ML20069B842
Person / Time
Site:	05000447
Issue date:	03/15/1983
From:	Sherwood G; GENERAL ELECTRIC CO.
To:	Eisenhut D; Office of Nuclear Reactor Regulation
References
	JNF-015-83, JNF-15-83, MFN-053-83, MFN-53-83, NUDOCS 8303170291
	Download: ML20069B842 (29)
	v • d • e

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SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MFN 053-83 MC 682 (408) 925-5040 JNF 015-83 March 15, 1983 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 Attention: Mr. D.G. Eisenhut, Director Division of Licensing Gentlemen:

SUBJECT:

IN THE MATTER OF 238 NUCLEAR ISLAND GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II) DOCKET NO. STN 50-447 REVISED DRAFT RESPONSES Attached please find revised final draft responses to selected questions of the Commission's August 25, 1982 and November 15, 1982 information requests. Only modifications (new or revised) to the responses of the referenced letters are provided. Responses are provided in the attachments as indicated below: Attachment Number Branch 1 Power Systems 2 Reactor Systems Sincerely, Glenn G. Sherwood, Manager Nuclear Safety & Licensing Operation Attachments cc: F.J. Miraglia (w/o attachments) C.0. Thomas (w/o attachments) D.C. Scaletti L.S. Gifford (w/o attachments) 8303170291 830315 /, PDR ADOCK 05000447 Y A PDR

9

ATTACHMENT NO. 1 DRAFT RESPONSES TO POWER SYSTEMS BRANCH QUESTIONS 1

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l , I e ! (. i I i 1 1 . . . 430.04 The undervoltage relaying described in Section 8.3.1.1.7 of your (8.3.1) FSAR, by itself, will not protect the Class 1E equipment against a degraded voltage condition. Branch Technical Position PSB-1 contained in Chapter 8 of the Standard Review Plan (SRP) requires that a second level of undervoltage protection be provided to protect Class 1E equipment against degraded voltage conditions. Describe your i compliance with this position for Class 1E, Divisions 1, 2 and 3. - g gesp o ,c _

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QUESTION 430.14 State in section 8.3.1.1 of your FSAR, whether the nuclear system pro-taction system ,(N5PS) non-Class if power supplies which feed the "3" scram solenoids have a separate and redundant Class If protective package installed between the power swply and bus consisting of evervoltage,
,- undervoltage and underfrequency protection. If not, this package should be installed to protect the solenoids against a conditten which could , fail them in the unsafe direction. Discuss the susceptibility of the load drivers to power supply anomalies such as ever/undervoltage, ever/ , unde' frequency, voltage transients, voltage spikes, EMI and harmonics.
~~The protective package must provide protection against any conditions which would fail the load drivers in the unsafe (i.e., shorted or closed) direction.~~
~~RESPONSE~~
tton-lE pow & SRPPb Current NSPS4fesign by G sists of "ndependent Uninterruptable sa ppite gerni a o cTnNon
yn e Re4<v 4s Sen.. t.h. s . l . 4 2. W'9 "f Power m u n_s,-(UPS)g Each cludes a battery charger,125 VDC battery, for dM an inverter, ameeen e4yyusemeestok, an Electrical Protection Assembly (EPA), a 480-120V regulating transformer, a manual bypass (inverter bypass) switch and essential metering devices for the UPS.
The EPA consists of over-under voltage and und'er frequency monitoring circuitry and an output disconnecting device (circuit breaker). The EPA provides over-under voltage and under frequency protection to the RPS loads and related power supply associated with the scram pilot valve solenoids and the MSIV pilot valve solenoids by disconnecting the bus " from the input power whenever the UPS output voltage and frequency deviates beyond the preset limits. These limits are to be established by field calculations. The EPA is designed to meet the IEEE-323 and IEEE-344 requirements. A second supply is through the 480-120V regulating transformer,e.c.d 1 Emtir t=irnr. The regulating transformer provides voltage regulation of 1sl 3 It is furnished with a harmonic distortion filter to reduce the maximum output distortion to 5% RMS. The regulating transformer is virtually immune to lightning or transient surges on the line and has a low audible noise level of 65 dB at 5 feet. The transformer is qualified for IEEE-344 and IEEE-323 requirements. 1 MP:csc/Il0146-6 11/4/82
The power supply through the bypass circuit, including regulating trans-former shyAseadanas.8aamas is also monitored by the EPA as described above. The new load driver cards are designed to meet the requirements of IEEE-472 and are capable of operation within voltage variations of 24-200V AC or DC. They also operoys oh cquare wave pukes as,a are therefore o nsensi + 1 ve h harrrwnic vcHages from fheIrpoWeYsu,cfy. l e e 9
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' " $2AS7A0R@/ . ""M P A R IS .D Rav. O O.l4 44 d E Utft Q 1ow 8.3.1.1.4.2 Nuclear Systems Protection System (NSPS) Power Supply The NSPS power supply is shown in Figure 8.3-1 and in Figures 8.3-20a, b, c,3with each bus supplyinge&Lamad e power for the independent trip systems of the Nuclear Systems Protection System (NSPS). Four NSPS control power buses (Divisions 1, 2, 3 and 4) have been established. They are each normally supplied indepen-dently from inverters wh hgnturn,aresuppliedfromtheDC buses of the corresponding division. Use of solid-state static 3
transfer switches makes it possible to energize the NSPS control power buses from alternate Class lE AC sources for added continuity. The second input to the transferPswitch is from a regulating trans-former, connected to the same visional power as the batte sup-lying the verteYr7 is pnyihh' 1 .faqif'4l2 [' r^ E N r.ri - ? ss _ swi_ N:..d 2.y W . h q $ fe.>- -oh
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The NSPS t;HF power S supply buses are designed to prov,ide power to the four-division 1ogic 3 system that operates the RPS and other safety functions controlled by the NSPS. These buses also supply pov3r to 27 ...J 1_i r r P r -- ""rr' y ch"* ^F # cy-*^~ Ned ' - ^ ' ^ " ^ " #
-- '---- Neutron monitoring system and parts of the process radia-tion monitoring system and leak detection instrumentation,. Power is applied so as to prevent inadvertent operation of the reactor scram nitiation or ECCS initiation upon loss of any single power suppig. Actual functioning of the NSPS is covered in Sections 7./, 7.3 and 7.4. -
EC> NSERT *A* Routine maintenance can be conducted in equipment associated with the NSPS Power Supply. Inverters and solid-state switches can be inspected, serviced and tested channel by channel without tripping the RPS, iG. (^) % w ob : ry . s-t um 6 m sa n kk-%<."ny"my ~ s.a s .- z h ag
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GESSAR Il Sec tion 8.3.1.1.4.2 + fNSERT"A] Two nondivisional RPS power supply buses have also been established. Each of the two nondivisional RPS bussis normally supplied independently from an inverter which in turn is supplied from a separate nondivisional DC bus. Use of[ w d transfer switch for each of these buses makes it possible to energize each bus from an alternate nondivisional AC source for added continuity. The second input to the transfer switch is from a regulating transformer, connected to the same nondivisional power bus as the battery supplying the inverter for the corresponding RPS bus. The RPS power supply buses are designed to provide power to the RPS scram and Nuclear Steam Supply Shutoff System (NS 4 ) solenoid valves. D
GESSAR II 22A7007 238 NUCLEAR ISLAND Rsv. 0
~~$ 8.3.1.1.4.2.1 Components Each of the four essential NSPS power supplies includes the following components:~~
(1) a power distribution cabinet, including the NSPS 120 VAC bus and circuit breakers for the individual loads; (2) a solid-state inverter, to convert 125 VDC battery power to 120VAC NSPS power; (3) a solid-state transfer switch to sense inverter failure , and automatically switch to alternate power; (4) a 120V/120V isolation transformer to provide noise isola-tion for the alternate 120 VAC power supply; end
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' GESSAR II 22A7007 238 NUCLEAR ISLAND Rcv. 0 8.3.1.1.4.2.2 Power Sources The NSPS power supply sources consist of three types of power.
(1) Class lE 120 VAC; (2) non-Class lE 120 VAC; and (3) Class lE 125 VDC. A/SPS i (1) Class lE 120 VAC: Fourgivisional 120 VAC buses are each fed by a 480V Class lE power supply via two paths. The normal path is from the normal battery charger to a divi-sional battery bus which powers an inverter. (The bat-tery can also be fed by nonessential AC power lter-nate battery charger.) The alternate path is direct, through a class lE stepdown transformer. (2) Non-Class lE 120 VAC: 4 1-nondivisional 120 VAC RP.S bus M ed by r r rf two h V divisional power suppli s. Asyparatestepdowp)ransformerisprovided O f m..- hVACy___ _____ -
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(3) Class lE 125 VDC: The nuclear system protection system also utilizes 125 VDC power from the Class lE batteries. 8.3.1.1.4.2.3 Operating Configuration The four 120 VAC essential power supplies operate independently, providing four divisions of inverter power supplies for the NSPS. The normal lineup for each division is , 4e. okke. hrohghanessential480VACe s .swGd, Mk & been 3 power supply, the normal battery chargery.aswP the invert.erf Trans-fer from the inverter, directly to the essential AC source is done automatically in case of inverter failure, or manually for mainte-nance or testing. Annunciation in the control room is provided for the following: switchingtothealternatesource;inveger failure, and manual bypass. Thenogsential120VACfowersupply supplies independent power to the scram solenoids and the W (3 Q
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GESSAR II 22A7007 238 NUCLEAR ISLAND, Rav. 0 8.3.1.1.4.2.3 Operating Configuration (Continued) MSIV solenoids for isolation. The nonessential 120 VAC bus is normally lined up to the preferred 480 VAC nondivisional' power supply. Tr sfer to the alternate nondivisional power supply is m .y done 2"+~a*
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I_ 8.3.1.1.5 Class lE Electric Equipment Considerations The following guidelines are utilized for Class lE equipment. 8.3.1.1.5.1 Physical Separation and Independence Equipment of one division is segregated from equipment of other divisions and nondivisional equipment, in accordance with IEEE Std 384-1974, Regulatory Guide 1.75 and General Design Criterion 17. g The overall design objective is to locate the divisional equipment and its associated control, instrumentation, electrical supporting systems and interconnecting cabling such that separation is main-tained among all divisions. Divisional separation is achieved through the use of barriers and spatial separation. The latter is enhanced by totally enclosed raceways. Redundant divisions of electric equipment and cabling are located in separate rooms or areas and/or are provided with spatial separa- . . tion, such that no single event may disable more than one of the redundant divisions or prevent safe shutdown of the plant. Cables entering the drywell area from the containment area utilize a standard conduit sleeve and conduit seal. The seals are located in each divisional sector and at elevations to serve the equipment inside the drywell and to maintain acceptable spatial separation 8.3-8 1 i
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~~f. s ATTACHMENT NO. 2 s ,~~
~~DRAFT RESPONSES TO REACTOR SYSTEMS BRANCH QUESTIONS~~
. b 440.13 Identify the relief valve discharge lines in the ECCS which penetrate (6.3) primary containment and have outlets below the surface of the supp-ression pool. Since these lines form part of the primary containment, our concern is that excessive @namic loads resulting from waterhammer during relief valve actuation may cause cracking or rupture of these lines. Provide additional information concerning measures you have taken to prevent this type of damage to these lines.
~~Response~~
All ECCS relief valves, except RHR relief valve number E12-F055, that discharge to the suppression pool, discharge subcooled water. Actuation of these relief valves are caused by small quantities of water that either leak back from the reactor and/or result from thermal expansion of water in the ECCS lines. Since these actuation conditions are characterized by pressure slowly approaching the relief valve set point and discharge of small quantities of water, significant water hamer and dynamic loads do not occur. RHR relief valve number E12-F055 is provided to prevent overpressurization of the RHR heat exchanger during the steam condensing mode (SCM). Actuation of this relief valve would occur if the steam pressure reducing valve number E12-F051 failed open during the SCM and steam would be discharged to the suppression pool. The dynamic loading' associated with actuation of E12-F055 during the SCM will be :
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f 440.20 We state in the SRP (e.g., in Section 15.1) that for anticipated transients, the most limiting plant systems single failure shall be identified and assumed in the analysis. Accordingly, describe the worst single failure for each events analyzed in Chapter 15 of your FSAR. Provide analyses including these postulated failures for the five most limiting events identified in your FSAR.
~~Response~~
Chapter 15 contains evaluations of postulated single failures associated with anticipated transients. Plant nuclear safety operational analysis (NOSA), the system-level qualitative-type failure modes and effects analysis of essential protective sequences in Appendix 15A, show compliance with the single active component failure or the single operator error criteria. The five most limiting analyzed Chapter 15 transients are:
1. Loss of Feedwater Heater-Manual Flow Control (Subsection 15.1.1)

2. Feedwater Control Failure-Maximum Demand (Subsection 15.1.2)

3. Pressure Regulatdon Downscale Failure (Subsection 15.2.1)

4. Generator Load Rejection with Failure of Bypass (Subsection 15.2.2)

5. Turbine Trip with Failure of Bypass (Subsection 15.2.3)
In reviewing the expected sequence of events utilized in simulating the plant performance for each of these transients, it was determined that postulating a single active safety-related component failure does not alter the transients. For the feedwater control failure - maximum demand transient in which credit is taken for full turbine bypass capacity, a single active component failure would result in the loss of one of the turbine bypass paths. However, the consequence of loosing one bypass path is not expected to result in fuel failure. 1}}

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