ML20076D889

Forwards Supplemental Responses to Power Sys Branch Questions Re GESSAR-II Ac/Dc Power sys/balance-of-plant Interfaces.Responses Will Be Included W/Amend 15 to SER

ML20076D889
Person / Time
Site:	05000447
Issue date:	05/24/1983
From:	Sherwood G GENERAL ELECTRIC CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML20076D891	List: ML20076D889 ML20076D894
References
RTR-NUREG-0979, RTR-NUREG-979 JNF-035-83, JNF-35-83, MFN-091-83, MFN-91-83, NUDOCS 8305260037
Download: ML20076D889 (10)

Text

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GENER AL h ELECTRIC NUCLEAR POWER SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 MFN 091-83 MC 682 (408) 925-5040 JNF 035-83 May 24, 1983 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 Attention: Mr. D.G. Eisenhut Division of Licensing Gentlemen:

SUBJECT:

IN THE MATTER OF 238 NUCLEAR ISLAND GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II)

DOCKET N0. STN 50-447 SUPPLEMENTAL RESPONSES TO POWER SYSTEMS BRANCH QUESTIONS Attached please find supplemental responses to selected Power Systems Branch questions. These responses will be included with Amendment Number 15.

Sincerely,

~

Glenn G. Sherwood, Manager Nuclear Safety & Licensing Operation Attachments D ]

cc: F.J. Miraglia (w/o attachments)

D.C. Scaletti 8 C.O. Thomas (w/o attachments)

L.S. Gifford (w/o attachments) / f L MEs b4 25888feB88"gh E

d

, we g y w s e Table 8.2-1 '

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NUCLEAR ISLAND AC POWER SYSTEM / BOP INTERFACES -

Nealmum Allowable Act ua l Act ual Mastmum Allowable Interface Steady Inrush SS Imad SC MVA Number

• Interf ace Description St at o LoaJ kVA (29 jl) Momentary LNT E-1 (A-C) Normal Feeder from slos' to AD 6900-400V XFMR 2550 kVAlli 3.400 1775 kVA ell 409 F-2 (A-F) Normal Feeder from DOP to sus c 79 35 18P 8 4 8 51,574 7935 HP 475 450 E-3 (A-C) geormal Feeder f rom BOP to AB 6900-400V XFMR 2550 kVAll) 3,400 1700 kVA 426 402 E-4 (A-FB Normal Feeder from BOP to Bus D 7935 HPiet 51 570 7935 HP 490 461 E-5 (A-CD Normal Preferred or Alternate Preferred Feeder J560 kVA 17,444 el 490 441 from BOP to NPCS Bus C 5WGR E-13 (A-F) Normal Preferred Feeder f rom BOP to sus E SWCR 8750 kvAIS) 10.423 5907 413 409 E-14 (A-F) Alternate Preferred Feeder f rom BOP to Bus E SWCR 8750 kvAIS) 10.423 5907 433 409 N W

E-15 "A-F) Ik.rmal Preferred feeder from BOP to sus F SWGR 8750 kVA(5) 10.423 4403 426 402 g3 L-16 (A-Fi Alternate Preferred Freder from BOP to Bus F SWGR 8750 kVAtSB 10.423 4403 426 402 g E-41 (A-C) Normal Feeder from BOP to RW 6900-400V XFMR 1275 kVAlll 1,700 604.1 433 409 OO m OM e E-43 (A-C) Normal Feeder from BOP to PW 6900-400V XFMR 1275 kVAll) 1,700 250.5 426 402 UM w M GA g E-50 QA-B) 250 VDC Feeder to inverter and SS 'K* 50 kVA ---

N 1 W a HH

• see FigUe 0.3-1 for interf aces identifled tr* accordance with these numbers. These (

interf aces are mondivlasonal.

Voltage variattom = t5t at the 6930-volt level Frequency variation = 60 Mat 2 U r

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Gl;bbit K 1i e.a.n s u u s

! 238 NUCLEAR ISLAND Rev. 15 i

Table 8.2-1

NUCLEAR ISLAND AC POWER SYSTEM / BOP INTERFACES I NOTES

(1) Value represents 85% of the transformer "AA" rating. . 1 i Each transformer has an additional 30% capacity (continuous) under forced air cooling conditions.

.-l (2). For unit subtransformer loads, actual inrush kVA is con-sidered as 85% of the transformer "FA" rating. For pumps, inrush kVA = 6.5 x rated horsepower.

1 (3) Values taker. from load summary calculations under normal operating conditions (Mode 2). Exceptions: Interfaces E-13, 14, 15 and 16 LPCS and RHR loads are included.

(4) Pump nameplate rating.

(5) Diesel generator nameplate rating.

l.

1 4

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8.2-4 .

4

=

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s Table 8.3-10 .

NUCLEAR ISLAND ONSITE AC AND DC POWER SYSTEM / BOP INTERFACES Masimum Actual Mas Nasimum Interface Bef9 rence Allowable Inrush Nous Frog Numte r Interface Description Figure Allowable Available

$$_HP g h kVA Volt. Ms ",3P VO SC Current E-3 (A-C) 4900v Feeder from Bus E, SWGR to BOP Figure 0.3-2 2335' 7590 6900 60:24 84 Div 1 ESWS SWGR 41.8 kA E-11 (A-C) 690CV Feeder from Bus F, f.tR to BOP Figure B.3-2 2335* 7590 6900 60924 84 ag,g ga Div 2 ESWS SWGR E-12 (A-C) 400v Feeder from Bus Cl-2 to BOP Figure 0.3-165 60 296 400 60 24 3.154 25 kA Div 3 (HPCS) ESWS Pump E-17 480V Feeder from Bus El-2, MCC to BOP Figure s.3-16P 3 25.5 400 60?2% 3.5% gg Div 1 DG Fuel Oil Transfer Puey E-18 4tCV Feeder from Bus El-2, MCC to BOP Figure 8.3-16P 3 25.5 480 60 2t 3.5% M Div 1 Back up DG Fuel Oil Transfer Punnp 15 kA W

E-20 480V Feeder from Bus F1-2, MCC to BOP Figure 853-16P 3 25.5 , 400 60?24 3.5%

Div 2 DG Fuel Oil Transfer Pump 35 ga g

E-21 440V Feeder from Bus F1-2, MCC to BOP Figure 8.3-16P 3 25.5 490 6022t 3.5% gg ga O CD Div 2 Back up DG Fuel 011 Transfer Pump O@

• I4 th W (A I

E-2) es0V Feeder from Bus Cl-2. NCC to BOP Div 2 (HPCS) DG Fuel Oil Tran?fer Pump Figure 0.3-168 3 25.5 400 60?24 3.754 15 k A >

H  %%

W E-24 480V Feeder from Bus Cl-2, MCC to BOP Figure 8.3-16S 3 25.5 400 60 24 3.754 15 kA gg Div 3 (HPCS) Back up DG Fuel Oil HH Transfer Pump gg g E-25 480V Feeder from Bus GI-2, MCC to BOP Figure 0.3-16S 1 e 400 60+2n 3.754 15 kA Div 3 (HPCS) ESWS Strainer Motor F-44 480V Feeder from Bus Cl-2, MCC to BOP Figure 3.3-16S 3 25.5 480 60 26 3.756 15 gn

.. Div 3 (HPCS) ESWS Backwash Strainer valve E-49 480V Feeder f ross bus Cl-2. MCC to BOP Figure 3.1-16S 1 8 400 60t24 3.75 15 kA Div 3 (HPCS) ESWS Return Header Isolation valve

• This figure includes an allowance for an additional ESW Pump (1133 HP) which can be connected manually by the operator. Actual steady state load for 6900v feeder f rom buses E and F is 1202 for each feeder. ~ ~ " ~ ~ ~ ~ ~ ~ ~

%M (D M.

. 4 O

HO UI M I i

Table 8.3-10 (Continued)

NUCLEAR ISLAND ONSITE AC AND DC POWER SYSTEM / BOP INTERFACES ,' _

3 Blas Mas $mWe Interface Beforence SS Inrush Nom Freq Allowable Available Number Interface Description F12ure HP/kVA MA_ Volt. Hs BOP VD SC Current -

E-59 480V Feeder from Bue El-2. MCC to BOP Figure 8.3-16P 15 --

480 60924 3.5% 25 kA Div 1 Fuel 021 storage Tank peceptacle E-60 400v Feeder from Bus F1-2. MCC to BOP rigure 0.3-16P 15 --

480 60t2n 3.54 25 kA Div 2 Fuel Oil Storage Tank Receptacle E-61 480V Feeder from Bus C1-2. MCC to BOP Figure 0.3-16S 15 --

480 60 24 3.5% 25 kA Day 3 (HPCS) DG Fuel Oa! Storage Tank peceptacle E 480V Feeder from MCC B1-1 to Steam- Figure 0.3-16C 7.5 40 400 60229 3.50 35 kA E-55 line Drain valvee &D y

E-74 From Recirc Pump *A* Current Trans- Figure 0.3-3a SA -- -- 60 25 -- - W former to BOP Switchgear Device E-76 From Rectre Pump *B" Current Trans- Figure 0.3-le SA -- - 60?24 -- -- Z former to BOP Swatchgear Device C3 O W E-02 ESW Pump Station Day 3 Area Supply Figure 8.3-16S 2 20 480 60t24 3.754 15 kh '

O til

• from CE Div 3 MCC-GL-2 M (f1 Gb [vj (g) 8 E-84 445) Power reed for Excess Water Pump Figure 0.3-16F 25 140 480 60*2s St 35 kA y.

H A. (81 (Badwastel G17 from MCC Al-1 y E-84 (87) Power Feed for MOV *A* (*S*) G17 Figure 0.3-16F 0.5 5 400 60t24 3.754 15 kA NM from MCC A3-1 M E 120 Volt AC Feeder from Bus J1 to 1311 Signal - 120 -- == ==

E-!!! Audio Alarre (AC)

E-34 (A-D) 125 VDC Battery Test reeder f rces figure 3.3-10 350A 125 -- 44 O

20 kA Dtv 1 Battery (E) to BOP VDC E- 35 (A.Bl 125 VDC Battery Test reeder from Div 4 Battery (H) to BOP Figure 8.3-19 150A -- 125 VDC

-- 49 15 kA

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E-36 (A-07 125 VDC Battery Test Feeder from Figure 8.3-18 250A --

125 -- 44 15 kA Div 2 Battery (F) to BOP VDC e

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Table 8.3-10 (Continued)

NUCLEAR ISLAND ONSITE AC AND DC POWER SYSTEM / BOP INTERFACES i

Mas Mas t.w Interface Deference SS Inrush Nous Frog Antowable Available Number Interf ace Descript ion Figure HP/kVA kVA Volt. Ma DOP VD 3CJ urrent E-30 (A-D) 125 VDC Battery Test feeder from Figure 0.3 18 100A -- 125 - 44 Div 3 Battery (G) to BOP VDC E-79 ESW Pump Station Div 3 Area Supply Figure 8.3-16s 2 20 480 60'2n 3.759 IS kA Fan "D* from CE Div 3 MCC Cl-2 E-00 FDR to ESW Pump Station Div 3 CFT FDR Figure 4.3-16$ $ -- 490 604 3.754 E-6 (A-BI 125 VDC Control FDR from Bus DC-E Figure 8.3-18 6 31 125 -- 84 20 kh SWGR to ESWS SWCp M

E-9 (A-B) 125 VDC Control FDR from BJs DC-F Figure 0.3-10 6 31 125 -- 86 l$ kA /

y SWGR to WSMS SWGR +' g y U g

CO y i ON w M a . j m N i M co / WN HH W (/) H

• I W

W ^

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sp M

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, s .u .. . u . . m 2,38 NUCLEAR ISLAND R2v. 15 19.3.8.5 QUESTION / RESPONSE G.5 (430.04) (Continued) and isolate these buses from the BOP. The feeder undervoltage relaying provides a second level of undervoltace protection ]

which satisfy the following requirements as stated in PSB-1.

B.1.a The selection of undervoltage and time delay setpoints will be determined from an analysis of the voltage requirements of the Class lE loads at all onsite system distribution levels; B.l.b.1) The GESSAR II design provides a time delay setting for the feeder undervoltage relaying to ensure the existence of a sustained degraded voltage condition.

Following this delay, an alarm in the control room will alert the operator to the degraded condition.

The operator would have the option, if necessary, to separate the Class lE distribution system from the degraded offsite power system and perform a manual bus transfer to the other offsite power source or the diesel-generator. A second time delay

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is initiated by the first alarm. If the undervoltage still exists at the end of the second time delay, the _

system will be automatically separated from the off-site power system. Receipt of a LOCA signal at any time during the second timing period will result in an immediate trip of the supply breaker from the off-site power source.

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Note that there are two time delays associated with the degraded voltage protection. The 'first time delay allows transient undervoltages to clear before initiating the second time delay. If the degraded _

19.3.8.5-2

GESSAR II 22A7007 238 NUCLEAR ISLAND Rev. 15 '

19.3.8.5 QUESTION / RESPONSE 8.5 (430.04) (Continued)

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voltage still persists at the time end of the first time delay, the second time delag before tripping 6's initiatecD

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to allow the operator to take manual corrective action. ,

i 1

I l

t 19.3.8.5-2a

esnAnna 2272A7007

,238 NUCLEAR ISLAND Rov. 15 19.3.8.5 QUESTION / RESPONSE 8.5 (430.04) (Continued)

B.1.b.2) The GESSAR II provides a second time delay.

B.l.C.1

&2) GESSAR II complies. Refer to Figure 8.3-2 "6900 volt Single Line Buses E & F," and Figure 8.3-14a, "HPCS Power System Simplified - One Line Diagram."

B.l.C.3 Divicier 1 and 2 Q GESSAR II complies. (Design details will be

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provided before the first Applicant references GESSAR II.) -

B.l.C.4 The voltage sensors (feeder undervoltage relaying) automatically initiate the disconnection of the offsite power sources whenever the voltage setpoint and the second time delay limits have been exceeded. ]

B.1.C.5 The GESSAR II design provides means for device testing and calibrating during plant operation.

B.l.C.6 GESSAR II complies.

B.l.d The Technical Specifications will include limiting conditions for operations, surveillance requirements and will be provided by the Applicants.

The trip. setpoints and the allowable values for the 1

second level voltage protection sensors and associated time delay devices are plant-unique items, which will be provided by the Applicant.

19.3.8.5-3 t

l l .

I. _ _ _ _ . , -. . .

Gl:Sa iR 11 22A700

• 238 NUCLEAR ISLAND Rev. 15 19.3'.8.5 QUESTION / RESPONSE 8.5 (430.04) (Continued)

Paragraph B.2 The GESSAR II design complies. For Division 1 and 2, the

] '

load shedding scheme is never bypassed. Bus transfer is always initiated at a bus voltage of 70% of rated by tripping the supply breaker. Load shed is then initiated at 30% of rated. This complies with the second paragraph of Section B.2 of PSB-1. There is no load shedding for the HPCS. It block starts the entire connected load. ,

Paragraph B.3 A voltage drop calculation was performed which shows that all safety related buses down to the 480V level provide full load operation voltages for safe continuous operation of all energized loads, based on a BOP supply voltage of 6.9KV +5%.

These calculations must be confirmed and checked when data for 7 the actual electrical equipment to be used is available. The results of the final calculations will be provided by the Applicant. ,

Ppargraph B.4

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This recommended testing procedure will be addressed by the t Applicant in the pre-operational test procedures in I

accordance with the requirements of PSB-1, Section B.4. j e

19.3.8.5-4

.