ML20039H301

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Forwards Info for NRC Review & Approval Prior to Incorporation Into SWESSAR-P1
ML20039H301
Person / Time
Site: 05000495
Issue date: 02/11/1977
From: William Kennedy
STONE & WEBSTER, INC.
To: Stolz J
Office of Nuclear Reactor Regulation
Shared Package
ML111090060 List: ... further results
References
FOIA-80-515, FOIA-80-555 NUDOCS 8201200126
Download: ML20039H301 (6)
v • d • e


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BGSchultz FPPaulitz AMorse RELevline RMMcMellon IMRicci/ Job Book-2 Duticci/Chrouo mangan

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February 11, 1977 RPS-251 (Follows RPS-250) l Mr. J. F. Stolz i

Chief Light Water Reactors Branch No.1 i

t Division of Project Management U. S. Nuclear Reactory Commission Washington, D. C.

20555 t

Dear Mr. Stolz:

DOCEET NO STN-50-495 S&W REFERENCE NUCLEAR PC*JER PLANT As stated in your " Report to the Advisory Committee on Reactor Safeguards" on the S'4ESSAR-P1/RESAR-3S design issued June 1976, any requirements placed upon the balance of plant by the RESAR-3S residual heat removal (RER) system vill be met and incorporated into 54ESSAR prior to issuance of Preliminary Design Approval. The criteria for the design function of the residual heat removal system is specified in RESAR-3S and'the RESAR-3S Safety Evaluation Report, NUREG-0104.

t The enclosed information is provided for NRC review to meet the specified i

criteria.

i Upon satisfactory review and approval by the NRC staff the enclosed infor-mation vill be incorporated into F4ESSAR-P1.

j Yery t y yours

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Enclosure /ha s

8201200126 810403 PDR FOIA MADDEN 80-515 PDR

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Discussion r

RESAR-3S interface of 8 3.1.4 states:

electrical power supplies to the RHR suction isolat "A

k rovide Class 1E RHR subsystem in operation and for isolation of thma on valves in such a t

o RCS."

or placing an e R3R subsystem from the come to the conclusion that the design modificatio s requirement and has proposed attached change to S'4ESSAR-P1 meets the desias described i below.

gn criteria listed i'

The following criteria were used for the design m difi 1

dence for residual removal system isolation va o

cation:

erlock indepen-tained.

residual heat removal system shall satisfy the int i

es shall be main-of the face _ requirements-provided in Table 8.1-2 of RESAR 3S b t

of the inter-

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interfaces.

I y flexible 2.

The balance of plant interface for the RHR at the 7-2 of the RESAR-3S SER. supply boundary shall satisfy all the nuclear steam e in Table 3.

The single failure criteria shall be me.t.

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s SVESSAR-P1 Table 8.4-4 INTERFACE

{tHR SUCTICN VALVES 8701 A,5, 8702A,B CRITERIA The power supply electrical equipment location, control, instrument, and power cable routing vill be designed so that a single failure vill not per-clude the operation and isolation of the RER system. Failures in pressure 7

interlocks and instrument along with the necessary operator action is out-side of this scope and is discussed in the NSSS SAR section 7.6.

DESIGN BASIS The design basis will be the sane as those discussed in chapter 8 for the Class 1E electrical system.

DESCRIPTION An independent power supply is provided for each of the four motor operated valves. This power arrangement is shown in Figure 8.4-1 sheet 1, and the physical relation of the valves to the reactor coolant loops and the RHR pumps along with the power assignement is shown in Figure 8.4-1 sheet 2.

The power arrangement presently in RESAR-3S and the SWESSAR-P1 arrangement allowed by flexible interface are shown below:

Equiement RESAR-3S SWESSAR-P1 Valve 8702A Train B (Purple)

Channel III (Blue)

Valve 8701B Train A (Orange)

Channel IV (Yellov)

Valve 8701A Train A (Orange)

Train A (Orange)

Valve 8702B Train B (Purple)

Train B (Purple)

Nota that channel I (R) d c supply is used as a control power supply for train A (0) a e equipment. There vill be no separation, Regulatory Guide 1.75, between (0) and (R) equipment or cables.

The separtion by cable vill be by service level only. This relationship is similiar for train B (P) and channel 2 (W).

Additional flexible interface requirements are the electrical isolation of pressure interlocks between pressure transmitter PT 405 (R) and valve 8702A (Y) control. A similiar requirement is imposed between PT 403 (V) and valve 8701B (B) control.

The physical separation of redundant electrical equipment is shown by dashed lines in Figure 8.4-1 sheet 1.

The redundant Class 1E systems, train A (0)/

channel I (R), train B (P)/ channel II (V), channel III (B), channel IV (Y),

physical separation and cable routing are shown ja Figure 8 3-2 sheet 1 thru 7.

The redundant instrument and control cables vill be routed from their respec-tive switch gaar areas or tunnels to the control room via separate spreading

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FIG. 8.4 - 1 (SH. 2)

INTERFACE RHR SUCTION VALV E REFERENCE NUCLEAR POWER PLANT l

SWESS AR -Pi

.c Table 8.4-4 (cont.)

ANALYSIS FAILURE SYSTEM UNAVAILABILITY SYSTEM AVAILABILITV Train A (0)

Flow Path A Flow Path B AC Power RHR Pu=p A Flow Path A Flov Path B MOV 8701A Flow Path A Flow Path B i

Channel 3 (B)

Flow Path A Flow Path B power to MOV 8702A MOV 8702A Flow Path A Flow Path B Train B (P)

Flow Path B Flow Path A AC Power RHR Punp B Flow Path B Flow Path A MOV 8701B Flov Path B Flow Path A Channel 4 (Y)

Flow Path B Flow Path A power to MOV 8702B i

MOV 8702B Flow Path B Flow Path A i

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UfelTED STATES NUCLEAR REGULATORY COMMISSION

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VV ASHINGTON. D.

C.' 20S55 301-492-7000 FACSIMILE SERVICE REQUEST 03fd> T DATE:

o MESSAGE TO:

th) bbbb11-t TELECOPY NUMBER: 2dN Nk lD 3 h

Attr0MATIC:

h No VERIFICATION NUMBER 04 3M Ol l y M4L l

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PLUS INSTRUCTION SHEET d- ) LYNGH0d Rdbr I

STATE & CITY

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j MESSAGE FROM:

TELECOPY NUMBER (301) 492-8110 RAPIFAX AUTOMATIC (301) 492-7617 3M VRC AUTOMATIC VERIFICATION NUMBER (301) 492-7371 BUILDING ot O OFFICE PHONE M'2 43 MAIL STOP l1d CLASS OF SERVICE:

Overnight 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> h

2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i

I bour Immediate SPECIAL INSTRUCTIONS:

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