ML20071J681

Submits Remaining Responses to NRC 820107 Request for Addl Info Re Seismic Qualification of Auxiliary Feedwater Sys. Tables of Nonseismically Qualified Electrical Circuits & Control Devices Encl

ML20071J681
Person / Time
Site:	Crystal River
Issue date:	04/20/1982
From:	Mardis D FLORIDA POWER CORP.
To:	Stolz J Office of Nuclear Reactor Regulation
References
3F-0482-06, GL-81-14, TAC-43647, NUDOCS 8204270334
Download: ML20071J681 (6)

Text

- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

l I

-n 4 @ yN$h 2M@

0 w y.?^

W v $ eg f

• [ Gl t w ri  % l G'dOYCiQ M

Power C 0 A P O n a T e o es April 20,1982

1. 3F-0482-06 File: 3-0-3-a-3

/ f\ ' I C3 #

Mr. John F. Stolz, Chief V g-Operating Reactors Branch #4 Division of Licensing

.h .

'S-'

1/ -

41 U.S. Nuclear Regulatory Commission 1' ~

Washington, D.C. 20555 i

, , ,,982

'1 * ;

n : n e r ,. , ..

? ~

Y

Subject:

Crystal River Unit 3 O ~" "

Docket No. 50-302 x Operating License No. DPR-72 Seismic Qualification of Auxiliary (Emergency) Y ( en - Feedwater Shg[2

Dear Mr. Stolz:

By letter dated January 7,1982, the NRC requested additional information on seismic qualification of the Auxiliary (Emergency) Feedwater System (EFWS). Florida Power Corporation (FPC) submitted a partial response to your additional information request on February 26,1982. FPC hereby submits the remaining responses to your questions.

Question 2(b) Mention what vertical seismic input was used for floors with fundamental frequency less than 25 cps.

Response 2(b) Within CR-3's seismically qualified structures, the only floors with fundamental frequencies less than 25 cps are the steel frame supported floor slabs of the containment interior structure. The seismic qualification for equipment and systems supported by these floors was based upon use of a vertical input which was two-thirds (2/3) of the horizontal response spectrum for the respective elevation.

Question 4 Table 1 of your response indicates that certain power supplies and the initiation and control system for the EFWS are not seismically qualified:

(a) Identify those non-seismically qualified items.

(b) Describe your program and schedule for their upgrading or justify why upgrading is not required.

col

//

8204270334 j General Office 3201 inirty-tourtn street soutn . P O Box 14042, st. Petersburg Fionda 33733 813-866 5151

_ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . 1

Mr. John F. Stolz April 20,1982 Page 2 (c) Describe the results of your walkdowns of these items, along with the scope and schedule of any resulting corrective actions which were identified.

- Response 4 (a) See Attachment I for identification of EFWS associated circuits which are not seismically qualified, and - Attachment 2 for identification of EFWS associated initiation and control devices which are mounted within non-seismically qualified cabinets or panels.

(b) Included within the ongoing EFWS upgrade (reference letters dated December 19, 1980, and August 11, 1981) is the seismic qualification of all the power and the initiation and control circuits required for EFWS function.

(c) The walkdown reported in our July 14, 1981 response to your February 10, 1981 information request provided the required evaluation of the EFWS associated power and control. circuits (Note: deviations 8,9,10, and 11 are the problems identified).

In addition, a walkdown of the main control board devices was performed during a recent survey of panels and cabinets for the EFWS upgrade project. - This survey was performcd - for the -

purpose of incorporating additional instrumentation and control devices on the existing main control board and determining the feasibility of upgrading the seismic qualification of the Plant Secondary Auxiliary section of the main control board.

Along with the main control board survey, a walkdown of the Non-Nuclear Instrumentation and Integrated Control System cabinets was performed by the same personnel. The walkdown identified no significant deviations from purdent engineering practices which could cause equipment failures during a seismic event.

i If you have any further questions, please contact this office.

Very truly yours,

& . Mk David G. Mardis Acting Manager Nuclear Licensing RAW:mm cc: Mr. 3. P. O'Reilly, Regional Administrator Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 3100 Atlanta, GA 30303

ATTACHMENT 1 NON-SEISMIC QUALIFIED ELECTRICAL CIRCUITS CKT. CKT.

EQUIPMENT NUMBER FUNCTION EFV-1 EFE2 POWER EFE4 CONTROL EFE5 "

EFE6 "

EFV-2 EFE12 POWER EFE14 CONTROL EFE15 "

EFE16 EFV-3 EFCI "

EFC3 "

EFV-4 EFC4 "

EFC6 "

EFV-7 EFC7 "

EFC9 "

EFV-8 EFC10 "

EFCl2 "

EFV-Il EFE24 "

EFE25 EFE26 EFE27 EFV-14 EFE34 "

EFE35 EFE36 EFE37 EFV-32 EFE44 "

EFE45 "

EFE46 "

EFE47 l

EFV-33 "

EFE54 EFE55 EFE56 EFE57 FWV-33 FWE25 POWER l "

FWE26 i

1

CKT. CKT.

EQUIPMENT NUMBER FUNCTION FWV-33 FWE27 POWER FWE28 FWE29 FWE30 FWE31 FWE32 FWE147 FWE148 FWE151 FWE152 FWV-34 FWE9 POWER FWE10 FWEli POWER FWE12 FWE13 FWE14 FWE16 FWE37 FWE143 FWE144 FWV-35 FWEl POWER FWE2 FWE3 FWE4 CONTROL FWE5 FWE6 FWE8 FWE36 FWE141 FWE142 FWF47 FWF194 FWV-36 FWE17 POWER FWE18 FWE19 FWE20 FWE21 FWE22 FWE24 FWE145 FWE146 2

l l

CKT. CKT.

E_QUIPMENT NUMBER FUNCTION FWV-39 FWE131 POWER FWE132 CONTROL FWE133 "

FWE134 "

FWE135 "

FWE136 "

FWV-40 FWE121 POWER FWE122 CONTROL FWE123 "

FWE124 "

FWE125 "

FWE126 "

ASV-5 ASE1 POWER ASE2 "

ASE3 "

ASE4 CONTROL ASE5 "

ASE6 "

ASE7 "

ASE10 "

ASE11 "

MSV-55 MSEll POWER MSE12 "

MSE13 CONTROL MSE14 "

MSE15 MSE16 MSE17 POWER MSV-56 MSE1 POWER MSE2 "

MSE3 CONTROL MSE4 MSE5 "

MSE6 "

MSE7 POWER 3

ATTACHMENT 2 NON-SEISMICALLY QUALIFIED CONTROL DEVICES PSA Panel CDST Level indicator (CD-67-LI)

EFP - 3A (Motor) Control Station (G A) --

Train A EFV - 1 Control Station (GH) -

Train A EFV-2 Control Station (GC) -

Train A EFV-3 Control Station (GB) -

Non-Safety Related (NSR)

EFV-4 Control Station (GG) -

NSR EFV-7 Control Station (GD) -

NSR EFV-8 Control Station (G3) -

NSR MSV-55 Control Station (GE) -

Train B MSV-56 Control Station (GF) -

Train B ASV-5 Control Station (GN) -

Train B i

FWV-34 Control Station (GK) -

Train B FWV-35 Control Station (GL) -

Train A EF Flow Indicators (FW-312-FI and FW-313-FI)

ICS Panel FWV-39 H/A Station FWV-40 H/A Station OTSG A & B LevelIndication OTSG A & B Startup or Emergency Feedwater Flow Also, the following functions have been identified and are associated with these cabinets:

ICS Cabinet Steam Generator Level Control of FWV-39 and 40 NNI Cabinet a) Steam Generator Level, Startup or Emergency Feedwater Flow, Pressure, and Temperature Instrument Signals b) Steam Generator Level, Startup or Emergency Feedwater Flow, Pressure, and Temperature Instrument Signals (Redundant Channel) c) EFP Actuation Signals

+v- ---w+ - m m